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| issue date = 03/31/1994
| issue date = 03/31/1994
| title = ISI Activities - 90 Day Rept Eleventh Refueling Outage Salem Generating Station Unit 1
| title = ISI Activities - 90 Day Rept Eleventh Refueling Outage Salem Generating Station Unit 1
| author name = LAKE L
| author name = Lake L
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:;.
{{#Wiki_filter:FORM NIS-1 OWNER 1 S DATA REPORT . . FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L    Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J.       07101
* L 2. 3 . 4. 5. 6. 7. 8. 9. FORM NIS-1 OWNER 1 S DATA REPORT ... FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
N/A. Commercial Service Date 7/1/77 .. National Board Number for Unit: N/A. Examination Dates: 08-17-92 through 02-02-94.
: 3. Plant Unit 1
This report covers the examinations that were conducted during the 11th Refueling Outage. Components Inspected.
: 4. Owner's Certificate of Authorization (if required) N/A.
MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER APPURTENANCE OR INSTALLER OR INSTALLER PROVINCE NATIONAL #1 Reactor Vessel #11 Steam Generator  
: 5. Commercial Service Date 7/1/77..
#12 Steam Generator  
: 6. National Board Number for Unit: N/A.
#13 Steam Generator  
: 7. Examination Dates: 08-17-92 through 02-02-94.
#14 Steam Generator  
: 8. This report covers the examinations that were conducted during the 11th Refueling Outage.
#1 Regen. Ht. Exch. #1 Rx. Coolant Filter Combustion Engineering Westinghouse Tampa Div. P.O. Box 19218 Tampa, FL 33616 II II II II II II Sentry Equip. Corp. Oconomowoc, WI Commercial Filters, Corp. Lebanon, IN SER. NO. NUMBER BOARD NO. 66201 Head 66101 Vessel N/A 20757 1003 N/A 68-10 1022 N/A 68-08 1023 N/A 68-09 1203 N/A 68-51 4195-A4 N/A 385, 386, 7, 8, 9 387 101238 N/A 1193 -----9404260399'
: 9. Components Inspected.
-----, PDR ADOCK.05000272 G . , PDR Page 1 of 22  
MANUFACTURER     STATION OR COMPONENTS OR MANUFACTURER     OR INSTALLER     PROVINCE  NATIONAL APPURTENANCE OR INSTALLER         SER. NO.        NUMBER    BOARD NO.
*
          #1 Reactor     Combustion        66201 Head Vessel          Engineering      66101 Vessel       N/A      20757
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES i. owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. 3. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 4. 5. Owner's Certificate of Authorization (if required)
          #11 Steam       Westinghouse      1003              N/A      68-10 Generator       Tampa Div.
N/A. Commercial Service Date 7/1/77. 6. National Board Number for Unit N/A. 7. 9. Examination Dates: 08-17-92 through 02-02-94.
P.O. Box 19218 Tampa, FL 33616
Components Inspected (cont'd):
          #12 Steam Generator       II  II 1022                N/A    68-08
MANUFACTURER COMPONENTS OR MANUFACTURER OR INSTALLER APPURTENANCE OR INSTALLER SER. NO. #1 Pressur-Delta Southern 1011 izer Chemical Volume & Control Piping System Component Cooling Sys. Containment Spray Piping System Mains team Piping sys. #11 RHR Heat Exchanger United Engineers
          #13 Steam Generator       II  II 1023                N/A    68-09
& Constructors (UE&C) 30 South N/A 17th st., Phila. PA 19101 UE&C N/A UE&C N/A UE&C N/A Engineers
          #14 Steam Generator       II  II 1203                N/A    68-51
& Sl5860-C Fabricators, Inc. Page 2 of 22 STATION OR PROVINCE NATIONAL NUMBER BOARD NO. N/A 68-8 N/A N/A N/A N/A N/A N/A N/A N/A N/A 122
          #1 Regen.       Sentry Equip. 4195-A4            N/A    385, 386, Ht. Exch.       Corp.            7, 8, 9                    387 Oconomowoc, WI
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 3 . 4. 5. 6. 7. 9. owner's Certificate of Authorization (if required)
          #1 Rx.         Commercial        101238              N/A    1193 Coolant         Filters, Corp.
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
Filter         Lebanon, IN
Components Inspected (cont'd):
  --- - -9404260399' 940420~ -- ---,
MANUFACTURER COMPONENTS OR MANUFACTURER OR INSTALLER APPURTENANCE OR INSTALLER SER. NO. Pressurizer UE&C N/A Relief Piping Sys. Pressurizer UE&C N/A Spray Sys. Reactor UE&C N/A Coolant Piping Sys Residual UE&C N/A Heat Removal System Service Water UE&C N/A System Steam Gen. UE&C N/A Feed Piping System Safety UE&C N/A Injection Piping Sys. Page 3 of 22 STATION OR PROVINCE NATIONAL NUMBER BOARD NO. N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
PDR ADOCK.05000272 G            . PDR
: i.
        ,                               Page 1 of 22
* 2 . 3 . 4 . 5. 6 . 7. 10. 1.0 *
 
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
: i. owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
Abstracts of Examinations:
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
This report also contains augmented examinations required by the Salem Technical Specification, Regulatory Guides, lars and Bulletins issued by the United States Nuclear Regulatory Commission.
: 3. Plant Unit 1
Examinations were conducted by PSE&G as well as companies under contract to PSE&G. The following is a brief summary with further details found in the attached report and on file at the Salem Generating Station. Since nearly all inservice examination requirements can be found in Salem's Technical Specifications, this summary lists these requirements first arranged by Technical fication paragraph number followed by applicable NRC lars and Bulletins . Page 4 of 22 I 1.
: 4. Owner's Certificate of Authorization (if required) N/A.
* 2 . 3. 4. 5. 6. 7. 11.
: 5. Commercial Service Date 7/1/77.
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
: 6. National Board Number for Unit N/A.
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
: 7. Examination Dates: 08-17-92 through 02-02-94.
Examination Summary 11.1 Technical Specification 4.0.5 -ASME XI (1983 Edition) During the Fall 1993 refueling outage, PSE&G, MQS and SwRI personnel performed nondestructive examinations (NDE) of selected Class 1, Class 2 and Class 3 nents at the Salem Unit 1 Generating Station. These examinations constituted the fourth inservice tion (ISI) of the second inspection interval of mercial operation.
: 9. Components Inspected (cont'd):
11.1.1 ISI Examination Southwest Research Institute (SwRI) under the direction of the Salem ISI Group conducted seventy-six (76) manual ultrasonic, one dred and four (104) liquid penetrant, and fourteen (14) magnetic particle examinations.
MANUFACTURER STATION OR COMPONENTS OR  MANUFACTURER  OR INSTALLER  PROVINCE NATIONAL APPURTENANCE    OR INSTALLER    SER. NO.      NUMBER  BOARD NO.
Examinations were conducted on the following systems: Class .l Vessels Piping Pumps Pressurizer RPV Steam Generator
  #1 Pressur-     Delta Southern      1011        N/A      68-8 izer Chemical        United Engineers Volume &        & Constructors Control        (UE&C) 30 South      N/A        N/A      N/A Piping          17th st., Phila.
#11 through #14 Chemical and Volume Control Reactor Coolant System Pressurizer Relief System Pressurizer Spray System Residual Heat Removal System Safety Injection System Reactor Coolant Pumps #12 and #14 Page 5 of 22
System          PA    19101 Component        UE&C                N/A        N/A      N/A Cooling Sys.
: i.
Containment      UE&C                N/A        N/A      N/A Spray Piping System Mains team      UE&C                N/A        N/A      N/A Piping sys.
* 2. 3. 4. 5. 6. 7. 11.
  #11 RHR Heat    Engineers &        Sl5860-C    N/A      122 Exchanger        Fabricators, Inc.
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required}
Page 2 of 22
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
 
Examination Summary (Cont'd} Integrally Welded Attachments Class .6. Vessels Piping Reactor Coolant Pumps #12 and #14 Safety Injection Head Tank #11 Reactor Coolant Filter Regenerative Heat Exchanger Main Steam System Steam Generator Feed System Containment Spray system Residual Heat Removal System Pressurizer Relief System Chemical Volume Control system Safety Injection System Integrally Welded Attachments Residual Heat Removal System Safety Injection System Main Steam System The following nonconformance was reported by SWRI: A PT examination on weld 4-SJ-1172-5 (Summary No. 131200}, revealed six (6) linear able indications.
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L    Owner: Public Service Electric & Gas Co., 80 Park Plaza
CNF 1-1 was issued by SWRI and dispositioned by PSE&G as follows: After cosmetically blending these tions, a PT re-exam was performed with no linear indications identified.
* 2.
There were no other*unacceptable indications identified . Page 6 of 22
3.
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES i. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 3. Plant Unit 1 4. owner's Certificate of Authorization (if required)
4.
N/A. 5. Commercial Service Date 7/1/77. 6. National Board Number for Unit N/A. 7. Examination Dates: 08-17-92 through 02-02-94.
5.
6.
Newark, N.J.
Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.
Commercial Service Date 7/1/77.
National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 9. Components Inspected (cont'd):
MANUFACTURER STATION OR COMPONENTS OR  MANUFACTURER  OR INSTALLER  PROVINCE  NATIONAL APPURTENANCE  OR INSTALLER    SER. NO. NUMBER    BOARD NO.
Pressurizer    UE&C            N/A          N/A        N/A Relief Piping Sys.
Pressurizer    UE&C            N/A          N/A        N/A Spray Sys.
Reactor        UE&C            N/A          N/A         N/A Coolant Piping Sys Residual        UE&C            N/A          N/A        N/A Heat Removal System Service Water  UE&C            N/A          N/A        N/A System Steam Gen.     UE&C            N/A          N/A         N/A Feed Piping System Safety          UE&C             N/A         N/A         N/A Injection Piping Sys.
Page 3 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
: i. Owner: Public Service Electric & Gas Co., 80 Park Plaza
* Newark, N.J. 07101
: 2. Plant:  Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
: 3. Plant Unit 1
: 4. Owner's Certificate of Authorization (if required) N/A.
: 5. Commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 10. Abstracts of Examinations:
1.0   This report also contains augmented examinations required by the Salem Technical Specification, Regulatory Guides, Circu-lars and Bulletins issued by the United States Nuclear Regulatory Commission.
Examinations were conducted by PSE&G as well as companies under contract to PSE&G. The following is a brief summary with further details found in the attached report and on file at the Salem Generating Station.
Since nearly all inservice examination requirements can be found in Salem's Technical Specifications, this summary lists these requirements first arranged by Technical Speci-fication paragraph number followed by applicable NRC Circu-lars and Bulletins .
Page 4 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES I
: 1. Owner:  Public Service Electric & Gas Co., 80 Park Plaza
* 2.
3.
4.
5.
6.
Newark, N.J.
Plant:
Plant Unit 1 07101 Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.
Commercial Service Date 7/1/77.
National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary 11.1  Technical Specification 4.0.5 - ASME XI (1983 Edition)
During the Fall 1993 refueling outage, PSE&G, MQS and SwRI personnel performed nondestructive examinations (NDE) of selected Class 1, Class 2 and Class 3 compo-nents at the Salem Unit 1 Generating Station. These examinations constituted the fourth inservice examina-tion (ISI) of the second inspection interval of com-mercial operation.
11.1.1 ISI Examination Southwest Research Institute (SwRI) under the direction of the Salem ISI Group conducted seventy-six (76) manual ultrasonic, one hun-dred and four (104) liquid penetrant, and fourteen (14) magnetic particle examinations.
Examinations were conducted on the following systems:
Class .l Vessels Pressurizer RPV Steam Generator #11 through #14 Piping Chemical and Volume Control Reactor Coolant System Pressurizer Relief System Pressurizer Spray System Residual Heat Removal System Safety Injection System Pumps Reactor Coolant Pumps #12 and #14 Page 5 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
: i. Owner: Public Service Electric & Gas Co., 80 Park Plaza
* 2.
3.
4.
5.
6.
Newark, N.J.
Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required} N/A.
Commercial Service Date 7/1/77.
National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (Cont'd}
Integrally Welded Attachments Reactor Coolant Pumps #12 and #14 Safety Injection Class .6.
Vessels Head Tank #11 Reactor Coolant Filter Regenerative Heat Exchanger Piping Main Steam System Steam Generator Feed System Containment Spray system Residual Heat Removal System Pressurizer Relief System Chemical Volume Control system Safety Injection System Integrally Welded Attachments Residual Heat Removal System Safety Injection System Main Steam System The following nonconformance was reported by SWRI:
A PT examination on weld 4-SJ-1172-5 (Summary No. 131200}, revealed six (6) linear record-able indications. CNF 1-1 was issued by SWRI and dispositioned by PSE&G as follows:
After cosmetically blending these indica-tions, a PT re-exam was performed with no linear indications identified.
There were no other*unacceptable indications identified .
Page 6 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
: i. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
: 3. Plant Unit 1
: 4. owner's Certificate of Authorization (if required) N/A.
: 5. Commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
11.1.2 Visual Examination on Valves and Bolting The Salem ISI Group conducted twenty-nine (29) Class 1 bolting exams and one (1) Class 1 valve internal exam. There were several Class 1 Bolting exam lies noted, including boric acid accumulation, nuts seized on the stud or bolt, etc .. Work orders and/or deficiency reports were ed to document and correct all anomalies.
11.1.2 Visual Examination on Valves and Bolting The Salem ISI Group conducted twenty-nine (29)
NOTE: No additional exams were required.
Class 1 bolting exams and one (1) Class 1 valve internal exam.
Examinations were conducted on the following systems: Valves Pressurizer Relief System Safety Injection System Residual Heat Removal System Chemical Volume and Control System Pressurizer Spray System There were no unacceptable indications fied. 11.1.3 Visual Examination of Supports The Salem !SI Group conducted and/or nated visual examinations on seventeen (17) Class I, five (5) Class II and one hundred forty eight (148) Class III supports . Page 7 of 22
There were several Class 1 Bolting exam anoma-lies noted, including boric acid accumulation, nuts seized on the stud or bolt, etc .. Work orders and/or deficiency reports were generat-ed to document and correct all anomalies.
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 3. Plant Unit 1 4. owner's Certificate of Authorization (if required)
NOTE: No additional exams were required.
N/A. 5. Commercial Service Date 7/1/77.
Examinations were conducted on the following systems:
* 6. National Board Number for Unit N/A. 7. Examination Dates: 08-17-92 through 02-02-94.
Valves Pressurizer Relief System Safety Injection System Residual Heat Removal System Chemical Volume and Control System Pressurizer Spray System There were no unacceptable indications identi-fied.
11.1.3 Visual Examination of Supports The Salem !SI Group conducted and/or coordi-nated visual examinations on seventeen (17)
Class I, five (5) Class II and one hundred forty eight (148) Class III supports .
Page 7 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
: 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
: 3. Plant Unit 1
: 4. owner's Certificate of Authorization (if required) N/A.
: 5. Commercial Service Date 7/1/77. *
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
Examinations were conducted on the following systems: Auxiliary Feedwater Chemical & Volume Control Component Cooling Containment Spray Residual Heat Removal Main Steam Pressurizer Relief Pressurizing Safety Injection Service Water There were no unacceptable indications fied. 11.1.4 System Pressure Tests System leakage exams were performed in ance with ASME Section XI on all Class I systems. A system leakage test was performed with the Reactor Coolant System in mode 3 (normal operating temperature and pressure) with the insulation installed.
Examinations were conducted on the following systems:
Auxiliary Feedwater       Main Steam Chemical & Volume Control Pressurizer Relief Component Cooling         Pressurizing Containment Spray         Safety Injection Residual Heat Removal     Service Water There were no unacceptable indications identi-fied.
11.1.4 System Pressure Tests System leakage exams were performed in accord-ance with ASME Section XI on all Class I systems.
A system leakage test was performed with the Reactor Coolant System in mode 3 (normal operating temperature and pressure) with the insulation installed. No pressure boundary leakage was detected. Minor mechanical leak-age was identified and work requests were initiated for repairs.
Thirty two (32) System Pressure Tests (SPT) were completed during a System Functional or Inservice Test on Nuclear Class 1, 2 and 3 components in accordance with ASME Section XI.
No pressure boundary leakage was detected.
No pressure boundary leakage was detected.
Minor mechanical age was identified and work requests were initiated for repairs. Thirty two (32) System Pressure Tests (SPT) were completed during a System Functional or Inservice Test on Nuclear Class 1, 2 and 3 components in accordance with ASME Section XI. No pressure boundary leakage was detected.
Work requests were initiated to correct minor mechanical leakage that was identified .
Work requests were initiated to correct minor mechanical leakage that was identified . Page 8 of 22
Page 8 of 22
: i.
 
* 2. 3. 4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
: i. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
Examination Summary (cont'd):
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
11.2* Preservice Examinations were performed on the #11 through #14 SJ17 valve replacement welds per DCP 1E0-2309. The welds that were replaced to facilitate the valve replacement are listed below: !SIC !SIC PSE&G  
: 3. Plant Unit 1
: 4. Owner's Certificate of Authorization (if required) N/A.
: 5. Commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
11.2* Preservice Examinations were performed on the #11 through #14 SJ17 valve replacement welds per DCP 1E0-2309.
The welds that were replaced to facilitate the valve replacement are listed below:
              !SIC                 !SIC                   PSE&G


==SUMMARY==
==SUMMARY==
  # COMPONENT ID WELD # 174900 RH-3282-77F-A 175001 RH-3282-76F-A 175101 RH-3282-75F-A 175500 RH-3295-111F-A 179601 RH-3295-110F-A 179701 RH-3295-109F-A 184600 RH-3269-43F-A 184700 RH-3269-42F-A 184801 RH-3268-41F-A 190100 RH-3256-4F-A 190201 RH-3256-3F-A 190301 RH-3256-2F-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted. Preservice Examination was performed on Safety tion System piping weids, due to the replacement of two (2) orifices per DCP lEC-3260.
  #         COMPONENT ID               WELD #
The welds that were replaced to facilitate the placement of the orifices are listed below: !SIC  
174900           1~-SJ-1142-49R        RH-3282-77F-A 175001           1~-SJ-1142-50R        RH-3282-76F-A 175101           1~-SJ-1142-51R        RH-3282-75F-A 175500           1~-SJ-1132-39R        RH-3295-111F-A 179601           1~-SJ-1132-40R        RH-3295-110F-A 179701           1~-SJ-1132-41R        RH-3295-109F-A 184600           1~-SJ-1122-41R        RH-3269-43F-A 184700           1~-SJ-1122-42R        RH-3269-42F-A 184801           1~-SJ-1122-43R        RH-3268-41F-A 190100           1~-SJ-1112-49R        RH-3256-4F-A 190201           1~-SJ-1112-50R        RH-3256-3F-A 190301           1~-SJ-1112-351        RH-3256-2F-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted.
Preservice Examination was performed on Safety Injec-tion System piping weids, due to the replacement of two (2) orifices per DCP lEC-3260.
The welds that were replaced to facilitate the re-placement of the orifices are listed below:
              !SIC                  !SIC                   PSE&G


==SUMMARY==
==SUMMARY==
  # 386600 386620 387100 387120 !SIC COMPONENT ID 2-SJ-2126-6R 2-SJ-2126-7R 2-SJ-2123-6R 2-SJ-2123-7R PSE&G WELD # SI-5-256B-A SI-5-257B-A SI-1-211C-B SI-1-212C-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted. Page 9 of 22
  #         COMPONENT ID               WELD #
' 1.
386600            2-SJ-2126-6R           SI-5-256B-A 386620            2-SJ-2126-7R           SI-5-257B-A 387100            2-SJ-2123-6R            SI-1-211C-B 387120            2-SJ-2123-7R            SI-1-212C-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted.
* 2. 3. 4. 5. 6. 7. 11. *
Page 9 of 22
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
 
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
Examination Summary (cont'd):
: 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
11.3 Technical Specification 4.4.6.0 -Steam Generator Tube Eddy Current Inspection.
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
: 11. 3. 1 Overview 11. 3. 2 The original scope of Salem lRll outage was comprised of 20% bobbin and 20% top of hot leg tubesheet in all four Steam Generators.
: 3. Plant Unit 1
In addition, a twelve hour* window was allotted for RPC testing of dented hot leg tube support plate Top of Tubesheet RPC Inspection The tube expansion in the Steam Generators at Salem Unit 1 were made using the WEXTEX ess (explosive expansions).
: 4. owner's Certificate of Authorization (if required) N/A.
History of Wextex units has shown some cracking in the expansion transition.
: 5. Commercial Service Date 7/1/77.
Cracking of the WEXTEX region can be axial, circumferential or oblique in tation as detected by RPC. The extent of circumferential cracking and the extent to which an axial indication extends into the transition zone are critical measurements.
: 6. National Board Number for Unit N/A.
Due to indications found, the initial scope was expanded by a total of 612 tubes in Steam Generator  
: 7. Examination Dates: 08-17-92 through 02-02-94.
#11. One circumferential and seven axial indications were detected in this Steam Generator.
: 11. Examination Summary (cont'd):
None of these indications exceeded the structural integrity limits. Three of these indications were OD initiated.
11.3 Technical Specification 4.4.6.0 - Steam Generator Tube Eddy Current Inspection.
These indications are believed to have been caused by ODSCC rather than residual stress from the WEXTEX expansion process. There were no expansions of Top of Tubesheet RPC inspections in #12 Steam Generator.
: 11. 3. 1 Overview The original scope of Salem lRll outage was comprised of 20% bobbin and 20% top of hot leg tubesheet in all four Steam Generators. In addition, a twelve hour* window was allotted for RPC testing of dented hot leg tube support plate ~ntersections.
708 tubes were inspected which represents 20.9% of the Steam Generator . Page 10 of 22
: 11. 3. 2 Top of Tubesheet RPC Inspection The tube expansion in the Steam Generators at Salem Unit 1 were made using the WEXTEX proc-ess (explosive expansions). History of Wextex units has shown some cracking in the expansion transition. Cracking of the WEXTEX region can be axial, circumferential or oblique in orien-tation as detected by RPC. The extent of circumferential cracking and the extent to which an axial indication extends into the transition zone are critical measurements.
* ' 1 . 2. 3. 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
Due to indications found, the initial scope was expanded by a total of 612 tubes in Steam Generator #11. One circumferential and seven axial indications were detected in this Steam Generator. None of these indications exceeded the structural integrity limits. Three of these indications were OD initiated. These indications are believed to have been caused by ODSCC rather than residual stress from the WEXTEX expansion process.
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
There were no expansions of Top of Tubesheet RPC inspections in #12 Steam Generator. 708 tubes were inspected which represents 20.9% of the Steam Generator .
Page 10 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1' . Owner: Public Service Electric & Gas Co., 80 Park Plaza
* 2.
3.
4.
5.
Newark, N.J.
Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.
Commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
Steam Generator #13 1 s scope was expanded to 100% due to an indication found in tube R14C39. This tube had a 0.448 11 axial indica-tion. The entire length of this indication was contained within the WEXTEX transition, therefore the structural integrity limit of 0.41" was exceeded, prompting the 100% expan-sion of this Steam Generator. This tube also contained two circumferential indications at the top of the tubesheet. Evaluation by Westinghouse determined that this tube re-quired stabilization. One additional tube in this Steam Generator was evaluated for stabi-lization and determined that no stabilization was required.
Steam Generator #14 had no expansions of the Top of Tubesheet RPC inspection. A total of 708 tubes were inspected which represents 20.9% of the Steam Generator.
11.3.3  Bobbin Inspection There were five different types of degradation detected during the bobbin inspection. Four of these mechanisms were previously identified to some degree in Unit 1. They are:
AVB WEAR All four Steam Generators have had some wear at the anti-vibration bars . . Steam Generator
                        #11 had two tubes plugged because of this wear.
COLD LEG THINNING All four Steam Generators have had thinning at peripheral tube cold leg support plate intersections. Steam Generator #14 had one tube plugged because of this mechanism.
Page 11 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1' . owner: Public Service Electric & Gas Co., 80 Park Plaza
* 2.
3.
4.
5.
6.
Newark, N.J.
Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.
Commercial Service Date 7/1/77.
National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
Steam Generator
OD INDICATIONS AT NON-DENTED SUPPORT PLATES These indications are usually distorted on bobbin and require further clarification by RPC testing. Typically, there is a deposit present, which adds to the distortion. This deposit is usually responsible for the corrosion occurring at these intersections.
#13 1 s scope was expanded to 100% due to an indication found in tube R14C39. This tube had a 0.448 11 axial tion. The entire length of this indication was contained within the WEXTEX transition, therefore the structural integrity limit of 0.41" was exceeded, prompting the 100% sion of this Steam Generator.
When these indications confirm, the RPC testing reveals a oval-shaped, pit-like signal. Steam Generators #11 and #12 plugged one tube each for this mechanism.
This tube also contained two circumferential indications at the top of the tubesheet.
Steam Generator #13 had four tubes plugged for this mechanism.
Evaluation by Westinghouse determined that this tube quired stabilization.
OD INDICATIONS AT THE TOP OF TUBESHEET These indications are similar to the support plate indications mentioned above, in that the signals are usually distorted by the presence of a deposit. Again, this deposit is most likely responsible for the corrosion occurring. As mentioned, three of these signals were deemed pluggable during the RPC inspection. In addition, several signals in both Steam Generators #11 and #13 were called INR (Indication not Recordable),
One additional tube in this Steam Generator was evaluated for lization and determined that no stabilization was required.
during the RPC inspection. INR was used since these signals did not fit any of the allowable RPC indications (SAI, MAI, SCI, MCI, SOI and MOI). These INR signals were also bobbin tested. In most cases, these signals were found to be less than a 20%
Steam Generator
through wall dimension, however, two more tubes in Steam Generator #11 were plugged for this mechanism as well as two tubes in Steam Generator #13.
#14 had no expansions of the Top of Tubesheet RPC inspection.
Page 12 of 22
A total of 708 tubes were inspected which represents 20.9% of the Steam Generator.
 
11.3.3 Bobbin Inspection There were five different types of degradation detected during the bobbin inspection.
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
Four of these mechanisms were previously identified to some degree in Unit 1. They are: AVB WEAR All four Steam Generators have had some wear at the anti-vibration bars .. Steam Generator
: 1. owner: Public Service Electric & Gas Co., 80 Park Plaza
#11 had two tubes plugged because of this wear. COLD LEG THINNING All four Steam Generators have had thinning at peripheral tube cold leg support plate intersections.
* 2.
Steam Generator
3.
#14 had one tube plugged because of this mechanism.
4.
Page 11 of 22 
5.
' 1 .
6.
* 2 . 3 . 4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
Newark, N.J.
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.
Examination Summary (cont'd):
Commercial Service Date 7/1/77.
OD INDICATIONS AT NON-DENTED SUPPORT PLATES These indications are usually distorted on bobbin and require further clarification by RPC testing. Typically, there is a deposit present, which adds to the distortion.
National Board Number for Unit N/A.
This deposit is usually responsible for the corrosion occurring at these intersections.
: 7. Examination Dates: 08-17-92 through 02-02-94.
When these indications confirm, the RPC testing reveals a oval-shaped, pit-like signal. Steam Generators  
#11 and #12 plugged one tube each for this mechanism.
Steam Generator  
#13 had four tubes plugged for this mechanism.
OD INDICATIONS AT THE TOP OF TUBESHEET These indications are similar to the support plate indications mentioned above, in that the signals are usually distorted by the presence of a deposit. Again, this deposit is most likely responsible for the corrosion occurring.
As mentioned, three of these signals were deemed pluggable during the RPC inspection.
In addition, several signals in both Steam Generators  
#11 and #13 were called INR (Indication not Recordable), during the RPC inspection.
INR was used since these signals did not fit any of the allowable RPC indications (SAI, MAI, SCI, MCI, SOI and MOI). These INR signals were also bobbin tested. In most cases, these signals were found to be less than a 20% through wall dimension, however, two more tubes in Steam Generator  
#11 were plugged for this mechanism as well as two tubes in Steam Generator  
#13. Page 12 of 22
* . 1. 2. 3. 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
One new degradation mechanism was identified during lRll. This was ID INITIATED TIONS AT DENTED SUPPORT PLATE INTERSECTIONS.
One new degradation mechanism was identified during lRll. This was ID INITIATED INDICA-TIONS AT DENTED SUPPORT PLATE INTERSECTIONS.
These indications can be detected by bobbin when they extend greater than 0.2 11 beyond the edge of the support plate. These indications can be attributed to residual stress from the dent. The shape rather than the size of the dent appears to be more of a factor in causing these indications.
These indications can be detected by bobbin when they extend greater than 0.2 11 beyond the edge of the support plate. These indications can be attributed to residual stress from the dent. The shape rather than the size of the dent appears to be more of a factor in causing these indications. The sizes of the dents associated with these indications are rela-tively small when*compared to the population of dents present in Unit 1 Steam Generators.
The sizes of the dents associated with these indications are tively small when*compared to the population of dents present in Unit 1 Steam Generators.
The first indication of this type was found in Steam Generator #12 tube R33C43 at lH (1st
The first indication of this type was found in Steam Generator  
* support plate hot leg side) . RPC of this indication revealed that it was 1.59 11 long, extending from 0.91 11 above the support plate to 0.68 11 below. This indication prompted 100%
#12 tube R33C43 at lH (1st
bobbin.testing in Steam Generator #12 from 7H to TEH (tube end hot). This expansion re-vealed two more indications tube R8C4 at lH and tube R28C85 at 2H. RPC of tube R8C4 showed an MAI (multiple axial indications).
* support plate hot leg side) . RPC of this indication revealed that it was 1.59 11 long, extending from 0.91 11 above the support plate to 0.68 11 below. This indication prompted 100% bobbin.testing in Steam Generator  
One of the axials was 1. 102 11 in length start-ing* at 0.74 11 above the support plate. The other axial was 1. 050" in length starting at 0.66 11 above the support plate. RPC of tube R28C85 showed and SAI 0.432 11 long starting at 0.68" .above the support plate.
#12 from 7H to TEH (tube end hot). This expansion vealed two more indications tube R8C4 at lH and tube R28C85 at 2H. RPC of tube R8C4 showed an MAI (multiple axial indications).
These indications in Steam Generator #12 prompted 100% bobbin testing in the other three Steam Generators from 7H to TEH. No more indications of this type were found in Steam Generators #11 and #14. However, two indications.were flagged in Steam Generator
One of the axials was 1. 102 11 in length ing* at 0.74 11 above the support plate. The other axial was 1. 050" in length starting at 0.66 11 above the support plate. RPC of tube R28C85 showed and SAI 0.432 11 long starting at 0.68" .above the support plate. These indications in Steam Generator  
                      #13 for RPC testing. RPC of tube R30C42 at 3H revealed an SAI 1. 032 11 long starting at O. 26 11 above the support plate and ending at 1.292 11 below the support plate.
#12 prompted 100% bobbin testing in the other three Steam Generators from 7H to TEH. No more indications of this type were found in Steam Generators  
Page 13 of 22
#11 and #14. However, two indications.were flagged in Steam Generator  
 
#13 for RPC testing. RPC of tube R30C42 at 3H revealed an SAI 1. 032 11 long starting at O. 26 11 above the support plate and ending at 1.292 11 below the support plate. Page 13 of 22
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY TH~ PROVISIONS OF THE ASME CODE RULES 1' . owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
' 1 .
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
* 2. 3. 4. 5. 6. 7. 11.
: 3. Plant Unit 1   *
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1
: 4. owner's Certificate of Authorization (if required) N/A.
* owner's Certificate of Authorization (if required)
: 5. Commercial Service Date 7/1/77.
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
: 6. National Board Number for Unit N/A.
Examination Summary (cont'd):
: 7. Examination Dates: 08-17-92 through 02-02-94.
11.4 RPC of tube R3C59 at lH revealed an MAI. One of the axials was 1.742" long starting at 0.87" above the support plate. The other axial was o. 591'.' long, starting at o. 74" above the support plate. Both of these indications were determined to be OD indications rather than ID. RPC OF DENTED SUPPORT PLATE INTERSECTIONS Twelve hours were allocated for sample testing of dented support plate tions in each Steam Generator.
: 11. Examination Summary (cont'd):
The 300 largest dents in each Steam Generator were selected for testing. The aim of this testing is to detect the presence of ferential indications.
RPC of tube R3C59 at lH revealed an MAI. One of the axials was 1.742" long starting at 0.87" above the support plate. The other axial was o. 591'.' long, starting at o. 74" above the support plate. Both of these indications were determined to be OD indications rather than ID.
Circumferential oriented indications can not be seen by bobbin probes. Due to time constraints and restrictions encountered within the tubes, none of the Steam Generators completed the 300 tube program. The number of tions inspected, ranged from 122 to 170. No indications were detected in this tion. Current Status of the Steam Generators At this time the total number of tubes plugged in the Salem Unit 1 Steam Generators are as follows: Generator  
RPC OF DENTED SUPPORT PLATE INTERSECTIONS Twelve hours were allocated for sample testing of dented support plate intersec-tions in each Steam Generator. The 300 largest dents in each Steam Generator were selected for testing. The aim of this testing is to detect the presence of circum-ferential indications. Circumferential oriented indications can not be seen by bobbin probes. Due to time constraints and restrictions encountered within the tubes, none of the Steam Generators completed the 300 tube program. The number of intersec-tions inspected, ranged from 122 to 170. No indications were detected in this inspec-tion.
# 11 12 13 14 Tubes previously plugged 104 121 112 143 New tubes plugged this outage 12 4 10 2 Tubes Plugged 116 125 122 145 Page 14 of 22
11.4  Current Status of the Steam Generators At this time the total number of tubes plugged in the Salem Unit 1 Steam Generators are as follows:
*
Generator #           11       12     13       14 Tubes previously plugged             104       121     112     143 New tubes plugged this outage           12         4     10       2 Tubes Plugged       116       125     122     145 Page 14 of 22
* i. 2. 3 . 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)
 
N/A. commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
: i. owner: Public Service Electric & Gas Co., 80 Park Plaza
* Newark, N.J. 07101
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J.     08038
: 3. Plant Unit 1
: 4. Owner's Certificate of Authorization (if required) N/A.
: 5. commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
NOTE: The first five and the last five tubes of Row 1 in each of the Steam Generators were ically plugged due to a vibration in the tube lane blocking device. The remaining Row 1 tubes were preventively plugged due to a wear problem on the tubes caused by a vibration in the tube lane blocking device. The remaining Row 1 tubes were preventively plugged due to the onset of stress corrosion cracking in the U-bend region as evidenced in two of the four Steam Generators.
NOTE:   The first five and the last five tubes of Row 1 in each of the Steam Generators were mechan-ically plugged due to a vibration in the tube lane blocking device. The remaining Row 1 tubes were preventively plugged due to a wear problem on the tubes caused by a vibration in the tube lane blocking device. The remaining Row 1 tubes were preventively plugged due to the onset of stress corrosion cracking in the U-bend region as evidenced in two of the four Steam Generators.
11.5 Technical Specification 4.6.1.2d, Containment Type "B" (Penetrations) and Type "C" (Valves) Leak Rate Testing . 11.5.1 summary The PSE&G Research Corp. under the field supervision of the Salem ISI Group, conducted local leak rate tests on sixty three (63) Type "B" Electrical Penetrations, seven (7) Type "B" Mechanical Penetrations and fifty five (55) Type "C" Mechanical Penetrations (113 valves). 11. 5. 2 Results A. Several Type "C" valves exceeded the recommended leak rate acceptable criteria.
11.5 Technical Specification 4.6.1.2d, Containment Type "B" (Penetrations) and Type "C" (Valves) Leak Rate Testing .
11.5.1   summary The PSE&G Research Corp. under the field supervision of the Salem ISI Group, conducted local leak rate tests on sixty three (63) Type "B" Electrical Penetrations, seven (7) Type "B" Mechanical Penetrations and fifty five (55)
Type "C" Mechanical Penetrations (113 valves).
: 11. 5. 2 Results A. Several Type "C" valves exceeded the recommended leak rate acceptable criteria.
These valves were worked to an acceptable condition and retested satisfactorily.
These valves were worked to an acceptable condition and retested satisfactorily.
B. A total As-Found leakage (min path) of . 15,338.5 SCCM was measured through all Type "B" and "C" containment penetrations.
B. A total As-Found leakage (min path) of
After corrective maintenance, a total Left (max path) of 26,372.0 SCCM was ured through all Type "B" and "C" tions. Page 15 of 22
                          . 15,338.5 SCCM was measured through all Type "B" and "C" containment penetrations.
' 1 .
After corrective maintenance, a total As-Left (max path) of 26,372.0 SCCM was meas-ured through all Type "B" and "C" penetra-tions.
* 2. 3. 4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)
Page 15 of 22
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
 
Examination Summary (cont'd):
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1' . Owner: Public Service Electric & Gas Co., 80 Park Plaza
11.6 Technical Specification 4.6.1.3b Elevation 100 1 and 130' Airlock Leak Rate Tests 11.6.1 Summary PSE&G Research Corporation under the field supervision of the Salem ISI Group conducted leak rate tests on the 100' and 130' ment personnel airlocks.
* 2.
11.6.2 Results The combined As-Found leakage for these locks was 4,925.0 SCCM. After maintenance, the combined As-Left leakage for the airlocks was 5,860.0 SCCM. Both of these measured combined leakage rates satisfies the Technical Specif cation acceptance criteria of 0.05 La (10,812 SCCM) . 11.7 Technical Specification 4.7.9. (a) "Visual Inspection of Hydraulic and Mechanical Snubbers" 11. 7. 1 Summary The Salem ISI Group conducted visual tions on twenty four (24) hydraulic and one hundred and eleven {111) mechanical snubbers.
3.
11.7.2 Results A. There were no discrepancies noted which would affect snubber operability.
4.
There were some minor items noted including missing washers, loose spherical bearings and binding around the bearings and some light corrosion.
5.
These conditions were all noted and corrected.
6.
B. All snubbers which were removed and stalled received a satisfactory "As-Left" visual examination.
Newark, N.J.
Page 16 of 22
Plant:
* * ' 1 . 2 . 3 . 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED' BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
Plant Unit 1 07101 Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Owner's Certificate of Authorization (if required) N/A.
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
Commercial Service Date 7/1/77.
National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
11.6   Technical Specification 4.6.1.3b Elevation 100 1 and 130' Airlock Leak Rate Tests 11.6.1   Summary PSE&G Research Corporation under the field supervision of the Salem ISI Group conducted leak rate tests on the 100' and 130' contain-ment personnel airlocks.
11.6.2   Results The combined As-Found leakage for these air-locks was 4,925.0 SCCM. After maintenance, the combined As-Left leakage for the airlocks was 5,860.0 SCCM. Both of these measured combined leakage rates satisfies the Technical Specif i-cation acceptance criteria of ~ 0.05 La (10,812 SCCM) .
11.7   Technical Specification 4.7.9. (a) "Visual Inspection of Hydraulic and Mechanical Snubbers"
: 11. 7. 1 Summary The Salem ISI Group conducted visual examina-tions on twenty four (24) hydraulic and one hundred and eleven {111) mechanical snubbers.
11.7.2   Results A. There were no discrepancies noted which would affect snubber operability. There were some minor items noted including missing washers, loose spherical bearings and binding around the bearings and some light corrosion. These conditions were all noted and corrected.
B. All snubbers which were removed and rein-stalled received a satisfactory "As-Left" visual examination.
Page 16 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED' BY THE PROVISIONS OF THE ASME CODE RULES
: 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza
* 2.
3.
4.
5.
6.
Newark, N.J.
Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J.     08038 owner's Certificate of Authorization (if required) N/A.
Commercial Service Date 7/1/77.
National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination summary (cont'd):
: 11. Examination summary (cont'd):
11.8 Technical Specification 4.7.9 (c) "Functional Testing of Selected Hydraulic and Mechanical Snubbers" 11.8.1 summary -Hydraulic Snubbers 11.8.2 A. Per Technical Specifications, 10% of the installed hydraulic snubbers as well as all previous outage functional test failures are required to be tested. The 10% sample included one 200 KIP Main Steam snubber and two 1000 KIP Steam Generator snubbers.
11.8 Technical Specification 4.7.9 (c) "Functional Testing of Selected Hydraulic and Mechanical Snubbers" 11.8.1   summary - Hydraulic Snubbers A. Per Technical Specifications, 10% of the installed hydraulic snubbers as well as all previous outage functional test failures are required to be tested. The 10% sample included one 200 KIP Main Steam snubber and two 1000 KIP Steam Generator snubbers.
There were no previous outage test ures. B. The 10% sample of hydraulic snubber (small size) included one (1) Lisega 3018 . There were no noted discrepancies in the Technical Specification sample. Summary -Mechanical snubbers Per Technical Specifications, 10% of the total installed mechanical snubbers as well as ous outage functional test failures were tested utilizing the WYLE Model 150 Snubber Testing machine. The 10% sample is broken down by *snubber category size (small, medium and large) with 10% from each size selected each outage. All selected snubbers are detailed below: A. The 10% sample of the medium size snubbers included two (2) PSA-l's and nine (9) PSA-3 's. B. The 10% sample of the large size snubbers included one (1) PSA-35. C. Due to previous outage failures, 100% of the small size snubbers (PSA-1/4 1 s, PSA-1/2'') are tested each outage. This ed in tests being performed on.one Model 1/4 and three Model 1/2. Page 17 of 22
There were no previous outage test fail-ures.
. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's
B. The 10% sample of hydraulic snubber (small size) included one (1) Lisega 3018 .
_Bridge, N.J. 08038 3. Plant Unit 1 4. owner's Certificate of Authorization (if required)
There were no noted discrepancies in the Technical Specification sample.
N/A. 5. Commercial Service Date 7/1/77. 6. National Board Number for Unit N/A. 7. Examination Dates: 08-17-92 through 02-02-94.
11.8.2  Summary - Mechanical snubbers Per Technical Specifications, 10% of the total installed mechanical snubbers as well as previ-ous outage functional test failures were tested utilizing the WYLE Model 150 Snubber Testing machine. The 10% sample is broken down by
                      *snubber category size (small, medium and large) with 10% from each size selected each outage.
All selected snubbers are detailed below:
A. The 10% sample of the medium size snubbers included two (2) PSA-l's and nine (9) PSA-3 's.
B. The 10% sample of the large size snubbers included one (1) PSA-35.
C. Due to previous outage failures, 100% of the small size snubbers (PSA-1/4 1 s, PSA-1/2'') are tested each outage. This result-ed in tests being performed on.one Model 1/4 and three Model 1/2.
Page 17 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
: 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
: 2. Plant:   Salem Generating Station P.O. Box 236, Hancock's _Bridge, N.J. 08038
: 3. Plant Unit 1
: 4. owner's Certificate of Authorization (if required) N/A.
: 5. Commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
11.8.3  Results - Mechanical Snubbers A. One medium size Technical Specification sample snubber failed the functional test resulting in a sample expansion of eleven (11) additional tests.
B. All the small size snubbers were tested satisfactory.
11.9  Technical Specification 4.4.11.1 Reactor Coolant Pump Flywheel-Examination 11.9.1  Summary Southwest Research Institute {SwRI) under the direction of the ISI Group performed an in-place ultrasonic examination (UT) on Reactor Coolant Pump {RCP) Flywheels SN 3S-76P917 and SN 2S-76P917. Flywheel examinations are tracked by the RCP Motor serial number and original pump location.
There were no unacceptable indications identi-fied.
11.10 NRC Bulletin 82-02 "Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of Power Plants".
11.10.1 Summary Visual (VT) and Magnetic Particle {MT) exams were performed on the #11 through #14 Steam Generator (inlet & outlet) and Pressurizer Primary Manway Bolts. Also #11 through #14 Reactor Coolant Pumps main flange bolting was visually inspected.
Page 18 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES l
: 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza
* 2.
3.
4.
5.
6.
Newark, N.J.
Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.
Commercial Service Date 7/1/77.
National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
11.8.3 Results -Mechanical Snubbers A. One medium size Technical Specification sample snubber failed the functional test resulting in a sample expansion of eleven (11) additional tests. B. All the small size snubbers were tested satisfactory.
There were several S/G (inlet & outlet) Pri-mary Manway washers replaced, due to deep galling. These washers were replaced in kind.
11.9 Technical Specification 4.4.11.1 Reactor Coolant Pump Flywheel-Examination 11.9.1 Summary Southwest Research Institute
A VT revealed wastage on the shank of one bolt on #14 S/G Outlet manway. This bolt was replaced. There were several PZR Primary Manway bolts replaced, due to non service induced anomalies found during the VT.
{SwRI) under the direction of the ISI Group performed an place ultrasonic examination (UT) on Reactor Coolant Pump {RCP) Flywheels SN 3S-76P917 and SN 2S-76P917.
NOTE:   100% of all the S/G and PZR manway bolts were examined during this refuel-ing outage.
Flywheel examinations are tracked by the RCP Motor serial number and original pump location.
There were no other unacceptable indications identified .
There were no unacceptable indications fied. 11.10 NRC Bulletin 82-02 "Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of Power Plants". 11.10.1 Summary Visual (VT) and Magnetic Particle {MT) exams were performed on the #11 through #14 Steam Generator (inlet & outlet) and Pressurizer Primary Manway Bolts. Also #11 through #14 Reactor Coolant Pumps main flange bolting was visually inspected.
* 11.11 NRC Bulletin 88-08 "Thermal Stresses in Piping Con-neated to Reactor Coolant System".
Page 18 of 22 l 1 .
11.11.1 Summary Southwest Research Institute {SwRI), and MQS under the direction of the Salem ISI Group, performed augmented ultrasonic and dye pene-trant examinations on nine (9) 1. 5 11 Safety Injections welds, two (2) 2 11 Chemical Volume Control welds and two (2) 3 11 Chemical Volume Control welds.
* 2. 3. 4. 5. 6. 7. 11.
NOTE:   Seven (7) components had the 88-08 exams waived, due to the replacement of the 11 through 14 SJ17 valves (DCP lE0-2309) . The associated replacement welds were not ultrasonically examined as required by NRC Bulletin 88-08. NRC Bulletin 88-08 is concerned with a service induced condition, which would not exist with these new welds.
* FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
There were no unacceptable indications identi-fied.
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
Page 19 of 22
Examination Summary (cont'd):
 
There were several S/G (inlet & outlet) mary Manway washers replaced, due to deep galling. These washers were replaced in kind. A VT revealed wastage on the shank of one bolt on #14 S/G Outlet manway. This bolt was replaced.
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L
There were several PZR Primary Manway bolts replaced, due to non service induced anomalies found during the VT. NOTE: 100% of all the S/G and PZR manway bolts were examined during this ing outage. There were no other unacceptable indications identified . 11.11 NRC Bulletin 88-08 "Thermal Stresses in Piping neated to Reactor Coolant System". 11.11.1 Summary Southwest Research Institute
: 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
{SwRI), and MQS under the direction of the Salem ISI Group, performed augmented ultrasonic and dye trant examinations on nine (9) 1. 5 11 Safety Injections welds, two (2) 2 11 Chemical Volume Control welds and two (2) 3 11 Chemical Volume Control welds. NOTE: Seven (7) components had the 88-08 exams waived, due to the replacement of the 11 through 14 SJ17 valves (DCP lE0-2309) . The associated replacement welds were not ultrasonically examined as required by NRC Bulletin 88-08. NRC Bulletin 88-08 is concerned with a service induced condition, which would not exist with these new welds. There were no unacceptable indications fied. Page 19 of 22 L FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 3. Plant Unit 1 4. owner's Certificate of Authorization (if required)
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
N/A. 5. Commercial Service Date 7/1/77. 6. National Board Number for Unit N/A. 7. Examination Dates: 08-17-92 through 02-02-94.
: 3. Plant Unit 1
: 4. owner's Certificate of Authorization (if required) N/A.
: 5. Commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
11.12 NRC Bulletin 88-11 "Pressurizer Surge Line Thermal stratifi.cation".
11.12 NRC Bulletin 88-11 "Pressurizer Surge Line Thermal stratifi.cation".
11.12.1 Summary The Salem ISI group performed visual tions on all existing surge line pipe supports / HEBA restraints and their associated tion. A total of ten (10) supports were examined.
11.12.1 Summary The Salem ISI group performed visual examina-tions on all existing surge line pipe supports
There were no unacceptable indications fied. 11.13 NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants". 11.13.1 Summary Measurements were taken at one hundred and sixty four (164) locations to identify possible pipe erosion/corrosion.
                    / HEBA restraints and their associated insula-tion. A total of ten (10) supports were examined.
Of the 164 locations, 147 were from the original scope and 17 were the result of significant wall thinning found in 15*components.
There were no unacceptable indications identi-fied.
Fifteen (15) components were cut out and replaced and one (1) nent received external weld "build-up".
11.13 NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants".
Other than the aforementioned areas, no other tions were observed.
11.13.1 Summary Measurements were taken at one hundred and sixty four (164) locations to identify possible pipe erosion/corrosion. Of the 164 locations, 147 were from the original scope and 17 were the result of significant wall thinning found in 15*components. Fifteen (15) components were cut out and replaced and one (1) compo-nent received external weld "build-up". Other than the aforementioned areas, no other condi-tions were observed.
11.14 Field Directive, S-C-R700-MFD-288, "Leak Rate Test Program for the Steam Generator Blowdown Isolation Valve (GB4) 11.14.1 PSE&G Research and Testing Lab under the field supervision of the Salem ISI Group, conducted leak rate tests on all four Steam Generator Blowdown Valves (GB-4's) in accordance with procedure SC.SS-IS.GB-0004(Q).
11.14 Field Directive, S-C-R700-MFD-288, "Leak Rate Test Program for the Steam Generator Blowdown Isolation Valve (GB4) 11.14.1 PSE&G Research and Testing Lab under the field supervision of the Salem ISI Group, conducted leak rate tests on all four Steam Generator Blowdown Valves (GB-4's) in accordance with procedure SC.SS-IS.GB-0004(Q).
Page 20 of 22
Page 20 of 22
' 1.
 
* 2. 3
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
* 4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)
: 1. owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 3
Examination Summary (cont'd):
* Plant Unit 1
11.14.2 Results All four valves had an acceptable leak rates below the test acceptance criteria of 30,000 SCCM. No discrepancies were noted. 11.15 Summary NuReg 0578 -TMI Lessons Learned -A. Twenty-seven (27) System Pressure Tests were pleted per NUREG 0578 commitments.
: 4. owner's Certificate of Authorization (if required) N/A.
Completed System Pressure Tests on the following systems: Chemical Volume and Control Containment Spray Liquid Radwaste Residual Heat Removal Safety Injection Sampling Waste Gas B. The PSE&G Research Corp., under the direction of the Salem ISI Group conducted the Waste Gas System Leak Test in accordance with procedure SC.SS-IS.WG-0003(R).
: 5. Commercial Service Date 7/1/77.
11.15 .1 Results A. The leakage on systems defined by NUREG 0578 were identified as minor mechanical leakage and would not have any adverse impact on the Auxiliary building access during an accident.
: 6. National Board Number for Unit N/A.
Work requests were initiated for repairs. B. The Waste Gas System Leak Rate Test showed no adverse findings relative to this Bulletin.
: 7. Examination Dates: 08-17-92 through 02-02-94.
Page 21 of 22 FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES .. 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 3. Plant Unit 1 4. Owner's Certificate of Authorization (if required)
: 11. Examination Summary (cont'd):
N/A. 5. Commercial Service Date 7/1/77. 6. National Board Number for Unit N/A. 7. Examination Dates: 08-17-92 through 02-02-94.
11.14.2 Results All four valves had an acceptable leak rates below the test acceptance criteria of ~ 30,000 SCCM. No discrepancies were noted.
11.15 Summary NuReg 0578 - TMI Lessons Learned -
A. Twenty-seven (27) System Pressure Tests were com-pleted per NUREG 0578 commitments.
Completed System Pressure Tests on the following systems:
Chemical Volume and Control   Safety Injection Containment Spray             Sampling Liquid Radwaste               Waste Gas Residual Heat Removal B. The PSE&G Research Corp., under the direction of the Salem ISI Group conducted the Waste Gas System Leak Test in accordance with procedure SC.SS-IS.WG-0003(R).
11.15 .1 Results A. The leakage on systems defined by NUREG 0578 were identified as minor mechanical leakage and would not have any adverse impact on the Auxiliary building access during an accident. Work requests were initiated for repairs.
B. The Waste Gas System Leak Rate Test showed no adverse findings relative to this Bulletin.
Page 21 of 22
 
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
: 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
: 3. Plant Unit 1
: 4. Owner's Certificate of Authorization (if required) N/A.
: 5. Commercial Service Date 7/1/77.
: 6. National Board Number for Unit N/A.
: 7. Examination Dates: 08-17-92 through 02-02-94.
: 11. Examination Summary (cont'd):
: 11. Examination Summary (cont'd):
We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Section XI. Date 30 , 19 tl signed PSE&G owner Certificate of Authorization No. (if applicable)
We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Section XI.
N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the state or Province of New Jersey and employed by Arkwright Mutual Insurance Company, Norwood, Massachusetts, have inspected the components described.in this Owner's Data Report during the period 08-17-92 to 02-02-94 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owner's Data Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his er makes any warranty, or implied, concerning the examinations and corrective measures described in this Owner's Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date   ~    30 , 19 tl signed PSE&G owner   By~. JI-~
Date J-l/ --------,
Certificate of Authorization No.   (if applicable) N/A Expiration Date   N/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the state or Province of New Jersey and employed by Arkwright Mutual Insurance Company, Norwood, Massachusetts, have inspected the components described.in this Owner's Data Report during the period 08-17-92 to 02-02-94 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owner's Data Report in accordance with the requirements of the ASME Code, Section XI.
Commissions Page 22 of 22 National Board, State, Province and No.
By signing this certificate neither the Inspector nor his employ-er makes any warranty, e~pressed or implied, concerning the examinations and corrective measures described in this Owner's Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
** PUBLIC SERVICE ELECTRIC & GAS CO. SALEH NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.O) SECTION XI COMPLETE COXPORERTS SECORD INTERVAL, SECORD PERIOD, SECORD OUTAGE (93RF) Karch 4, 1994 REVISION 0 Date Date Date i3ld.1'1.
Date - -J-l/
I -of<ifaL/'
          ------,     19~v Commissions National Board, State, Province and No.
DATE: 03/04/94 ' REVISIO'H:
Page 22 of 22
0 EACTOR PRESSURE VESSEL  
 
PUBLIC SERVICE ELECTRIC & GAS CO.
SALEH NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.O)
SECTION XI COMPLETE COXPORERTS SECORD INTERVAL, SECORD PERIOD, SECORD OUTAGE (93RF)
Karch 4, 1994 REVISION 0 Date i3ld.1'1.
I Date Date
                                            -of<ifaL/'
 
DATE: 03/04/94                                   SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:
  ' REVISIO'H:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND* INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS EACTOR PRESSURE VESSEL N      0 ASME                                  0 G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND* INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: CIRCUMFERENTIAL WELDS CREF. DWG. NO. A*1) 002001 1*RPV-7042 VESSEL TO FLANGE B-A B1.30 UT1.5 UT5.7 UT12.5 THREADS IN FLANGE (REF. DWG. NO. A*2) 003700 1*RPV*LIG 1 THRU 54 B-G-1 B6.4D UTO REACTOR VESSEL SUPPORT CREF. DWG. NO. A-1> 003751 1-RPV-11CLSUPPORT SLIDING SUPPORT 003752 1-RPV-12HLSUPPORT SLIDING SUPPORT INTERIOR (REF. 1?WG-. NO. *A-1) 004310 RPV INTERNAL SURFACE F-A F2.10 F-A F2.10 VT-3 VT-3 B-N-1 VT-3 B13.10 CONTROL ROD DRIVE HOUSINGS (REF. DWG. NO. A-2B> VS1SSISRCE0094Q X * -PERFORM MANUAL UT FROM THE SURFACE OF X THE VESSEL FLANGE ON VESSEL TO X FLANGE WELD (#1 THRU 54, STUD HOLES). W.0.#931121035 TO PERFORM NOE. **53-SAM/109-SAM**
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                     ITEM NO METHOD       PROCEDURE         C M R     **CALIBRATION BLOCK**
VS1SSISRCE0009Q X --EXAMINE LIGAMENTS  
CIRCUMFERENTIAL WELDS CREF. DWG. NO. A*1) 002001   1*RPV-7042                       B-A       UT1.5     VS1SSISRCE0094Q   X * -     PERFORM MANUAL UT FROM THE SURFACE OF VESSEL TO FLANGE                B1.30    UT5.7                        X         THE VESSEL FLANGE ON 100~ VESSEL TO UT12.5                      X         FLANGE WELD (#1 THRU 54, STUD HOLES).
#18 THRU #54. S1SSISZZ0020Q S1SSISZZ0020Q VS1SSISZZ002QQ W.0.#931121035 TO PERFORM NOE. **7-1.25-8-CS-60-SAM** X --THIS EXAM IS TO BE COORDINATED WITH THE SAFE END WELD EXAMINATIONS ON THE #11 COLD LEG. W.O. # 931121035, TO PERFORM NOE. X --THIS EXAM IS TO BE COORDINATED WITH THE SAFE END WELD EXAMINATIONS OF THE #12 HOT LEG. W.0.# 931121035, TO PERFORM NOE. X --SWRI TO PERFORM VT-3 INSPECTION.
W.0.#931121035 TO PERFORM NOE.
W.0.#931121035 TO PERFORM NOE *. FOR SMD TO SUPPORT THE RPV VT, SEE W.0.# 930601189.
                                                                                              **53-SAM/109-SAM**
006050 1-CRDH B-0 PT (#72) VS1SSISZZ0003Q X --EXAMINED #72 & 73 CRDH, NEAR #50 STUD ** CRD HOUSING BODY-TO-ADAPTER WELDS 814.10 PT (#73) X HOLE. W.O. #931121035 TO PERFORM NOE.
THREADS IN FLANGE (REF. DWG. NO. A*2) 003700 1*RPV*LIG 1 THRU 54                B-G-1    UTO        VS1SSISRCE0009Q   X -   - EXAMINE LIGAMENTS #18 THRU #54.
, DATE: ,03/04/94 REVISION:
B6.4D                                            W.0.#931121035 TO PERFORM NOE.
0 .PRESSURIZER
                                                                                              **7-1.25-8-CS-60-SAM**
*
REACTOR VESSEL SUPPORT CREF. DWG. NO. A-1>
003751  1-RPV-11CLSUPPORT                F-A      VT-3      S1SSISZZ0020Q    X -   - THIS EXAM IS TO BE COORDINATED WITH THE SLIDING SUPPORT                  F2.10                                            SAFE END WELD EXAMINATIONS ON THE #11 COLD LEG. W.O. # 931121035, TO PERFORM NOE.
003752 1-RPV-12HLSUPPORT                  F-A      VT-3      S1SSISZZ0020Q    X -   -   THIS EXAM IS TO BE COORDINATED WITH THE SLIDING SUPPORT                  F2.10                                            SAFE END WELD EXAMINATIONS OF THE #12 HOT LEG. W.0.# 931121035, TO PERFORM NOE.
INTERIOR (REF. 1?WG-. NO. *A-1) 004310 RPV INTERNAL SURFACE              B-N-1    VT-3        VS1SSISZZ002QQ  X -     - SWRI TO PERFORM VT-3 INSPECTION.
B13.10                                            W.0.#931121035 TO PERFORM NOE *. FOR SMD TO SUPPORT THE RPV VT, SEE W.0.#
930601189.
CONTROL ROD DRIVE HOUSINGS (REF. DWG. NO. A-2B>
006050 1-CRDH                             B-0       PT (#72)   VS1SSISZZ0003Q   X -     - EXAMINED #72 & 73 CRDH, NEAR #50 STUD CRD HOUSING BODY-TO-ADAPTER     814.10   PT (#73)                     X         HOLE. W.O. #931121035 TO PERFORM NOE.
WELDS
 
    , DATE: ,03/04/94                             SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    2 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS
.PRESSURIZER N      0 ASHE                                  0 G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION BOLTING CREF. DWG. NO. A-3) 007820 PZR BOLTING-HANWAY  
EXAMINATION AREA             CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION               ITEM *No METHOD      PROCEDURE        C M R    **CALIBRATION BLOCK**
** SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASHE SEC. XI CATGY EXAM ITEM *No METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 2 B-G-2 B7.21 VT-1 (ISi) SCSSISZZ0010Q VT-1 (PSI) MT VSHSSSPZZ0202Q --X A FLORESCENT MT EXAM TO BE PERFORMED  
BOLTING CREF. DWG. NO. A-3) 007820 PZR BOLTING-HANWAY           B-G-2     VT-1 (ISi) SCSSISZZ0010Q     - - X   A FLORESCENT MT EXAM TO BE PERFORMED ?ER B7.21    VT-1 (PSI)                  X - -   NRC BULLETIN 82-02. MQS TO PERFORM THE MT        VSHSSSPZZ0202Q    X - -   MT AND PSE&G TO PERFORM THE VT. W.O.
?ER X --NRC BULLETIN 82-02. MQS TO PERFORM THE X --MT AND PSE&G TO PERFORM THE VT. W.O. #920401058  
                                                                                          #920401058 & 931121035 TO PERFORM NOE.
& 931121035 TO PERFORM NOE. SEVERAL BOLTS WERE REPLACED PER CJP #S-93-254  
SEVERAL BOLTS WERE REPLACED PER CJP
& w.o. #930401183
                                                                                          #S-93-254 & w.o. #930401183
* DATE: 03/04/94
* DATE: 03/04/94                             SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    3
* REVISION:
* REVISION:     0                    OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)
0 TEAM GENERATOR 11  
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS TEAM GENERATOR 11 N      0 ASME                                  O G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION BOLTING CREF. DWG. NO. A*4) 008790 11*STG*OMB BOLTS*OUTLET MANWAY 008795 11*STG-IMB BOLTS-INLET MANWAY *** SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 3 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-G-2 B7.30 B-G-2 B7.30 VT-1 MT VT-1 MT PROCEDURE SCSSISZZ0010Q VSHSSSPZZ0202Q SCSSISZZ0010Q VSHSSSPZZ0202Q N 0 O G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** x x x x A FLORESCENT MT EXAM TO BE PERFORMED PER 82-02. MQS TO PERFORM MT AND PSE&G TO PERFORM THE VT. W.O. # 931105020 AND 931121035 TO PERFORM ND. A FLORESCENT MT EXAM TO.BE PERFORMED PER 82-02.' MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931105020 AND 931121035 TO PERFORM NOE *
EXAMINATION AREA             CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION               ITEM NO METHOD      PROCEDURE        C M R    **CALIBRATION BLOCK**
, DATE: ,03/04/94 REVISION:
BOLTING CREF. DWG. NO. A*4) 008790 11*STG*OMB                   B-G-2   VT-1       SCSSISZZ0010Q     x         A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS*OUTLET MANWAY          B7.30    MT        VSHSSSPZZ0202Q    x        82-02. MQS TO PERFORM T~E MT AND PSE&G TO PERFORM THE VT. W.O. # 931105020 AND 931121035 TO PERFORM ND.
0 STEAM GENERATOR 12  
008795  11*STG-IMB                  B-G-2    VT-1      SCSSISZZ0010Q    x        A FLORESCENT MT EXAM TO.BE PERFORMED PER BOLTS-INLET MANWAY          B7.30    MT        VSHSSSPZZ0202Q    x        82-02.' MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931105020 AND 931121035 TO PERFORM NOE *
 
  , DATE: ,03/04/94                             SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    4 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS STEAM GENERATOR 12 N      0 ASME                                  0  G T SEC. XI                                R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION BOLTING (REF. DWG. NO. A-5) 009650 12-STG-OMB BOLTS-OUTLET MANWAY 009675 12-STG-IMB BOLTS-INLET MANWAY ** SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 4 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-G-2 B7.30 B-G-2 B7.30 VT-1 MT VT-1 MT PROCEDURE SCSSISZZ0010Q VSHSSSPZZ0202Q SCSSISZZ0010Q VSHSSSPZZ0202Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --A FLORESCENT MT EXAM TO BE PERFORMED PER X 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931121035  
EXAMINATION AREA             CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD      PROCEDURE        C M R    **CALIBRATION BLOCK**
& 931105031 TO PERFORM NOE. X A FLORESCENT MT EXAM TO BE PERFORMED PER X --82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931121035  
BOLTING (REF. DWG. NO. A-5) 009650 12-STG-OMB                   B-G-2     VT-1       SCSSISZZ0010Q     X -   - A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-OUTLET MANWAY          B7.30    MT        VSHSSSPZZ0202Q    X         82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931121035 &
& 931105031 TO PERFORM NOE
931105031 TO PERFORM NOE.
* DATE: 03/04/94 : REVISION:
009675  12-STG-IMB                  B-G-2    VT-1        SCSSISZZ0010Q    X         A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-INLET MANWAY          B7.30    MT          VSHSSSPZZ0202Q  X -   - 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931121035 &
0 TEAM GENERATOR 13  
931105031 TO PERFORM NOE
* DATE: 03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    5
: REVISION:     0                      OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS TEAM GENERATOR 13 N      0 ASME                                  0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION BOLTING (REF. DWG. NO. A-6) 010550 13-STG-OMB BOLTS-OUTLET MANWAY 010575 13-STG-IMB BOLTS-INLET MANWAY SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 5 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-G-2 B7.30 B-G-2 B7.30 VT-1 MT VT-1 MT PROCEDURE SCSSISZZ0010Q VSHSSSPZZ0202Q SCSSISZZ0010Q VSHSSSPZZ0202Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** x x x x A FLORESCENT MT EXAM TO BE PERFORMED PER 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931105032 AND 931121035 TO PERFORM NOE. A FLORESCENT MT EXAM TO BE PERFORMED PER 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. # 931105032 AND 931121035 TO PERFORM THE NOE.
EXAMINATION AREA             CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD      PROCEDURE        C M R    **CALIBRATION BLOCK**
, DATE: ,03/04/94 REVISION:
BOLTING (REF. DWG. NO. A-6) 010550 13-STG-OMB                   B-G-2     VT-1       SCSSISZZ0010Q     x         A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-OUTLET MANWAY          B7.30    MT        VSHSSSPZZ0202Q    x        82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931105032 AND 931121035 TO PERFORM NOE.
0 .STEAM GENERATOR 14  
010575  13-STG-IMB                  B-G-2    VT-1      SCSSISZZ0010Q    x        A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-INLET MANWAY          B7.30    MT        VSHSSSPZZ0202Q    x        82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. # 931105032 AND 931121035 TO PERFORM THE NOE.
 
    , DATE: ,03/04/94                             SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    6 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI CCJIPLETE COMPONENTS
.STEAM GENERATOR 14 N      O ASME                                    0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION BOLTING (REF. DWG. NO. A-7) 011450 14-STG-OMB BOLTS-OUTLET MANWAY 011475 14-STG-IMB BOLTS-INLET MANWAY "'C.* ** ** SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 6 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI CCJIPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-G-2 B7.30 B-G-2 B7.30 VT-1 MT VT-1 MT PROCEDURE SCSSISZZ0010Q VSHSSSPZZ0202Q SCSSISZZ0010Q VSHSSSPZZ0202Q N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** x X A FLORESCENT MT EXAM TO BE PERFORMED PER 82-02. MQS TO PERFORM MT & PSE&G TO PERFORM VT. W.O. #931121035  
EXAMINATION AREA             CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD      PROCEDURE          C M R    **CALIBRATION BLOCK**
& 931105033 TO PERFORM NOE. #14CL BOLT #16 WAS FOUND TO HAVE WASTAGE ON BOLT SHANK. CJP # S-93-262 REPLACED BOLT W/ SATISFACTORY PSI VT. X A FLORESCENT MT EXAM TO BE PERFORMED PER X --82-02. MQS TO PERFORM THE.MT & PSE&G TO PERFORM VT. w;o. #931105033  
BOLTING (REF. DWG. NO. A-7) 011450 14-STG-OMB                   B-G-2     VT-1       SCSSISZZ0010Q             X A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-OUTLET MANWAY          B7.30    MT        VSHSSSPZZ0202Q    x        82-02. MQS TO PERFORM MT & PSE&G TO PERFORM VT. W.O. #931121035 & 931105033 TO PERFORM NOE. #14CL BOLT #16 WAS FOUND TO HAVE WASTAGE ON BOLT SHANK.
& 931121035 TO PERFORM NOE.
CJP # S-93-262 REPLACED BOLT W/
DATE: 03/04/94 SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 7 ' REVISION:
SATISFACTORY PSI VT.
0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS CHEMICAL AND VOLUME CONTROL SYSTEM N 0 ASME 0 G T SEC. XI R E H  
011475  14-STG-IMB                  B-G-2    VT-1        SCSSISZZ0010Q    X       A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-INLET MANWAY          B7.30    MT          VSHSSSPZZ0202Q    X -   02. MQS TO PERFORM THE.MT & PSE&G TO PERFORM VT. w;o. #931105033 & 931121035 TO PERFORM NOE.
                              "'C.* **
 
DATE: 03/04/94                                   SALEM NUCLEAR PO\IER STATION UNIT 1                                 PAGE:   7
' REVISION:     0                           OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS CHEMICAL AND VOLUME CONTROL SYSTEM N     0 ASME                                   0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! FI CATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** ------------------------------
EXAMINATION AREA                   CATGY   EXAM                         E 0 E   REMARKS NUMBER !DENT! FI CATION                   ITEM NO METHOD     PROCEDURE         c M R   **CALIBRATION BLOCK**
----------
12*CV*1143 ~REF. DWG. NO. A*82 011700 12-CV-1143*3                       B*J     PT         VS1SSISZZ0003Q     x . -   W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO ELBO\I                     B9.11   UT45       VS1SSISZZ0014Q     - x -   INDICATIONS ARE GEOMETRIC REFLECTORS UT45T                         x       FROM THE WELD ROOT AND COUNTERBORE.
---------------
UT45TAN                       x
----------------------------------------
                                                                                            **12*SS-160-1.283.*21 *SAM**
12*CV*1143 DWG. NO. A*82 011700 12-CV-1143*3 B*J PT VS1SSISZZ0003Q x . -W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO ELBO\I B9.11 UT45 VS1SSISZZ0014Q  
3-CV-1141 ~REF. DWG. NO. A-92 016701 3-CV-1141*14                       A*E     PT         VS1SSJSZZ0003Q     x       EXAMINED PER NRC BULLETIN 88*08.
-x -INDICATIONS ARE GEOMETRIC REFLECTORS UT45T x FROM THE WELD ROOT AND COUNTERBORE.
VALVE TO ELBOW                     NB88-08 UT45       VS1SSISZZ0014Q     x - -   W.0.#931121035 TO PERFORM NOE.
UT45TAN x **12*SS-160-1.283.*21  
UT45T                         x - -
*SAM** 3-CV-1141 DWG. NO. A-92 016701 3-CV-1141*14 A*E PT VS1SSJSZZ0003Q x EXAMINED PER NRC BULLETIN 88*08. VALVE TO ELBOW NB88-08 UT45 VS1SSISZZ0014Q x --W.0.#931121035 TO PERFORM NOE. UT45T x --UT45TAN x **3-SS-160*.451-30-SAM**
UT45TAN                       x
016801 3*CV*1141-15 A*E PT VS1SSJSZZ0003Q x --EXAMINED PER NRC BULLETIN 88-08. ELBOW TO BRANCH CONNECTION NB88-08 UT45 VS1SSISZZ0014Q . x -W.0.#931121035 TO PERFORM NOE. THE UT45 UT45T x --INDICATION JS A GEOMETRIC REFLECTOR FROM UT45TAN x THE WELD ROOT. **3-SS-160-.451-30*SAM**
                                                                                            **3-SS-160*.451-30-SAM**
2-CV-1175 DWG. NO. A-11, A*122 022001 2*CV*1175-35 A-E PT VS1SSISZZ0003Q x EXAMINED PER NRC BULLETIN 88-08. VALVE TO PIPE NB88*08 UT45 VS1SSJSZZ0016Q x W.0.#931121035 TO PERFORM NDE. UT45T x . -UT70 x --.,.,. **1.5-SS-COUP-111-SAM**
016801   3*CV*1141-15                       A*E     PT         VS1SSJSZZ0003Q     x -   - EXAMINED PER NRC BULLETIN 88-08.
022101 2*CV*1175*36 A-E PT* VS1SSISZZ0003Q x EXAMINED.PER NRC BULLETIN 88*08. PIPE TO TEE NB88*08 UT45 VS1SSISZZ0016Q x --W.0.#931121035 TO PERFORM NOE. UT45T x UT70 x **1.5-SS-COUP-111-SAM**
ELBOW TO BRANCH CONNECTION         NB88-08 UT45       VS1SSISZZ0014Q     . x   - W.0.#931121035 TO PERFORM NOE. THE UT45 UT45T                         x -   - INDICATION JS A GEOMETRIC REFLECTOR FROM UT45TAN                       x       THE WELD ROOT.
, DATE: p3/04/94 REVISION:
                                                                                            **3-SS-160-.451-30*SAM**
0 PRESSURE RELIEF SYSTEM  
2-CV-1175 ~REF. DWG. NO. A-11, A*122 022001   2*CV*1175-35                       A-E     PT         VS1SSISZZ0003Q     x       EXAMINED PER NRC BULLETIN 88-08.
VALVE TO PIPE                     NB88*08 UT45       VS1SSJSZZ0016Q     x       W.0.#931121035 TO PERFORM NDE.
UT45T                         x .   -
UT70                         x -   -
                            .,.,.                                                           **1.5-SS-COUP-111-SAM**
022101   2*CV*1175*36                       A-E     PT*       VS1SSISZZ0003Q     x       EXAMINED.PER NRC BULLETIN 88*08.
PIPE TO TEE                       NB88*08 UT45       VS1SSISZZ0016Q     x - -   W.0.#931121035 TO PERFORM NOE.
UT45T                         x UT70                         x
                                                                                            **1.5-SS-COUP-111-SAM**
 
, DATE: p3/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    8 REVISION:     0                          OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS PRESSURE RELIEF SYSTEM N      0 ASME                                  0 G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION
EXAMINATION AREA               CATGY     EXAM                         E 0 E     REMARKS NUMBER IDENTIFICATION                    ITEM NO METHOD     PROCEDURE         c M R     **CALIBRATION BLOCK**
------------------------------
4-PR-1100 {REF. DWG. NO. A-162 026600 4-PR-1100-8                      B-J       PT         VS1SSISZZ0003Q   x - -   W.0.#931121035 TO PERFORM NOE.
4-PR-1100
PIPE TO TEE                    B9.11    UT45      VS1SSISZZ0014Q    x UT45T                        x - -
{REF. DWG. 026600 4-PR-1100-8 PIPE TO TEE 3-PR-1107
UT45TAN                      x
{REF. DWG. 027400 3-PR-1107-6 PIPE TO ELBOW 027600 3-PR-1107-8 PIPE TO ELBOW NO. A-162 NO. A-162 3-PR-1106 CREF. DWG. NO. A-17) 028500 3-PR-1106-3 ELBOW TO PIPE SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H CATGY EXAM E 0 E REMARKS ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** PAGE: 8 ----------
                                                                                          **4-SS-160-.533-28-SAM-Rl"*
---------------
3-PR-1107 {REF. DWG. NO. A-162 027400 3-PR-1107-6                      B-J      PT        VS1SSISZZ0003Q    x         W.0.#931121035 TO PERFORM NDE.
----------------------------------------
PIPE TO ELBOW                  B9.21 027600 3-PR-1107-8                      B-J      PT          VS1SSISZZ0003Q  X -   - W.O. 931121035 TO PERFORM NOE.
B-J B9.11 B-J B9.21 B-J B9.21 B-J B9.21 PT UT45 UT45T UT45TAN PT PT PT VS1SSISZZ0003Q VS1SSISZZ0014Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. x x --x **4-SS-160-.533-28-SAM-Rl"*
PIPE TO ELBOW                  B9.21 3-PR-1106 CREF. DWG. NO. A-17) 028500 3-PR-1106-3                      B-J      PT          VS1SSISZZ0003Q  X -   - W.0.#931121035 TO PERFORM NDE.
x W.0.#931121035 TO PERFORM NDE. X --W.O. 931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NDE.
ELBOW TO PIPE                  B9.21
** 
 
' DATE: , 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 10 REVISION:
  ' DATE: , 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                 PAGE:   10 REVISION:     0                         OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
~REACTOR SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
COOLANT SYSTEM SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H  
CLASS 1 SECTION XI COMPLETE COMPONENTS COOLANT SYSTEM N     0 ASME                                   0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! FI CATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** ------------------------------
EXAMINATION AREA                 CATGY     EXAM                         E 0 E   REMARKS NUMBER !DENT! FI CATION                 ITEM NO METHOD       PROCEDURE         c MR    **CALIBRATION BLOCK**
----------
29-RC-1140 (REF. DWG. NO. A-27l 047301   29-RC-1140-1                   B-F       PT         VS1SSISZZ0003Q   x -   - W.0.#931121035 TO PERFORM NOE. FOR SMD NOZZLE TO SAFE-END             B5.130                                         TO REMOVE THE SANDBOX COVERS, SEE W.0.#
---------------
930601187.
----------------------------------------
                                                                                              **37-SAM/76-SAM**
29-RC-1140 (REF. DWG. NO. A-27l 047301 29-RC-1140-1 B-F PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. FOR SMD NOZZLE TO SAFE-END B5.130 TO REMOVE THE SANDBOX COVERS, SEE W.0.# 930601187.  
047401   29-RC-1140-2                   B-J       PT         VS1SSISZZ0003Q   x - -   W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO PIPE               B9.11                                           TO REMOVE THE SANDBOX COVERS, SEE W.0.#
**37-SAM/76-SAM**
930601187.
047401 29-RC-1140-2 B-J PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO PIPE B9.11 TO REMOVE THE SANDBOX COVERS, SEE W.0.# 930601187.  
                                                                                              **2.312-SS-37-SAM**
**2.312-SS-37-SAM**
29-RC-1120 (REF. DWG. NO. A-29l 050901   29-RC-1120-1                   B-F       PT         VS1SSISZZ0003Q   *x - -   w.o.#931121035 TO PERFORM NOE. FOR SMD NOZZLE TO SAFE-END             B5.130                                           TO REMOVE THE SANDBOX COVERS, SEE W.0.#
29-RC-1120 (REF. DWG. NO. A-29l 050901 29-RC-1120-1 B-F PT VS1SSISZZ0003Q  
930601187.
*x --w.o.#931121035 TO PERFORM NOE. FOR SMD NOZZLE TO SAFE-END B5.130 TO REMOVE THE SANDBOX COVERS, SEE W.0.# 930601187.  
                                                                                              **37-SAM/76-SAM**
**37-SAM/76-SAM**
051001   29-RC-1120-2                   B-J       PT         VS1SSISZZ0003Q   x - -   W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO PIPE               B9.11                                           TO REMOVE THE SAND~OX COVERS, SEE W.0.#
051001 29-RC-1120-2 B-J PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO PIPE B9.11 TO REMOVE THE COVERS, SEE W.0.# 930601187.  
930601187.
*.*2.312-SS-37-SAM**
                                                                                              *.*2.312-SS-37-SAM**
27.5-RC-1130 (REF. DWG. NO. A-32l 057201 27.5-RC-1130-4.
27.5-RC-1130 (REF. DWG. NO. A-32l 057201   27.5-RC-1130-4.                 B-J       PT         VS1SSISZZ0003Q   x - -   W.0.#931121035 TO PERFORM NOE. FOR SMD ELBOW TO SAFE-END~*            B9.11                                           TO REMOVE THE SANDBOX COVERS, SEE W.0.#
B-J PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. FOR SMD ELBOW TO B9.11 TO REMOVE THE SANDBOX COVERS, SEE W.0.# 930601187.  
930601187.
**2.312-SS-37-SAM**
                                                                                              **2.312-SS-37-SAM**
057301 27.5-RC-1130-5 B-F PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO NOZZLE B5.130 TO REMOVE THE SANDBOX COVERS, SEE W.0.# 930601187.  
057301   27.5-RC-1130-5                 B-F       PT         VS1SSISZZ0003Q   x - -   W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO NOZZLE             B5.130                                           TO REMOVE THE SANDBOX COVERS, SEE W.0.#
**37-SAM/76-SAM**
930601187.
27.5-RC-1110 (REF. DWG. NO. A-34l 059901 27.5-RC-1110-4 B-J PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. FOR SMD ELBOW*TO SAFE-END B9.11 TO REMOVE THE SANDBOX COVERS, SEE W.0.# 930601187.  
                                                                                              **37-SAM/76-SAM**
**2.312-SS-37-SAM**
27.5-RC-1110 (REF. DWG. NO. A-34l 059901   27.5-RC-1110-4                 B-J       PT         VS1SSISZZ0003Q   x   - -   W.0.#931121035 TO PERFORM NOE. FOR SMD ELBOW*TO SAFE-END               B9.11                                             TO REMOVE THE SANDBOX COVERS, SEE W.0.#
DATE: 03/04/94 'REVISION:
930601187.
0 COOLANT SYSTEM  
                                                                                              **2.312-SS-37-SAM**
 
DATE: 03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                PAGE:    11
    'REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~EACTOR. COOLANT SYSTEM                         CLASS 1 SECTION XI COMPLETE COMPONENTS N      0 ASME                                  0  G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOO PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 11 27.5-RC-1110 CREF. DWG. NO. A-34) 060001 27.5-RC-1110-5 SAFE-END TO NOZZLE * ** B-F PT 85.130 VS1SSISZZ0003CI X --W.0.#931121035 TO PERFORM NOE. FOR SMD TO REMOVE THE SANDBOX COVERS, SEE W.0.# 930601187.  
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOO     PROCEDURE         C M R     **CALIBRATION BLOCK**
**37-SAM/76-SAM**
27.5-RC-1110 CREF. DWG. NO. A-34) 060001 27.5-RC-1110-5                 B-F     PT         VS1SSISZZ0003CI   X -   - W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO NOZZLE            85.130                                          TO REMOVE THE SANDBOX COVERS, SEE W.0.#
DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 12 REVISION:
930601187.
0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H  
                                                                                          **37-SAM/76-SAM**
 
DATE: 03/04/94                                   SALEM NUCLEAR POWER STATION UNIT 1                                 PAGE:     12 REVISION:     0                         OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N     0 ASME                                   0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** ------------------------------
EXAMINATION AREA                 CATGY     EXAM                         E 0 E   REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE         c M R   **CALIBRATION BLOCK**
-----------------
12*SJ*1151 CREF. DWG. NO. A-53) 094700 12-SJ-1151*3                     B*J       PT         VS1SSISZZ0003Q   x       W.O. #931121035 TO PERFORM NOE. THIS ELBOW TO PIPE                 - B9.11     UT45       VS1SSISZZ0014Q   - x   - WELD REPLACES  
---------------
----------------------------------------
12*SJ*1151 CREF. DWG. NO. A-53) 094700 12-SJ-1151*3 B*J PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NOE. THIS ELBOW TO PIPE -B9.11 UT45 VS1SSISZZ0014Q  
-x -WELD REPLACES  


==SUMMARY==
==SUMMARY==
  #094600, DUE TO A UT45T x HANGER OBSTRUCTION.
  #094600, DUE TO A UT45T                       x       HANGER OBSTRUCTION. THE UT45 UT45TAN                     x       INDICATIONS ARE GEOMETRIC REFLECTORS UTO       VS1SSISZZ0018Q   x - -   FROM THE WELD ROOT.
THE UT45 UT45TAN x INDICATIONS ARE GEOMETRIC REFLECTORS UTO VS1SSISZZ0018Q x --FROM THE WELD ROOT. **12-SS-160-1.283-21-SAM**
                                                                                          **12-SS-160-1.283-21-SAM**
10-SJ-1141 (REF. DWG. NO. A-54) 096700 10-SJ-1141-14 B*J PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. VALVE TO TEE B9.11 UT45 VS1SSISZZ0014Q --x LIMITATION:
10-SJ-1141 (REF. DWG. NO. A-54) 096700 10-SJ-1141-14                     B*J       PT         VS1SSISZZ0003Q   x       W.0.#931121035 TO PERFORM NOE.
THE EXAM IS LIMITED TO 0% UT45T --x COVERAGE, DUE TO VALVE \ TEE CONFIGURATION.  
VALVE TO TEE                     B9.11     UT45       VS1SSISZZ0014Q   - -   x LIMITATION: THE EXAM IS LIMITED TO 0%
**10-SS-160-1.119-22-SAM**
UT45T                       - -   x COVERAGE, DUE TO VALVE \ TEE CONFIGURATION.
8-SJ-1162
                                                                                          **10-SS-160-1.119-22-SAM**
{REF. DWG. NO. A-58, A-592 105000 8-SJ-1162*5 B*J .PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO PIPE B9.11 UT45 VS1SSISZZ0014Q  
8-SJ-1162 {REF. DWG. NO. A-58, A-592 105000 8-SJ-1162*5                       B*J     .PT         VS1SSISZZ0003Q   x       W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO PIPE                     B9.11     UT45       VS1SSISZZ0014Q   - x   - INDICATIONS ARE GEOMETRIC REFLECTORS UT45T                       x       FROM THE WELD ROOT.
-x -INDICATIONS ARE GEOMETRIC REFLECTORS UT45T x FROM THE WELD ROOT. UT45TAN x **8-SS*XX*.860-23-SAM**
UT45TAN                     x
8-SJ-1152 CREF. DWG. NO. A-60, A-61> 109600 8*SJ*1152*4PS*2 B*K-1 PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. PENETRATION TO ?IRE B10.10 109900 8-SJ-1152*6 8-J PT VS1SSISZZ0003Q
                                                                                          **8-SS*XX*.860-23-SAM**
* x W.0.#931121035 TO PERFORM NOE *. THE UT45 PIPE TO ELBOW 89.11 UT45 VS1SSISZZ0014Q  
8-SJ-1152 CREF. DWG. NO. A-60, A-61>
-x -INDICATIONS ARE GEOMETRIC INDICATIONS UT45T x FROM THE WELD ROOT AND COUNTERBORE.
109600 8*SJ*1152*4PS*2                   B*K-1     PT         VS1SSISZZ0003Q   x - -   W.0.#931121035 TO PERFORM NOE.
UT45TAN . x **8-SS*XX*.860*23-SAM**
PENETRATION TO ?IRE             B10.10 109900 8-SJ-1152*6                       8-J       PT         VS1SSISZZ0003Q
4-SJ-1182
* x       W.0.#931121035 TO PERFORM NOE *. THE UT45 PIPE TO ELBOW                   89.11     UT45       VS1SSISZZ0014Q   - x   - INDICATIONS ARE GEOMETRIC INDICATIONS UT45T                       x       FROM THE WELD ROOT AND COUNTERBORE.
{REF. DWG. NO. A-74) 129000 4-SJ-1182-14 B*J PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO ELBOW B9.11 UT45 VS1SSISZZ0014Q  
UT45TAN .                   x
-x -INDICATIONS ARE GEOMETRIC REFLECTORS UT45T x FROM THE WELD ROOT. UT45TAN x **4*SS*160*.533*28*SAM-R**
                                                                                          **8-SS*XX*.860*23-SAM**
DATE: 03/04/94 REVISION:
4-SJ-1182 {REF. DWG. NO. A-74) 129000 4-SJ-1182-14                       B*J       PT         VS1SSISZZ0003Q   x       W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO ELBOW                   B9.11     UT45       VS1SSISZZ0014Q   - x   - INDICATIONS ARE GEOMETRIC REFLECTORS UT45T                       x       FROM THE WELD ROOT.
0 SAFETY INJECTION SYSTEM  
UT45TAN                     x
                                                                                          **4*SS*160*.533*28*SAM-R**
 
DATE: 03/04/94                                 SALEM NUCLEAR PO\IER STATION UNIT* 1                                PAGE:    13 REVISION:     0                        OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N    0 ASME                                  0 G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION  
EXAMINATION AREA               CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD      PROCEDURE          c M R    **CALIBRATION BLOCK**
-------------------------------------
4*SJ-1172 {REF. DWG. NO. A*75l 131200 4-SJ-1172-5                     B-J     PT         VS1SSISZZ0003Q           x W.0.#931121035 CNDE). THE PT EXAM ELBO\I TO PIPE                  B9.11    PT                            x   - - REVEALED 6 LINEAR RECORDABLE UT45      VS1SSISZZ0014Q    -   x -   INDICATIONS. DURING THE RELEVANCY UT45T                        x       DETERMINATION PROCESS, SURFACE UT45TAN                      x       CONDITIONING PROCEEDED A.RE-EXAM WITH NO LINEAR INDICATIONS IDENTIFIED. UT45 GEOMETRIC, DUE TO WELD COUNTERBORE.
4*SJ-1172
                                                                                        **4-SS-160-.533-28-SAM-R**
{REF. DWG. NO. A*75l 131200 4-SJ-1172-5 ELBO\I TO PIPE 133800 4-SJ-1172-28 TEE TO REDUCER 3-SJ-1192
133800 4-SJ-1172-28                    B-J      PT        VS1SSISZZ0003Q    x         W.0.#931121035 TO PERFORM NOE. THE UT45 TEE TO REDUCER                  B9.11    UTOL      VS1SSISZZ0018Q    x         INDICATION IS A GEOMETRIC REFLECTOR FROM UT45        VS1SSISZZ0014Q    -   x -   THE WELD ROOT.
{REF. DWG. NO. A-722 134700 3-SJ-1192-BA PIPE TO PIPE 2-SJ-1147 CREF. DWG. NO. A-78) 141500 2-SJ-1147-8FB FLANGE BOLTING 2-SJ-1137 CREF. DWG. NO. A-802 147900 2-SJ-1137-10FB FLANGE BOLTING SALEM NUCLEAR PO\IER STATION UNIT* 1 PAGE: 13 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY ITEM NO B-J B9.11 B-J B9.11 B-J B9.21 B-G-2 B7.50 B-G-2 87.50 EXAM METHOD PROCEDURE
UT45T                        x   - -
----------
UT45TAN                      x   - - **4-SS-160-.533-28-SAM-R**
---------------
3-SJ-1192 {REF. DWG. NO. A-722 134700 3-SJ-1192-BA                    B-J      PT          VS1SSISZZ0003Q    x   - -   W.0.#931121035 TO PERFORM NOE.
PT VS1SSISZZ0003Q PT UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UTOL VS1SSISZZ0018Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q VT-1 SCSSISZZ0010Q VT-1 SCSSISZZ0010Q N 0 0 G T R E H E 0 E REMARKS c M R **CALIBRATION BLOCK** .----------------------------------------
PIPE TO PIPE                    B9.21 2-SJ-1147 CREF. DWG. NO. A-78) 141500 2-SJ-1147-8FB                    B-G-2    VT-1        SCSSISZZ0010Q    X -   - W.O.# 920810139 & 931121035.
x W.0.#931121035 CNDE). THE PT EXAM x --REVEALED 6 LINEAR RECORDABLE  
FLANGE BOLTING                  B7.50 2-SJ-1137 CREF. DWG. NO. A-802 147900 2-SJ-1137-10FB                  B-G-2    VT-1        SCSSISZZ0010Q    X -   - W.0.# 920810145 &931121035.
-x -INDICATIONS.
FLANGE BOLTING                  87.50 2-SJ-1128 CREF. DWG. NO. A-83.84,852 155500 2-SJ-1128-2FB                   B-G-2     VT-1       SCSSISZZ0010Q     X -   -   W.0.# 920810149 & 931121035.
DURING THE RELEVANCY x DETERMINATION PROCESS, SURFACE x CONDITIONING PROCEEDED A.RE-EXAM WITH NO LINEAR INDICATIONS IDENTIFIED.
FLANGE BOLTING                  B7.50
UT45 GEOMETRIC, DUE TO WELD COUNTERBORE.  
 
**4-SS-160-.533-28-SAM-R**
, DATE: , 03/04/94                                   SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    14 REVISION:     0                          OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
x W.0.#931121035 TO PERFORM NOE. THE UT45 x INDICATION IS A GEOMETRIC REFLECTOR FROM -x -THE WELD ROOT. x --x --**4-SS-160-.533-28-SAM-R**
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
x --W.0.#931121035 TO PERFORM NOE. X --W.O.# 920810139  
CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N      O ASME                                  0  G T SEC. XI                                R E H
& 931121035.
X --W.0.# 920810145  
& 931121035.
2-SJ-1128 CREF. DWG. NO. A-83.84,852 155500 2-SJ-1128-2FB FLANGE BOLTING B-G-2 B7.50 VT-1 SCSSISZZ0010Q X --W.0.# 920810149  
& 931121035.
, DATE: , 03/04/94 REVISION:
0 SAFETY INJECTION SYSTEM  


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION_
EXAMINATION AREA                 CATGY    EXAM                        E 0 E REMARKS NUMBER IDENTIFICATION_                   ITEM NO METHOD       PROCEDURE         C M R **CALIBRATION BLOCK**
SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 14 2-SJ-1128 CREF. DWG. NO. A-83.84.85) 158200 2-SJ-1128-29 ELBOW TO PIPE 158600 2-SJ-1128-32 PIPE TO COUPLING B-J B9.40 B-J B9.40 2-SJ-1118 CREF. DWG. NO. A-87. A-88) 165800 2-SJ-1118-4FB FLA.NGE BOL Tl NG 1.5-SJ-1142 DWG. 174300 1 1/2-SJ-1142-43 ELBOW TO PIPE 174900 1 1/2-SJ-1142-49R PIPE TO VALVE 175001 1/2-SJ-1142-50R VALVE TO PIPE 175101 1 1/2-SJ-1142-51R PIPE TO ELBOW NO. B-G-2 B7.50 A-89,90,91}
2-SJ-1128 CREF. DWG. NO. A-83.84.85) 158200 2-SJ-1128-29                       B-J       PT         VS1SSISZZ0003Q   X -   -   W.O. #931121035 TO PERFORM NOE. THIS ELBOW TO PIPE                    B9.40                                          WELD REPLACES  
B-J B9.40 B-J B9.40 A-E NB88-08 A-E NB88-08 PT PT VT-1 PT PT PT UT PT UT VS1SSISZZ0003Q VS1SSISZZ0003Q SCSSISZZ0010Q VS1SSISZZ0003Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q X --W.O. #931121035 TO PERFORM NOE. THIS WELD REPLACES  


==SUMMARY==
==SUMMARY==
  #157900, DUE TO HANGER INTERFERENCE  
  #157900, DUE TO HANGER INTERFERENCE *.
*. X --W.O. #931121035 TO PERFORM NOE. THIS EXAM REPLACES  
158600 2-SJ-1128-32                      B-J      PT        VS1SSISZZ0003Q    X -   - W.O. #931121035 TO PERFORM NOE. THIS PIPE TO COUPLING                  B9.40                                          EXAM REPLACES  


==SUMMARY==
==SUMMARY==
Line 399: Line 668:


==SUMMARY==
==SUMMARY==
  #159100 WAS LOCATED IN THE DECAY TUNNEL. X --W.0.# 920810151  
  #159100 WAS LOCATED IN THE DECAY TUNNEL.
& 931121035.
2-SJ-1118 CREF. DWG. NO. A-87. A-88) 165800 2-SJ-1118-4FB                      B-G-2    VT-1      SCSSISZZ0010Q    X -   - W.0.# 920810151 & 931121035.
x --W.O. #931121035 TO PERFORM NOE. THIS WELD REPLACED  
FLA.NGE BOL Tl NG                B7.50 1.5-SJ-1142    ~REF. DWG. NO. A-89,90,91}
174300 1 1/2-SJ-1142-43 ELBOW TO PIPE B-J      PT        VS1SSISZZ0003Q    x -   - W.O. #931121035 TO PERFORM NOE. THIS B9.40                                          WELD REPLACED  


==SUMMARY==
==SUMMARY==
  #174100, DUE TO A HANGER OBSTRUCTION.
  #174100, DUE TO A HANGER OBSTRUCTION.
x --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-184 & W.0# 920508129.
174900 1 1/2-SJ-1142-49R PIPE TO VALVE B-J B9.40 PT        VHSSSSPZZ0206Q    x - -   PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-184 & W.0#
x --88-08 EXAMS WAIVED, REPLACEMENT.
920508129.
W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-184 & W.0# 920508129.  
175001    1/2-SJ-1142-50R VALVE TO PIPE A-E NB88-08 UT PT        VHSSSSPZZ0206Q    x - -   88-08 EXAMS WAIVED, REPLACEMENT.
**1.5-SS-COUP-111-SAM**
W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-184 &W.0#
x --88-08 EXAMS WAIVED, REPLACEMENT.
920508129.
W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS DUE TO THE REPLACEMENT OF THIS IJELO PER DCP 1E0-2309, CJP# S-93-184 & W.0# 920508129.  
                                                                                            **1.5-SS-COUP-111-SAM**
**1.5-SS-COUP-111-SAM**
175101  1 1/2-SJ-1142-51R                A-E      PT          VHSSSSPZZ0206Q  x   - -   88-08 EXAMS WAIVED, REPLACEMENT.
,DATE: 0,3/04/94 REVISION:
PIPE TO ELBOW                    NB88-08 UT                                      W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PE~FORMED, DUE TO THE REPLACEMENT OF THIS IJELO PER DCP 1E0-2309, CJP# S-93-184 & W.0#
0 INJECTION SYSTEM  
920508129.
                                                                                            **1.5-SS-COUP-111-SAM**
 
    ,DATE: 0,3/04/94                               SALEM NUCLEAR PO\IER STATION UNIT 1                                  PAGE:  15 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~AFETY    INJECTION SYSTEM CLASS 1 SECTION XI COMPLETE COMPONENTS N    0 ASME                                  0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION . SALEM NUCLEAR PO\IER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 15 1.5-SJ-1142 CREF. DWG. NO. A-89.90.91) 179500 1 1/2-SJ-1132-39R PIPE TO VALVE 179601 1 1/2-SJ-1132-40R VALVE TO PIPE 179701 PIPE TO ELBOW 179801 1 1/2-SJ-1132-42 ELBOW TO PIPE ** B-J B9.40 PT A-E PT NB88-08 UT A-E PT NB88-08 UT A-E PT NB88-08 UT45 UT45T UT70 VHSSSSPZZ0206Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q VS1SSISZZ0016Q X --PSI BASELINE EXAMINATION.WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0# 921117149.
EXAMINATION AREA               CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION .                 ITEM NO METHOD     PROCEDURE         C M R   **CALIBRATION BLOCK**
X --88-08 EXAMS WAIVED, REPLACEMENT.
1.5-SJ-1142 CREF. DWG. NO. A-89.90.91) 179500 1 1/2-SJ-1132-39R               B-J     PT         VHSSSSPZZ0206Q     X -   - PSI BASELINE EXAMINATION.WAS PERFORMED, PIPE TO VALVE                  B9.40                                          DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0#
W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & .W.0# 921117149.  
921117149.
**1. 5-SS-COUP-*111-SAM**
179601  1 1/2-SJ-1132-40R              A-E      PT        VHSSSSPZZ0206Q    X -   - 88-08 EXAMS WAIVED, REPLACEMENT.
X --88-08 EXAMS WAIVED, REPLACEMENT.
VALVE TO PIPE                  NB88-08 UT                                      W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & .W.0#
x x x x W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0# 921117149.  
921117149.
**1.5-SS-COUP-111-SAM**
                                                                                          **1. 5-SS-COUP-*111-SAM**
EXAMINED PER NRC BULLETIN 88-08. W.O. #931121035 TO PERFORM NOE. **1.5-SS-COUP-111-SAM**
179701      1/2~SJ-1132-41R            A-E      PT        VHSSSSPZZ0206Q    X -   - 88-08 EXAMS WAIVED, REPLACEMENT.
DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 16 ' REVISIClN:
PIPE TO ELBOW                  NB88-08 UT                                      W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0#
0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H  
921117149.
                                                                                            **1.5-SS-COUP-111-SAM**
179801  1 1/2-SJ-1132-42              A-E      PT        VHSSSSPZZ0206Q    x        EXAMINED PER NRC BULLETIN 88-08. W.O.
ELBOW TO PIPE                  NB88-08 UT45        VS1SSISZZ0016Q    x        #931121035 TO PERFORM NOE.
UT45T                        x UT70                          x
                                                                                            **1.5-SS-COUP-111-SAM**
 
DATE: 03/04/94                                   SALEM NUCLEAR POWER STATION UNIT 1                                 PAGE:     16
'   REVISIClN:     0                       OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N     0 ASME                                 0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** ------------------------------
EXAMINATION AREA                 CATGY   EXAM                         E 0 E REMARKS NUMBER IDENTIFICATION                     ITEM NO METHOD     PROCEDURE         c M R **CALIBRATION BLOCK**
-----------------
1.5-SJ*1132 {REF. OWG. NO. A*92, A*93l 179901   1 1/2*SJ*1132*43               A*E     PT         VS1SSISZZ0003Q   x         EXAMINED PER NRC BULLETIN 88-08.
---------------
PIPE TO BRANCH CONNECTION       NB88*08 UT45       VS1SSISZZ0016Q   x -   . W.0.#931121035 TO PERFORM NOE.
----------------------------------------
UT45T                       x UT70                         x
1.5-SJ*1132
                          ':')
{REF. OWG. NO. A*92, A*93l 179901 1 1/2*SJ*1132*43 A*E PT VS1SSISZZ0003Q x EXAMINED PER NRC BULLETIN 88-08. PIPE TO BRANCH CONNECTION NB88*08 UT45 VS1SSISZZ0016Q x -. W.0.#931121035 TO PERFORM NOE. UT45T x UT70 x ':') **1.5-SS-COUP-111*SAM**
                                                                                            **1.5-SS-COUP-111*SAM**
1.5*SJ*1122
1.5*SJ*1122 {REF. DWG. NO. A*94, A-952 184600 1 1/2*SJ-1122-41R                 'B*J     PT         VHSSSSPZZ0206Q   x - -   PSI BASELINE EXAMINATION WAS PERFORMED.
{REF. DWG. NO. A*94, A-952 184600 1 1/2*SJ-1122-41R  
TEE TO PIPE                     B9.40                                           DUE TO THE REPLACEMENT OF ~HIS WELD PER DCP 1E0-2309; CJP# S-93-181 &W.0.3 930709175.
'B*J PT VHSSSSPZZ0206Q x --PSI BASELINE EXAMINATION WAS PERFORMED.
184700 1 1/2-SJ*1122*42R                 B*J     PT         VHSSSSPZZ0206Q   x -   . PSI BASELINE EXAMINATION WAS PERFORMED, PIPE TO VALVE                   B9.40                                           DUE TO THE REPLACEMENT OF THIS WELD PER OCP 1E0-2309, CJP# S-93-181 & W.0#
TEE TO PIPE B9.40 DUE TO THE REPLACEMENT OF WELD PER DCP 1E0-2309; CJP# S-93-181 & W.0.3 930709175.
930709175.
184700 1 1/2-SJ*1122*42R B*J PT VHSSSSPZZ0206Q x -. PSI BASELINE EXAMINATION WAS PERFORMED, PIPE TO VALVE B9.40 DUE TO THE REPLACEMENT OF THIS WELD PER OCP 1E0-2309, CJP# S-93-181 & W.0# 930709175.
184801   1 1/2-SJ*1122-43R               A-E     PT         VHSSSSPZZ0206Q   x . . 88-08 EXAMS WAIVED, REPLACEMENT.
184801 1 1/2-SJ*1122-43R A-E PT VHSSSSPZZ0206Q x . . 88-08 EXAMS WAIVED, REPLACEMENT.
VALVE TO PIPE                   NB88-08 UT                                     W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-181 & W.0#
VALVE TO PIPE NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-181 & W.0# 930709175.  
930709175.
**1.5-SS-COUP-111-SAM**
                                                                                            **1.5-SS-COUP-111-SAM**
184901 1/2-SJ-1122-44 A-E PT VHSSSSPZZ0206Q x EXAMINED PER NRC BULLETIN 88-08. w.o. PIPE TO ELBOW NB88*08 UT45 VS1SSISZZ0016Q x #931121035 TO PERFORM NOE. UT45T x UT70 x **1.5-SS-COUP-111*SAM**
184901       1/2-SJ-1122-44               A-E     PT         VHSSSSPZZ0206Q   x         EXAMINED PER NRC BULLETIN 88-08. w.o.
185001 1/2-SJ-1122-45 A-E PT VHSSSSPZZ0204Q x EXAMINED PER NRC BULLETIN 88-08. '.1.0. ELBOW TO PIPE NB88-08 UT45 VS1SSISZZ0016Q x #931121035 TO PERFORM NOE. UT45T x UT70 x **1.5-SS-COUP-111-SAM**
PIPE TO ELBOW                   NB88*08 UT45       VS1SSISZZ0016Q   x         #931121035 TO PERFORM NOE.
185101 1 1/2-SJ-1122-46 A-E PT VS1SSISZZ0003Q x EXAMINED PER NRC BULLETIN 88-08. PIPE TO BRANCH CONNECTION NB88-08 UT45 VS1SSISZZ0016Q x --W.0.#931121035 TO PERFORM NOE. UT45T x UT70 x **1.5-SS-COUP-111-SAM**
UT45T                       x UT70                         x
' DATE: 93/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 17 REVISION:*
                                                                                            **1.5-SS-COUP-111*SAM**
0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
185001       1/2-SJ-1122-45               A-E     PT         VHSSSSPZZ0204Q   x         EXAMINED PER NRC BULLETIN 88-08.   '.1.0.
INJECTION SYSTEM SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H  
ELBOW TO PIPE                   NB88-08 UT45       VS1SSISZZ0016Q   x         #931121035 TO PERFORM NOE.
UT45T                       x UT70                         x
                                                                                            **1.5-SS-COUP-111-SAM**
185101   1 1/2-SJ-1122-46                 A-E     PT         VS1SSISZZ0003Q   x         EXAMINED PER NRC BULLETIN 88-08.
PIPE TO BRANCH CONNECTION       NB88-08 UT45       VS1SSISZZ0016Q   x - -   W.0.#931121035 TO PERFORM NOE.
UT45T                       x UT70                         x
                                                                                            **1.5-SS-COUP-111-SAM**
 
DATE: 93/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:   17
  ' REVISION:*
0                       OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~AFETY    INJECTION SYSTEM CLASS 1 SECTION XI COMPLETE COMPONENTS N     0 ASME                                 0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTI Fl CATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** ------------------------------
EXAMINATION AREA                 CATGY   EXAM                         E 0 E     REMARKS NUMBER IDENTI Fl CATION                 ITEM NO METHOD     PROCEDURE         c M R     **CALIBRATION BLOCK**
----------
1'.5*SJ-1112 CREF. DWG. NO. A-96. A-97>
---------------
190100 1 1/2-SJ-1112-49R               B-J     PT         VHSSSSPZZ0206Q   x - -   PSI BASELINE EXAMINATION WAS PERFORMED, PIPE TO VALVE                   B9.40                                           DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 & W.0#
----------------------------------------
921117147.
1'.5*SJ-1112 CREF. DWG. NO. A-96. A-97> 190100 1 1/2-SJ-1112-49R B-J PT VHSSSSPZZ0206Q x --PSI BASELINE EXAMINATION WAS PERFORMED, PIPE TO VALVE B9.40 DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 & W.0# 921117147.
190201 1 1/2-SJ-1112-50R               A-E     PT         VHSSSSPZZ0206Q   x - -   88-08 EXAMS WAIVED, REPLACEMENT.
190201 1 1/2-SJ-1112-50R A-E PT VHSSSSPZZ0206Q x --88-08 EXAMS WAIVED, REPLACEMENT.
VALVE TO PIPE                   NB88-08 UT                                     W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS* PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 & W.0#
VALVE TO PIPE NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS* PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 & W.0# 921117147.  
921117147.
**1.5-SS-COUP-111-SAM**
                                                                                            **1.5-SS-COUP-111-SAM**
190301 1/2-SJ-1112-51R A-E PT VHSSSSPZZ0206Q
190301     1/2-SJ-1112-51R             A-E     PT         VHSSSSPZZ0206Q
* x --88-08 EXAMS WAIVED, REPLACEMENT.
* x   - -   88-08 EXAMS WAIVED, REPLACEMENT.
PIPE TO ELBOW NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP
PIPE TO ELBOW                   NB88-08 UT                                     W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 &W.0#
* 1E0-2309, CJP# S-93-182 & W.0# 921117147.  
921117147.
**1.5-SS-COUP-111-SAM**
                                                                                            **1.5-SS-COUP-111-SAM**
190401 1 1/2-SJ-1112-52 A-E PT VHSSSSPZZ0206Q x EXAMINED PER NRC BULLETIN 88-08. w.o. ELBOW TO PIPE NB88-08 UT45 VS1SSISZZ0016Q x #931121035 TO PERFORM NOE. UT45T x UT70 x **1.5-SS-COUP-111-SAM**
190401   1 1/2-SJ-1112-52               A-E     PT         VHSSSSPZZ0206Q   x         EXAMINED PER NRC BULLETIN 88-08. w.o.
190501 1/2-SJ-1112-53 A-E PT VS1SSISZZ0003Q x --EXAMINED PER NRC BULLETIN 88-08. PIPE TO BRANCH CONNECTION NB88-08 UT45 VS1SSISZZ0016Q x --w.o.#931121035 TO PERFORM NOE. UT45T x --UT70 x **1.5-SS-COUP-111-SAM**  
ELBOW TO PIPE                   NB88-08 UT45       VS1SSISZZ0016Q   x         #931121035 TO PERFORM NOE.
** 
UT45T                       x UT70                         x
, DATE:
                                                                                            **1.5-SS-COUP-111-SAM**
REVISION:
190501       1/2-SJ-1112-53             A-E     PT         VS1SSISZZ0003Q   x   - -   EXAMINED PER NRC BULLETIN 88-08.
0 COOLANT PUMP 12  
PIPE TO BRANCH CONNECTION       NB88-08 UT45         VS1SSISZZ0016Q   x   - -   w.o.#931121035 TO PERFORM NOE.
UT45T                       x   - -
UT70                         x
                                                                                            **1.5-SS-COUP-111-SAM**
 
  , DATE: ~3/04/94                                  SALEM NUCLEAR POWER STATION UNIT 1                                PAGE:    18 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~EACTOR    COOLANT PUMP 12 CLASS 1 SECTION XI COMPLETE COMPONENTS N      0 ASME                                  0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 18 INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 191800 12*PMP*1LG LUG 191850 12-PMP-2LG LUG 191900 12*PMP*3LG LUG B-K-1 PT B10.20 B-K-1 PT B10.20 B*K-1 B10.20 PT PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 192101 12-PMP*FLW A-E PUMP MOTOR FLYWHEEL (IN-PLACE)
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE         C M R   **CALIBRATION BLOCK**
RG1.14 ** UTOL UT45 VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0001Q X *
INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 191800 12*PMP*1LG                       B-K-1     PT         VS1SSISZZ0003Q   X *
* W.0.#931121035 TO PERFORM NOE. LIMITATION:
* W.0.#931121035 TO PERFORM NOE.
THE EXAM IS LIMITED TO 72% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X -* W.0.#931121035 TO PERFORM NOE. LIMITATION:
LUG                            B10.20                                          LIMITATION: THE EXAM IS LIMITED TO 72%
THE EXAM IS LIMITED TO 72% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X *
COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.
* W.0.#931121035 TO PERFORM NOE. x x LIMITATION:
191850 12-PMP-2LG                        B-K-1    PT        VS1SSISZZ0003Q    X -
THE EXAM IS LIMITED TO 76% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. PERFORM IN-PLACE UT EXAMINATION PER PER NRC REGULATORY GUIDE 1.14 & W.O. #931121035 ON RCP MOTOR FLYWHEEL S/N 3S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO THE BORE AND BOLT HOLES. **42-SAM**
* W.0.#931121035 TO PERFORM NOE.
DATE: 03/04/94 REVISION:
LUG                            B10.20                                          LIMITATION: THE EXAM IS LIMITED TO 72%
0 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 19 COOLANT PUMP 14 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS  
COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.
191900 12*PMP*3LG                        B*K-1    PT        VS1SSISZZ0003Q    X *
* W.0.#931121035 TO PERFORM NOE.
LUG                            B10.20                                          LIMITATION: THE EXAM IS LIMITED TO 76%
COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.
PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 192101  12-PMP*FLW                      A-E      UTOL      VS1SSISZZ0001Q    x        PERFORM IN-PLACE UT EXAMINATION PER PER PUMP MOTOR FLYWHEEL (IN-PLACE) RG1.14    UT45                        x        NRC REGULATORY GUIDE 1.14 & W.O.
                                                                                            #931121035 ON RCP MOTOR FLYWHEEL S/N 3S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO THE BORE AND BOLT HOLES.
                                                                                            **42-SAM**
 
DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:   19 REVISION:      0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~EACTOR      COOLANT PUMP 14 CLASS 1 SECTION XI COMPLETE COMPONENTS N      0 ASME                                  O  G  T SEC. XI                                R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION ASME SEC. XI CATGY EXAM ITEM NO METHOD INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 193400 14-PMP-1LG LUG 193450 14-PMP-2LG LUG 193500 14-PMP-3LG LUG B-K-1 PT B10.20 B-K-1 .PT B10.20 B-K-1 PT B10.20 PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 193701 14-PMP-FLW A-E UTOL . PUMP MOTOR FLYWHEEL (IN-PLACE)
EXAMINATION AREA               CATGY      EXAM                        E  0  E  REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE        C  M  R  **CALIBRATION BLOCK**
RG1.14 UT45 ** PROCEDURE VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0001Q N 0 O G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.0.#931121035 TO PERFORM NOE. LIMITATION:
INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 193400 14-PMP-1LG                       B-K-1     PT       VS1SSISZZ0003Q   X - -     W.0.#931121035 TO PERFORM NOE.
THE EXAM IS LIMITED TO 77% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X --W.0.#931121035 TO PERFORM NOE. LIMITATION:
LUG                            B10.20                                          LIMITATION: THE EXAM IS LIMITED TO 77%
THE EXAM IS LIMITED TO 74% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X --W.0.#931121035 TO PERFORM NOE. LIMITATION:
COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.
THE EXAM IS LIMITED TO 76%, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X PERFORM IN-PLACE UT EXAMINATION PER NRC X --REGULATORY GUIDE 1.14 & W.O. #931121035 ON THE RCP MOTOR FLYWHEEL S/N 2S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO BORE AND BOLT HOLES. **42-SAM**   
193450 14-PMP-2LG                      B-K-1    .PT        VS1SSISZZ0003Q    X - -     W.0.#931121035 TO PERFORM NOE.
, DATE: ,03/04/94 REVISION:
LUG                            B10.20                                          LIMITATION: THE EXAM IS LIMITED TO 74%
0  
COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.
193500 14-PMP-3LG                      B-K-1      PT        VS1SSISZZ0003Q  X - -     W.0.#931121035 TO PERFORM NOE.
LUG                            B10.20                                            LIMITATION: THE EXAM IS LIMITED TO 76%,
DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.
PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 193701  14-PMP-FLW                    A-E        UTOL      VS1SSISZZ0001Q  X         PERFORM IN-PLACE UT EXAMINATION PER NRC
          . PUMP MOTOR FLYWHEEL (IN-PLACE) RG1.14    UT45                        X -     - REGULATORY GUIDE 1.14 &W.O. #931121035 ON THE RCP MOTOR FLYWHEEL S/N 2S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO BORE AND BOLT HOLES.
                                                                                            **42-SAM**
 
  , DATE: ,03/04/94                                 SALEM NUCLEAR PO\IER STATION UNIT 1                                PAGE:  20 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
*~
CLASS 1 SECTION xr COMPLETE COMPONENTS N    O ASME                                    0 G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION VALVE BODIES 193870 12 SJ 55 VB ON LINE 10-SJ-1121 BOLTING CREF. DWG. NO. 194100 1 CV 78 ON LINE 3-CV-1133 BOLTING 194700 1 PR 1 ON LINE *3-PR-1106 194800 1 PR 2 ON LINE 3-PR-1107 195400 1 PS 1 ON.LINE 4-PS-1111 195500 1 PS 3 ON LINE 4-PS-1131 197000 11 SJ 43 ON LINE 6-SJ-1112 A-10> SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 20 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION xr COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-M-2 VT-3 B12.50 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 PROCEDURE S1SSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZo010Q SCSSISZZ0010Q SCSSISZZ0010Q N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.O. 931121035 TO PERFORM NDE. --x W.0.# 920810209 AND 931121035 TO PERFORM NDE. ONE (1) STUD WAS FOUND WITH INADEQUATE THREAD ENGAGEMENT.
EXAMINATION AREA               CATGY    EXAM                          E 0 E  REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD      PROCEDURE          C M R  **CALIBRATION BLOCK**
A DR WAS ISSUED TO SYSTEM ENGINEERING.
VALVE BODIES 193870 12 SJ 55 VB                     B-M-2    VT-3       S1SSISZZ0010Q      X -   - W.O. 931121035 TO PERFORM NDE.
w.o. #93100204 CORRECTED THE THREAD ENGAGEMENT PROBLEM. A SA Tl S FACTORY RE-EXAM WAS PERFORMED. x --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO DCP 1EC-3219-1, CJP# PS-93-053  
ON LINE 10-SJ-1121            B12.50 BOLTING CREF. DWG. NO. A-10>
& W.0.# 930126150.
194100 1 CV 78                          B-G-2     VT-1       SCSSISZZ0010Q     - -   x W.0.# 920810209 AND 931121035 TO PERFORM ON LINE 3-CV-1133              B7.70                                          NDE. ONE (1) STUD WAS FOUND WITH INADEQUATE THREAD ENGAGEMENT. A DR WAS ISSUED TO SYSTEM ENGINEERING. w.o.
NEW STUDS AND NUTS WERE INSTALLED.
                                                                                          #93100204 CORRECTED THE THREAD ENGAGEMENT PROBLEM. A SA Tl SFACTORY RE-EXAM WAS PERFORMED.
x --PSI BASELINE 'EXAMINATION WAS PERFORMED, DUE TO DCP 1EC-3219-1, CJP# PS-93-054  
BOLTING 194700 1 PR 1                          B-G-2    VT-1      SCSSISZZ0010Q      x -   - PSI BASELINE EXAMINATION WAS PERFORMED, ON LINE *3-PR-1106            B7.70                                          DUE TO DCP 1EC-3219-1, CJP# PS-93-053 &
& W.0.# 930126150.
W.0.# 930126150. NEW STUDS AND NUTS WERE INSTALLED.
NEW STUDS AND NUTS WERE INSTALLED.
194800 1 PR 2                          B-G-2    VT-1      SCSSISZZ0010Q      x - - PSI BASELINE 'EXAMINATION WAS PERFORMED, ON LINE 3-PR-1107              B7.70                                          DUE TO DCP 1EC-3219-1, CJP# PS-93-054 &
x --THE BOLTING WAS REPLACED PER 1EC-3249-1/PS-93-056/930708108  
W.0.# 930126150. NEW STUDS AND NUTS WERE INSTALLED.
& 931121035.
                              ~*
x --THE BOLTING WAS REPLACED PER 1EC-3249-1/PS-93-057/930708111  
195400 1 PS 1                          B-G-2    VT-1      SCSSISZZo010Q      x - - THE BOLTING WAS REPLACED PER ON.LINE 4-PS-1111              B7.70                                          1EC-3249-1/PS-93-056/930708108 &
& 931121035.
931121035.
x --W.0.# 920810155 AND 931121035 TO PERFORM NDE.
195500 1 PS 3                          B-G-2    VT-1      SCSSISZZ0010Q      x - - THE BOLTING WAS REPLACED PER ON LINE 4-PS-1131              B7.70                                          1EC-3249-1/PS-93-057/930708111 &
, DATE: 03/04/94 REVISION:
931121035.
0  
197000 11 SJ 43                          B-G-2    VT-1      SCSSISZZ0010Q      x - - W.0.# 920810155 AND 931121035 TO PERFORM ON LINE 6-SJ-1112              B7.70                                          NDE.
 
, DATE: 03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    21 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS N      O ASHE                                  0 G T SEC. -XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION BOLTING CREF. DWG. NO. A-68) 197900 12 SJ 43 ON LINE 6-SJ-1122 BOLTING CREF. DWG. NO. A-56) 198200 12 SJ 55 ON LINE 10-SJ-1121 198300 12 SJ 56 ON LINE 10-SJ-1121 BOLTING CREF. DWG. NO. A-66) 198800 13 SJ 43 ON LINE 6-SJ-1132 BOLTING CREF. DWG. NO. A-67) 199200 13 SJ 156 ON LINE 6-SJ-1131 BOLTING 199500 14 RH 27 ON LINE 8-SJ-1145 199600 14 SJ 43 ON LINE 6-SJ-1142 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 21 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASHE SEC. -XI CATGY EXAM ITEM NO METHOD B-G-2 B7.70 B7.70 B-G-2 B7.70 B-G-2 B7.70 B-G-2 B7.70 B-G-2 B7.70 B-G-2 B7.70 VT-1 VT-1 VT-1 VT-1 VT-1 VT*1 VT-1 PROCEDURE SCSSISZZ001QQ SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.0.# 920810158 AND 931121035 TO PERFORM NOE. --x W.0.# 920810195
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD      PROCEDURE        C M R    **CALIBRATION BLOCK**
& 931121035 TO PERFORM NOE. THE VT-1 EXAM REVEALED BORON RESIDUE BETWEEN THE VALVE BODY TO BONNET. THE VALVE WAS DISASSEMBLED  
BOLTING CREF. DWG. NO. A-68) 197900 12 SJ 43                       B-G-2    VT-1      SCSSISZZ001QQ    X -   - W.0.# 920810158 AND 931121035 TO PERFORM ON LINE 6-SJ-1122            B7.70                                            NOE.
& INSPECTED  
BOLTING CREF. DWG. NO. A-56) 198200 12 SJ 55                        B~G-2     VT-1       SCSSISZZ0010Q     - - x    W.0.# 920810195 & 931121035 TO PERFORM ON LINE 10-SJ-1121            B7.70                                            NOE. THE VT-1 EXAM REVEALED BORON RESIDUE BETWEEN THE VALVE BODY TO BONNET. THE VALVE WAS DISASSEMBLED &
& BOLTING MATERIAL WAS REPLACED UNDER W.O. # 931002074  
INSPECTED & BOLTING MATERIAL WAS REPLACED UNDER W.O. # 931002074 & CJP
& CJP #S-93-250.
                                                                                        #S-93-250.
x ---W.0.# 920810203  
198300 12 SJ 56                        B-G-2    VT-1      SCSSISZZ0010Q    x - -   -W.0.# 920810203 ON LINE 10-SJ-1121            B7.70 BOLTING CREF. DWG. NO. A-66) 198800 13 SJ 43                        B-G-2    VT-1      SCSSISZZ0010Q    - -   x W.0.# 920810161 & 931121035 TO PERFORM ON LINE 6-SJ-1132            B7.70                                            NOE. BORON RESIDUE WAS FOUND ON SEVERAL STUDS. W.O. #931026136 REMOVED THE BORON AND A SATISFACTORY VT RE-EXAM WAS PERFORMED.
--x W.0.# 920810161  
BOLTING CREF. DWG. NO. A-67) 199200 13 SJ 156                      B-G-2    VT-1      SCSSISZZ0010Q    x - -   W.0.# 920810173-ON LINE 6-SJ-1131            B7.70 BOLTING 199500 14 RH 27                        B-G-2    VT*1      SCSSISZZ0010Q    x - -   THE BOLTING MATERIAL WAS REPLACED IH ON LINE 8-SJ-1145            B7.70                                            ACCORDANCE WITH CJP #S-93-249 & W.O.
& 931121035 TO PERFORM NOE. BORON RESIDUE WAS FOUND ON SEVERAL STUDS. W.O. #931026136 REMOVED THE BORON AND A SATISFACTORY VT RE-EXAM WAS PERFORMED.
                                                                                        #940326008.
x --W.0.# 920810173-x --THE BOLTING MATERIAL WAS REPLACED IH ACCORDANCE WITH CJP #S-93-249  
199600 14 SJ 43                        B-G-2    VT-1      SCSSISZZ0010Q    x - -   W.0.# 920810162 AND 931121035 TO PERFORM ON LINE 6-SJ-1142            B7.70                                            NOE.
& W.O. #940326008.
 
x --W.0.# 920810162 AND 931121035 TO PERFORM NOE.
DATE: 03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:  22
DATE: 03/04/94 'REVIS1014:
'REVIS1014:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
0  
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS N      0 ASME                                  0 G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION BOLTING (REF. DWG. NO. A-54) 199700 14 SJ 54 ON LINE 10-SJ-1141 199800 14 SJ 55 ON LINE 10-SJ-1141 199900 14 SJ 56 ON LINE 10-SJ-1141 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 22 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-G-2 B7.70 B-G-2 B7.70 B-G-2 87.70 VT-1 VT-1 VT-1 PROCEDURE SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q N 0 0 G T R E H E 0 E. REMARKS C M R **CALIBRATION BLOCK** --X W.0.# 920810207  
EXAMINATION AREA               CATGY    EXAM                        E 0 E. REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD      PROCEDURE        C M R    **CALIBRATION BLOCK**
& 931121035 TO PERFORM NOE. THE VT REVEALED BORON RESIDUE ON THE STUDS. W.O. #931013197 WAS INITIATED TO CLEAN OFF THE BORON. AFTER THE BORON WAS REMOVED A SATISFACTORY VT-1 EXAM WAS PERFORMED. X --W.0.# 920810201* --X W.0.# 920810206  
BOLTING (REF. DWG. NO. A-54) 199700 14 SJ 54                       B-G-2   VT-1       SCSSISZZ0010Q     - - X   W.0.# 920810207 & 931121035 TO PERFORM ON LINE 10-SJ-1141            B7.70                                          NOE. THE VT REVEALED BORON RESIDUE ON THE STUDS. W.O. #931013197 WAS INITIATED TO CLEAN OFF THE BORON. AFTER THE BORON WAS REMOVED A SATISFACTORY VT-1 EXAM WAS PERFORMED.
& 931121035 TO PERFORM NOE. THE VISUAL EXAMINATION REVEALED SEVERAL STUDS WITH A LACK OF THREAD ENGAGEMENT.
199800 14 SJ 55                      B-G-2    VT-1      SCSSISZZ0010Q    X -   - W.0.# 920810201*
W.O. #930730004 DISSASSEMBLED  
ON LINE 10-SJ-1141            B7.70 199900 14 SJ 56                      B-G-2    VT-1        SCSSISZZ0010Q    -   - X   W.0.# 920810206 &931121035 TO PERFORM ON LINE 10-SJ-1141            87.70                                            NOE. THE VISUAL EXAMINATION REVEALED SEVERAL STUDS WITH A LACK OF THREAD ENGAGEMENT. W.O. #930730004 DISSASSEMBLED & INSPECTED THIS VALVE.
& INSPECTED THIS VALVE. DURING RE-ASSEMBLY THE LACK OF THREAD ENGAGEMENT WAS CORRECTED.
DURING RE-ASSEMBLY THE LACK OF THREAD ENGAGEMENT WAS CORRECTED.
, DATE: p3/04/94 REVISION:
 
0 TANKS, VESSEL 11  
  , DATE: p3/04/94                               SALEM NUCLEAR PO\JER STATION UNIT 1                                PAGE:  23 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~HEAD    TANKS, VESSEL 11 CLASS 2 SECTION XI COMPLETE COMPONENTS N    0 ASHE                                  0 G T SEC. XI                                R E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\JER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASHE SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 23 CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-4) 204900 11-HT-1 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE. UPPER HEAD TO SHELL C1.20 UTOW --x LIMITATION:
EXAMINATION AREA               CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R   **CALIBRATION BLOCK**
EXAM LIMITED TO 38%, DUE TO UT45 VS1SSISZZ0012Q x WELD CONFIGURATION.
CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-4) 204900 11-HT-1                         C-A     UTOL       VS1SSISZZ0018Q     x       W.0.#931121035 TO PERFORM NOE.
UT ON THE WELD NOT UT45T x PERFORMED, DUE TO THE WELD UT45TAN x CONFIGURATION.  
UPPER HEAD TO SHELL           C1.20   UTOW                         - -   x LIMITATION: EXAM LIMITED TO 38%, DUE TO UT45       VS1SSISZZ0012Q     x       WELD CONFIGURATION. UT ON THE WELD NOT UT45T                         x       PERFORMED, DUE TO THE WELD UT45TAN                       x       CONFIGURATION.
**6-SS-10-.140-45-SAM**
                                                                                          **6-SS-10-.140-45-SAM**
, DATE: ,03/04/94 REVISION:
 
0
  , DATE: ,03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:  24 REVISION:     0                        OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)
* REACTOR COOLANT FILTER  
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
CLASS 2 SECTION XI CC>>4PLETE CC>>4PONENTS
* REACTOR COOLANT FILTER N      0 ASME                                    0  G  T SEC. XI                                  R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 2 SECTION XI CC>>4PLETE CC>>4PONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 24 CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-6) 205020 1-RCF-1 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE. UPPER HEAD TO FLANGE C1.20 UTOW x LIMITATION:
EXAMINATION AREA               CATGY    EXAM                          E  0  E REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE           C M   R **CALIBRATION BLOCK**
EXAM LIMITED TO 74%, DUE TO UT45 VS1SSISZZ0012Q x --CONFIGURATION.
CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-6) 205020 1-RCF-1                       C-A       UTOL       VS1SSISZZ0018Q     x       W.0.#931121035 TO PERFORM NOE.
UT45T x UT45TAN x **14-SS-10-.250-96-SAM**
UPPER HEAD TO FLANGE           C1.20     UTOW                           x       LIMITATION: EXAM LIMITED TO 74%, DUE TO UT45       VS1SSISZZ0012Q     x - -   CONFIGURATION.
205030 1-RCF-2 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE. FLANGE TO SHELL C1.10 UTOW x LIMITATION:
UT45T                         x UT45TAN                       x       **14-SS-10-.250-96-SAM**
EXAM LIMITED TO 86%, DUE TO UT45 VS1SSISZZ0012Q x CONFIGURATION AND WELDED SUPPORT. UT45T x UT45TAN x **14-SS-10-.250-96-SAM**
205030 1-RCF-2                         C-A       UTOL       VS1SSISZZ0018Q     x       W.0.#931121035 TO PERFORM NOE.
, DATE: ,03/04/94 REVISION:
FLANGE TO SHELL               C1.10     UTOW                           x       LIMITATION: EXAM LIMITED TO 86%, DUE TO UT45       VS1SSISZZ0012Q     x       CONFIGURATION AND WELDED SUPPORT.
0 HEAT EXCHANGER  
UT45T                         x UT45TAN                       x       **14-SS-10-.250-96-SAM**
 
    , DATE: ,03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                PAGE:    25 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~REGENERATIVE      HEAT EXCHANGER CLASS 2 SECTION XI COMPLETE COMPONENTS N      0 ASME                                  0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 25 CIRCUMFERENTIAL WELDS (REF. DWG. NO. B-7) 205105 1-RHE-5 CAP TO SHELL 205120 1-RHE-8 SHELL TO CAP C-A C1 .10 C-A C1 .10 UTOL VS1SSISZZ0018Q UTOW UT45 VS1 SS! SZZ0013Q UT45T UT60 UT60T UTOL VS1SSISZZ0018Q UTOW UT45 VS1SSISZZ0013Q UT45T UT60 UT60T x --W.0.#931121035 TO PERFORM NDE. THE UT45 x INDICATION IS A GEOMETRIC REFLECTOR FROM -x -THE INSIDE SURFACE. x --x --**9.5-SS-X-.750-86-SAM**
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD       PROCEDURE         C M R   **CALIBRATION BLOCK**
x x W.0.#931121035 TO PERFORM NOE. THE UT45 x AND UT60 INDICATIONS ARE  
CIRCUMFERENTIAL WELDS (REF. DWG. NO. B-7) 205105 1-RHE-5 CAP TO SHELL C-A       UTOL       VS1SSISZZ0018Q   x - -   W.0.#931121035 TO PERFORM NDE. THE UT45 C1 .10    UTOW                        x       INDICATION IS A GEOMETRIC REFLECTOR FROM UT45      VS1 SS! SZZ0013Q  - x -   THE INSIDE SURFACE.
-x -REFLECTORS FROM THE WELD ROOT. x -x -**9.5-SS-X-.750-86-SAM**
UT45T                        x - -
x
UT60                        x - -   **9.5-SS-X-.750-86-SAM**
UT60T                        x 205120 1-RHE-8                        C-A      UTOL      VS1SSISZZ0018Q    x       W.0.#931121035 TO PERFORM NOE. THE UT45 SHELL TO CAP                  C1 .10    UTOW                        x       AND UT60 INDICATIONS ARE G~OMETRIC UT45      VS1SSISZZ0013Q    - x -   REFLECTORS FROM THE WELD ROOT.
UT45T                        x UT60                        - x -   **9.5-SS-X-.750-86-SAM**
UT60T                        x
 
PAGE: 26 ASME SEC. XI


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION ASME SEC. XI CATGY EXAM ITEM NO METHOD INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. B-8) 205170 11-RHRHEX-1VS VESSEL SUPPORT 205180 11-RHRHEX-2VS VESSEL SUPPORT c-c C3.10 c-c C3.10 PT PT PAGE: 26 REMARKS PROCEDURE
EXAMINATION AREA               CATGY    EXAM                        REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD PROCEDURE            **CALIBRATION BLOCK**
**CALIBRATION BLOCK** VS1SSISZZ0003Q X --W.0.#931121035 TO PERFORM NOE. VS1SSISZZ0003Q X --W.0.#931121035 TO PERFORM NOE.
INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. B-8) 205170 11-RHRHEX-1VS                 c-c     PT     VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.
, DATE: P3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 27 REVISION:
VESSEL SUPPORT                C3.10 205180  11-RHRHEX-2VS                  c-c      PT    VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.
0 OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS FEEDWATER SYSTEM N 0 ASME 0 G T SEC. XI R E H  
VESSEL SUPPORT                C3.10
                        *~*
 
, DATE: P3/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:   27 REVISION:     0                         OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS FEEDWATER SYSTEM N     0 ASME                                 0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! Fl CATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** ------------------------------
EXAMINATION AREA               CATGY   EXAM                         E 0 E     REMARKS NUMBER !DENT! Fl CATION                 ITEM NO METHOD     PROCEDURE         c MR      **CALIBRATION BLOCK**
-----------------
16-BF-2141 (REF. DWG. NO. B-102 210601   16*BF*2141*1R                   A*E     RT         VSHSSSPZZ0210Q   x - -   PERFORM NOE UNDER W.O. # 9304216193. 45 REDUCER TO NOZZLE               ATS     UT45       VS1SSISZZ0017Q   - x -     AND 60 DEGREE INDICATIONS ARE GEOMETRIC UT45T                       x - -     REFLECTORS FROM THE INSIDE SURFACE.
---------------
UT60                         - x -
----------------------------------------
UT60T                       x         **116-SAM**
16-BF-2141 (REF. DWG. NO. B-102 210601 16*BF*2141*1R A*E RT VSHSSSPZZ0210Q x --PERFORM NOE UNDER W.O. # 9304216193.
16-BF-2131 (REF. DWG. NO. B-112 213401   16*BF*2131 *,1R                 A*E     RT         VSHSSSPZZ0210Q   x         PERFORM NOE UNDER W.O. 930426192. THE ELBOW TO NOZZLE                 ATS     UT45       VS1SSISZZ0017Q   x         60 DEGREE INDICATION IS A GEOMETRIC UT45T                       x         REFLECTOR FROM THE WELD ROOT.
45 REDUCER TO NOZZLE ATS UT45 VS1SSISZZ0017Q  
UT60                         - x   -
-x -AND 60 DEGREE INDICATIONS ARE GEOMETRIC UT45T x --REFLECTORS FROM THE INSIDE SURFACE. UT60 -x -UT60T x **116-SAM**
UT60T                       x         **35-SAM/36-SAM**
16-BF-2131 (REF. DWG. NO. B-112 213401 16*BF*2131  
16-BF-2121 (REF. DWG. NO. e-122 217791   16*BF*2121*1R                   A*E     RT         VSHSSSPZZ0210Q   x         PERFORM NOE UNDER W.O. # 930426190. THE REDUCER TO NOZZLE               ATS     UT45       VS1SSISZZ0017Q     - x   - 45 AND 60 DEGREE INDICATIONS ARE UT45T                       x         GEOMETRIC REFLECTORS FROM THE WELD ROOT.
*,1R A*E RT VSHSSSPZZ0210Q x PERFORM NOE UNDER W.O. 930426192.
UT60                         - x   -
THE ELBOW TO NOZZLE ATS UT45 VS1SSISZZ0017Q x 60 DEGREE INDICATION IS A GEOMETRIC UT45T x REFLECTOR FROM THE WELD ROOT. UT60 -x -UT60T x **35-SAM/36-SAM**
UT60T                       x         **116-SAM**
16-BF-2121 (REF. DWG. NO. e-122 217791 16*BF*2121*1R A*E RT VSHSSSPZZ0210Q x PERFORM NOE UNDER W.O. # 930426190.
16-BF-2111 (REF. DWG. NO. B-132 220573 16*BF*2111*1R                     A*E     RT         VSHSSSPZZ0210Q   x         PERFORM NOE UNDER- W.O. 930426188. THE REDUCER TO NOZZLE               ATS     UT45       VS1SSISZZ0017Q     - x -     45 AND 60 DEGREE INDICATIONS ARE UT45T                       x         GEOMETRIC REFLECTORS FROM THE WELD ROOT.
THE REDUCER TO NOZZLE ATS UT45 VS1SSISZZ0017Q  
UT60                         - x -
-x -45 AND 60 DEGREE INDICATIONS ARE UT45T x GEOMETRIC REFLECTORS FROM THE WELD ROOT. UT60 -x -UT60T x **116-SAM**
UT60T                       x - -     **116-SAM**
16-BF-2111 (REF. DWG. NO. B-132 220573 16*BF*2111*1R A*E RT VSHSSSPZZ0210Q x PERFORM NOE UNDER-W.O. 930426188.
 
THE REDUCER TO NOZZLE ATS UT45 VS1SSISZZ0017Q  
DATE: 03/04/94                                 SALEM NUCLEAR PO\IER STATION UNIT 1                                PAGE:    28
-x -45 AND 60 DEGREE INDICATIONS ARE UT45T x GEOMETRIC REFLECTORS FROM THE WELD ROOT. UT60 -x -UT60T x --**116-SAM**
' REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
DATE: 03/04/94 ' REVISION:
SECOND INTERVAL, SECOND PERia>, SECOND OUTAGE (93RF)
0 MAIN STEAM SYSTEM  
CLASS 2 SECTION XI COMPLETE COMPONENTS MAIN STEAM SYSTEM N    0 ASME                                    0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\IER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERia>, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO-METHOD PROCEDURE
EXAMINATION AREA                 CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO- METHOD     PROCEDURE _       C M R   **CALIBRATION BLOCK**
_ N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 28 32-MS-2141 CREF. DWG. NO. B-25) 227600 32-MS-2141-1 NOZZLE TO REDUCER 32-MS-2121 CREF. DWG. NO. B-27> 229900 32-MS-2121-2PS-1 PIPE SUPPORT 30-MS-2141
32-MS-2141 CREF. DWG. NO. B-25) 227600 32-MS-2141-1                     C-F-2    MT        VS1SSISZZ0002Q    X        W.0.#931121035 TO PERFORM NOE.
{REF. 232000 30-MS-2141-1 REDUCER TO ELBOW 232040 30-MS-2141-1LD-I LONGITUDINAL 232080 30-MS-2141-1LD-O LONGITUDINAL DWG. NO. B-25) C-F-2 C5.51 c-c C3.20 C-F-2 C5.51 C-F*2 C5.52 C-F-2 C5.52 MT UT45 UT45T MT MT UT45 UT45T MT UT45 UT45T MT UT45 UT45T VS1SSISZZ0002Q X VS1SSISZZ0017Q
NOZZLE TO REDUCER               C5.51    UT45      VS1SSISZZ0017Q    *X UT45T                        x - -
* X x --W.0.#931121035 TO PERFORM NOE. **32*CS-XX-1.618-47-SAM**
                                                                                          **32*CS-XX-1.618-47-SAM**
VS1SSISZZ0002Q X --W.0.#931121035 TO PERFORM NOE. VS1SSISZZ0002Q x --W.0.#931121035 TO PERFORM NOE. THE UT45 VS1SSISZZ0017Q  
32-MS-2121 CREF. DWG. NO. B-27>
-x -INDICATIONS ARE GEOMETRIC REFLECTORS x FROM THE WELD ROOT. **PL-1.5-CS-65-SAM**
229900 32-MS-2121-2PS-1                 c-c      MT        VS1SSISZZ0002Q    X -  -  W.0.#931121035 TO PERFORM NOE.
VS1SSISZZ0002Q x --W.0.#931121035 TO PERFORM NOE. EXAMINE VS1SSISZZ0017Q x 2.5T OF WELD LENGTH. x **PL-1.5-CS-65-SAM**
PIPE SUPPORT                   C3.20 30-MS-2141 {REF. DWG. NO. B-25) 232000 30-MS-2141-1                      C-F-2   MT         VS1SSISZZ0002Q     x - -   W.0.#931121035 TO PERFORM NOE. THE UT45 REDUCER TO ELBOW                C5.51    UT45       VS1SSISZZ0017Q     - x   - INDICATIONS ARE GEOMETRIC REFLECTORS UT45T                        x         FROM THE WELD ROOT.
VS1SSISZZ0002Q x --W.0.#931121035 TO PERFORM NOE. -EXAMINE VS1SSISZZ0017Q x 2.5T OF WELD LENGTH. x **PL-1.5-CS-65-SAM**
                                                                                          **PL-1.5-CS-65-SAM**
, DATE: .03/04/94 REVISION:
232040 30-MS-2141-1LD-I                  C-F*2    MT          VS1SSISZZ0002Q   x   - -   W.0.#931121035 TO PERFORM NOE. EXAMINE LONGITUDINAL                    C5.52    UT45      VS1SSISZZ0017Q   x         2.5T OF WELD LENGTH.
0 PRESSURE RELIEF SYSTEM  
UT45T                        x
                                                                                          **PL-1.5-CS-65-SAM**
232080 30-MS-2141-1LD-O                  C-F-2    MT        VS1SSISZZ0002Q     x - -   W.0.#931121035 TO PERFORM NOE. - EXAMINE LONGITUDINAL                    C5.52    UT45      VS1SSISZZ0017Q     x       2.5T OF WELD LENGTH.
UT45T                        x
                                                                                          **PL-1.5-CS-65-SAM**
 
, DATE: .03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                PAGE:    29 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS PRESSURE RELIEF SYSTEM N      O ASME                                  0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 29 12-PR-2101 CREF. DWG. NO. B-37, B-38) 254900 12-PR-2101-2 PIPE TOPiPE C-F-1 PT C5.11 . UT45 UT45T UT45TAN VS1SSISZZ0003Q VS1SSISZZ0014Q x x x x W.O. #931121035 TO PERFORM NOE. THIS WELD REPLACED  
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD       PROCEDURE         C M R   **CALIBRATION BLOCK**
12-PR-2101 CREF. DWG. NO. B-37, B-38) 254900 12-PR-2101-2                   C-F-1     PT         VS1SSISZZ0003Q   x       W.O. #931121035 TO PERFORM NOE. THIS PIPE TOPiPE                    C5.11 . UT45      VS1SSISZZ0014Q    x        WELD REPLACED  


==SUMMARY==
==SUMMARY==
  #254400, DUE TO HANGER INTERFERENCE.
  #254400, DUE TO UT45T                        x        HANGER INTERFERENCE. EXAMINED 2.5T OF UT45TAN                      x        THE INTERSECTING LONGITUDINAL SEAM ON THE UP STREAM AND DOWN STREAM SIDE.
EXAMINED 2.5T OF THE INTERSECTING LONGITUDINAL SEAM ON THE UP STREAM AND DOWN STREAM SIDE. **31-SAM/66-SAM**
                                                                                        **31-SAM/66-SAM**
' DATE: P3/04/94 REliISION:
 
0 ESIDUAL HEAT REMOVAL SYSTEM  
    ' DATE: P3/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:  30 REliISION:     0                        OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS ESIDUAL HEAT REMOVAL SYSTEM N      0 ASME                                  0 G T SEC. XI                              R. E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION 263294 14-RH-2114-16PS-2 PIPE SUPPORT 263296 14-RH-2114-16PS-3 PIPE SUPPORT .,..,.. 14-RH-2114-16PS-4 PIPE SUPPORT 263304 14-RH-2114-18 FLANGE TO PUMP "'" 14-RH-2112 CREP. DWG. NO. 263384 14-RH-2112-29 TEE TO PIPE ** SALEM NUCLEAR POWER STATION UNIT 1 PAGE: OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOO c-c C3.20 c-c C3.20 c-c C3.20 C-F-1 PT PT PT PT PROCEDURE VS1SSI.SZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q N 0 0 G T R. E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.0.#931121035 TO PERFORM NOE. x --W.0.#931121035 TO PERFORM NOE. x --W.0.#931121035 TO PERFORM NOE. x W.0.#931121035 TO PERFORM NOE. 30 CS.11 UT45T VS1SSISZZ0014Q x LIMITATION:
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOO      PROCEDURE        C M R    **CALIBRATION BLOCK**
THE UT EXAM WAS LIMITED TO SOX COVERAGE.
263294 14-RH-2114-16PS-2                 c-c      PT        VS1SSI.SZZ0003Q  X -    -  W.0.#931121035 TO PERFORM NOE.
THE TRANVERSE SCAN WAS THE ONLY UT PERFORMED, DUE TO THE FLANGE AND PUMP CONFIGURATION.  
PIPE SUPPORT                   C3.20 263296 14-RH-2114-16PS-3                 c-c      PT        VS1SSISZZ0003Q    x  - -    W.0.#931121035 TO PERFORM NOE.
**14-SS-40-.438-79-SAM**
.,..,..       PIPE SUPPORT 14-RH-2114-16PS-4 PIPE SUPPORT C3.20 c-c C3.20 PT         VS1SSISZZ0003Q   x  - -   W.0.#931121035 TO PERFORM NOE.
B-46> C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. CS.11 UT45 VS1SSISZZ0014Q x EXAMINATION INCLUDES 2.ST OF THE UT45T x INTERSECTING LONGITUDINAL SEAM ON THE UT45TAN x DOWN STREAM SIDE. **14-SS-40-.438*79-SAM**
263304 14-RH-2114-18                      C-F-1    PT        VS1SSISZZ0003Q    x        W.0.#931121035 TO PERFORM NOE.
DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 31 ' REVISIO!i:
FLANGE TO PUMP                  CS.11   UT45T     VS1SSISZZ0014Q   x         LIMITATION: THE UT EXAM WAS LIMITED TO
0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) ' SECOND INTERVAL, SECOND PERIOD,* SECOND OUTAGE (93RF) CLASS 2 SECTION XI CC>>4PLETE COMPONENTS INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H  
                              "'"                                                            SOX COVERAGE. THE TRANVERSE SCAN WAS THE ONLY UT PERFORMED, DUE TO THE FLANGE AND PUMP CONFIGURATION.
                                                                                              **14-SS-40-.438-79-SAM**
14-RH-2112 CREP. DWG. NO. B-46>
263384 14-RH-2112-29                      C-F-1   PT         VS1SSISZZ0003Q   x         W.0.#931121035 TO PERFORM NOE.
TEE TO PIPE                    CS.11   UT45       VS1SSISZZ0014Q   x         EXAMINATION INCLUDES 2.ST OF THE UT45T                       x         INTERSECTING LONGITUDINAL SEAM ON THE UT45TAN                     x         DOWN STREAM SIDE.
                                                                                              **14-SS-40-.438*79-SAM**
 
                                                                                                                                      ~1/.1 DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                     PAGE:   31
' REVISIO!i:   0                         OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
    '                                   SECOND INTERVAL, SECOND PERIOD,* SECOND OUTAGE (93RF)
CLASS 2 SECTION XI CC>>4PLETE COMPONENTS INJECTION SYSTEM N     0 ASME                                   0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! Fl CATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** ------------------------------
EXAMINATION AREA                 CATGY   EXAM                         E 0 E       REMARKS NUMBER !DENT! Fl CATION                 ITEM NO METHOD     PROCEDURE         c MR        **CALIBRATION BLOCK**
-----------------
14-SJ-2124 ~REF. DWG. NO. B-52) 263716 14-SJ-2124-1                       C-F-1   PT         VS1SSISZZ0003Q . x           W.0.#931121035 TO PERFORM NOE.
---------------
VALVE TO ELBOW                  C5.11    UT45      VS1SSISZZ0014Q    x           LIMITATION: EXAM LIMITED TO 95X, DUE TO UT45T                        x           CONFIGURATION OF VALVE.
----------------------------------------
UT45TAN                      x
14-SJ-2124 263716 14-SJ-2124-1 VALVE TO ELBOW 263718 14-SJ-2124-HD-I LONGITUDINAL 263no 14-SJ-2124-1LD-O LONGITUDINAL l2-SJ-2152 263830 12-SJ-2152-5 ELBOW TO PIPE 263896 12-sJ-2152-36 PIPE TO PIPE 263898 12-SJ-2152-36PS-1 PIPE SUPPORT 263900 12-SJ-2152-36PS-2 PIPE SUPPORT DWG. NO. DWG. NO. "<* B-52) C-F-1 C5.11 C-F-1 C5.12 .C-F-1 B-54) C5.12 C-F-1 C5.11 C-F-1 C5.11 c-c C3.20 c-c C3.20 PT VS1SSISZZ0003Q . UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. x LIMITATION:
                                                                                            **14-SS-40-.438-79-SAM**
EXAM LIMITED TO 95X, DUE TO x CONFIGURATION OF VALVE. x **14-SS-40-.438-79-SAM**
263718 14-SJ-2124-HD-I                    C-F-1    PT        VS1SSISZZ0003Q    x           W.0.#931121035 TO PERFORM NOE. EXAMINE LONGITUDINAL                    C5.12    UT45      VS1SSISZZ0014Q    x           2.5T OF WELD LENGTH.
x W.0.#931121035 TO PERFORM NOE. EXAMINE x 2.5T OF WELD LENGTH. x x **14-SS-40-.438-79-SAM**
UT45T                        x UT45TAN                      x
x W.0.#931121035 TO PERFORM NOE. EXAMINE x 2.5T OF WELD LENGTH. x x **14-SS-40-.438-79-SAM**
                                                                                            **14-SS-40-.438-79-SAM**
x W.0.#931121035 TO PERFORM NOE. x -.;. EXAMINATION INCLUDED 2.5T OF THE x INTERSECTING LONGITUDINAL SEAM DOWN x STREAM. **12-SS-40-.377-31-SAM**
263no 14-SJ-2124-1LD-O                  .C-F-1    PT        VS1SSISZZ0003Q    x           W.0.#931121035 TO PERFORM NOE. EXAMINE LONGITUDINAL                    C5.12    UT45      VS1SSISZZ0014Q    x           2.5T OF WELD LENGTH.
x W.0.#931121035 TO PERFORM NOE. EXAM -x -2.5T OF LONG SEAM ON BOTH SIDES. THE x UT45 INDICATIONS ARE GEOMETRIC x REFLECTORS FROM THE INSIDE .SURFACE.  
UT45T                        x UT45TAN                      x
**12-SS-40-.377-31-SAM**
                                                                                            **14-SS-40-.438-79-SAM**
x --W.0.#931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NOE.
l2-SJ-2152  ~REF. DWG. NO. B-54) 263830 12-SJ-2152-5                      C-F-1    PT          VS1SSISZZ0003Q    x           W.0.#931121035 TO PERFORM NOE.
* DATE: 03/04/94 REVISION:
ELBOW TO PIPE                    C5.11    UT45        VS1SSISZZ0014Q    x -   .;.
0 .SAFETY INJECTION SYSTEM  
EXAMINATION INCLUDED 2.5T OF THE UT45T                        x           INTERSECTING LONGITUDINAL SEAM DOWN UT45TAN                      x           STREAM.
                                                                                            **12-SS-40-.377-31-SAM**
263896 12-sJ-2152-36                      C-F-1    PT          VS1SSISZZ0003Q    x           W.0.#931121035 TO PERFORM NOE. EXAM PIPE TO PIPE                    C5.11    UT45        VS1SSISZZ0014Q    - x -       2.5T OF LONG SEAM ON BOTH SIDES. THE UT45T                        x           UT45 INDICATIONS ARE GEOMETRIC UT45TAN                      x           REFLECTORS FROM THE INSIDE .SURFACE.
                                                                                              **12-SS-40-.377-31-SAM**
263898 12-SJ-2152-36PS-1                  c-c      PT          VS1SSISZZ0003Q    x   - -     W.0.#931121035 TO PERFORM NOE.
PIPE SUPPORT                    C3.20 263900 12-SJ-2152-36PS-2                  c-c      PT          VS1SSISZZ0003Q    X -     -   W.0.#931121035 TO PERFORM NOE.
PIPE SUPPORT                    C3.20
* DATE: 03/04/94                                 SALEM NUCLEAR PO'JER STATION UNIT 1                                PAGE: 32 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS
.SAFETY INJECTION SYSTEM N    0 ASME                                  0 G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO'JER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOO PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 12-SJ-2152 CREF. DWG. NO. B-54)
EXAMINATION AREA                 CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOO     PROCEDURE         C M R   **CALIBRATION BLOCK**
* 263904 12-SJ-2152-36PS-4 PENETRATION TO PIPE ** c-c C3.20 PT VS1SSISZZ0003Q X --W.0.#931121035 TO NOE. 32 
12-SJ-2152 CREF. DWG. NO. B-54) 263904   12-SJ-2152-36PS-4               c-c     PT         VS1SSISZZ0003Q     X -   - W.0.#931121035 TO PERFOR~ NOE.
, DATE: !>3/04/94 REVISION:
PENETRATION TO PIPE            C3.20
0 CONTAINMENT SPRAY  
 
, DATE: !>3/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    33 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS CONTAINMENT SPRAY N      0 ASME                                  0  G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION 8-CS-2114 (REF. DWG. NO. 355480 8-CS-2114-4 PIPE TO ELBOW 355500 8-CS-2114-5 ELBOW TO PIPE B-66) SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOO PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: C-F-1 PT VS1SSISZZ0003Q x W.0.# 931121035 TO PERFORM NOE. 33 THIS c5.11 UT45 VS1SSISZZ0014Q x EXAM REPLACES  
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOO      PROCEDURE        C M R    **CALIBRATION BLOCK**
8-CS-2114 (REF. DWG. NO. B-66) 355480 8-CS-2114-4                       C-F-1   PT         VS1SSISZZ0003Q   x         W.0.# 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW                  c5.11   UT45       VS1SSISZZ0014Q   x         EXAM REPLACES  


==SUMMARY==
==SUMMARY==
  #355400, DUE TO A UT45T x SUPPORT INTERFERENCE.
  #355400, DUE TO A UT45T                       x         SUPPORT INTERFERENCE.
UTO VS1SSISZZ0018Q x --**8-SS .140-24-SAM**
UTO       VS1SSISZZ0018Q   x - -
0 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NOE. THIS c5.11 UT45 VS1SSISZZ0014Q x --EXAM REPLACES  
                                                                                        **8-SS .140-24-SAM** 0 355500 8-CS-2114-5                      C-F-1   PT         VS1SSISZZ0003Q   x         W.O. #931121035 TO PERFORM NOE. THIS ELBOW TO PIPE                  c5.11   UT45       VS1SSISZZ0014Q   x - -   EXAM REPLACES  


==SUMMARY==
==SUMMARY==
  #355420, DUE TO A UT45T x SUPPORT INTERFERENCE.
  #355420, DUE TO A UT45T                       x         SUPPORT INTERFERENCE.
UT45TAN x --UTO VS1SSISZZ0018Q x **8-SS-10-.140-24-SAM**
UT45TAN                     x - -
, DATE:
UTO         VS1SSISZZ0018Q   x         **8-SS-10-.140-24-SAM**
SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 34 RE.VISION:
 
0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 2 SECTION XI COMPLETE CC>>4PONENTS CHEMICAL & VOLUME CONTROL N 0 ASHE 0 G T SEC. XI R E H  
, DATE: ~3/04/94                                            SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:     34 RE.VISION:     0                                   OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
CLASS 2 SECTION XI COMPLETE CC>>4PONENTS CHEMICAL & VOLUME CONTROL N     0 ASHE                                   0 G T SEC. XI                                 R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD *PROCEDURE c M R **CALIBRATION BLOCK** -------------------------------------
EXAMINATION AREA                           CATGY   EXAM                           E 0 E   REMARKS NUMBER IDENTIFICATION                               ITEM NO METHOD     *PROCEDURE         c M R   **CALIBRATION BLOCK**
----------
3*CV-2163 ~REF. DWG. NO. B-702 358300 3-CV-2163-6                                 C-F-1   PT           VS1SSISZZ0003Q   x       W.O. 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW                             C5.21   UT45         VS1SSISZZ0014Q   x       WELD REPLACES  
---------------
----------------------------------------
3*CV-2163 DWG. NO. B-702 358300 3-CV-2163-6 C-F-1 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q x WELD REPLACES  


==SUMMARY==
==SUMMARY==
  #365500, DUE TO UT45T x ALARA CONCERNS.
  #365500, DUE TO UT45T                         x       ALARA CONCERNS. THE WELD WAS LOCATED IN UT45TAN                       x - - THE SEAL WATER INJECTION FILTER ROC>>4.
THE WELD WAS LOCATED IN UT45TAN x --THE SEAL WATER INJECTION FILTER ROC>>4. UTOL VS1SSISZZ0018Q x **3-SS-160-.451-30-SAM**
UTOL         VS1SSISZZ0018Q   x       **3-SS-160-.451-30-SAM**
358320 3-CV-2163-7 C-F-1 PT VS1SSISZZ0003Q x --W.0 *. 931121035 TO PERFORM NOE. THIS ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q  
358320 3-CV-2163-7                                 C-F-1   PT           VS1SSISZZ0003Q   x - - W.0 *. 931121035 TO PERFORM NOE. THIS ELBOW TO PIPE                             C5.21   UT45         VS1SSISZZ0014Q   - x   - WELD REPLACES  
-x -WELD REPLACES  


==SUMMARY==
==SUMMARY==
  #365520, DUE TO UT45T x ALARA CONCERNS.
  #365520, DUE TO UT45T                         x       ALARA CONCERNS. THE WELD !'AS LOCATED IN UT45TAN                       x -   - THE SEAL WATER INJECTION FILTER ROC>>4.
THE WELD !'AS LOCATED IN UT45TAN x --THE SEAL WATER INJECTION FILTER ROC>>4. UTOL VS1SSISZZ0018Q x --THE UT45 INDICATION IS A GEOMETRIC REFLECTOR FROM THE WELD ROOT. **3-SS-160-.451-30-SAM**
UTOL         VS1SSISZZ0018Q   x -   - THE UT45 INDICATION IS A GEOMETRIC REFLECTOR FROM THE WELD ROOT.
358340 3-CV-2163-8 C-F-1 PT V.S1 SSI SZZ0003Q x --W.O. 931121035 TO PERFORM NDE* THIS PIPE TO ELBOW C5.21 UT45
                                                                                                    **3-SS-160-.451-30-SAM**
* VS1SSISZZ0014Q x WELD REPLACES  
358340 3-CV-2163-8                                   C-F-1   PT           V.S1 SSI SZZ0003Q x - - W.O. 931121035 TO PERFORM NDE* THIS PIPE TO ELBOW                             C5.21   UT45
* VS1SSISZZ0014Q   x       WELD REPLACES  


==SUMMARY==
==SUMMARY==
  #368720, DUE TO UT45T x ALARA CONCERNS.
  #368720, DUE TO UT45T                         x       ALARA CONCERNS. THE WELD WAS LOCATED IN UT45TAN                       x - - THE SEAL WATER INJECTION FILTER ROC>>4.
THE WELD WAS LOCATED IN UT45TAN x --THE SEAL WATER INJECTION FILTER ROC>>4. UTOL VS1SSISZZ0018Q x **3-SS-160-.451-30-SAM**
UTOL         VS1SSISZZ0018Q   x       **3-SS-160-.451-30-SAM**
3-CV-2160 DWG. NO. B-712 359100 3-CV-2160-5 C-F-1 PT VS1SSISZZ0003Q x
3-CV-2160 ~REF. DWG. NO. B-712 359100 3-CV-2160-5                                 C-F-1     PT         VS1SSISZZ0003Q   x       W~0.#931121035 TO PERFORM NOE. THE UT45 ELBOW TO PIPE                             C5.21   UT45         VS1SSISZZ0014Q     - x - AND UT60 INDICATIONS ARE GEOMETRIC UT45T                         x       REFLECTORS FROM THE WELD ROOT.
TO PERFORM NOE. THE UT45 ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q  
                          ~ .. "'"'..,                       UT45TAN                       x UT60                             x   **3-SS-160-.451-30-SAM**
-x -AND UT60 INDICATIONS ARE GEOMETRIC UT45T x REFLECTORS FROM THE WELD ROOT. .. "'"'.., UT45TAN x UT60 x **3-SS-160-.451-30-SAM**
UTOL         VS1SSISZZ0018Q     x 359120 3-CV-2160-6                                   C-F-1     PT         VS1SSISZZ0003Q   x       W.O. #931121035 TO PERFORM NDE. THIS
UTOL VS1SSISZZ0018Q x 359120 3-CV-2160-6 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NDE. THIS -PIPE TO PIPE C5.21 UT45 VS1SSISZZ0014Q  
        -PIPE TO PIPE                               C5.21   UT45         VS1SSISZZ0014Q     - x -   EXAM REPLACED  
-x -EXAM REPLACED  


==SUMMARY==
==SUMMARY==
  #359000, DUE TO A *:
  #359000, DUE TO A
UT45T x HIGH NUMBER OF EXAM LIMITATIONS PRESENT. UT45TAN x THE UT45 AND UT60 INDICATIONS ARE UT60 -x -GEOMETRIC REFLECTORS FROM THE WELD ROOT. UTOL VS1SSISZZ0018Q x **3-SS-160-.451-30-SAM**
                                        *: ..]--.~.          UT45T                         x       HIGH NUMBER OF EXAM LIMITATIONS PRESENT.
359140 3-CV-2160-7 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NDE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q x --EXAM REPLACED SuMMARY #359080, DUE TO A UT45T x SUPPORT INTERFERENCE.
UT45TAN                         x       THE UT45 AND UT60 INDICATIONS ARE UT60                           - x -   GEOMETRIC REFLECTORS FROM THE WELD ROOT.
UT45TAN x UT60 x **3-SS-160-.451-30-SAM**
UTOL         VS1SSISZZ0018Q     x       **3-SS-160-.451-30-SAM**
UTOL VS1SSISZZ0018Q x --
359140 3-CV-2160-7                                   C-F-1     PT         VS1SSISZZ0003Q     x       W.O. #931121035 TO PERFORM NDE. THIS PIPE TO ELBOW                             C5.21     UT45       VS1SSISZZ0014Q     x - -   EXAM REPLACED SuMMARY #359080, DUE TO A UT45T                         x       SUPPORT INTERFERENCE.
DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 35 ' REVISION:
UT45TAN                         x UT60                           x       **3-SS-160-.451-30-SAM**
0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) '  
UTOL         VS1SSISZZ0018Q     x - -
& VOLUME CONTROi. SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)  
 
:,,,:~:,:~~
DATE: 03/04/94                                   SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:     35
    ' REVISION:     0                           OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
        '                                     SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)
~CHEMICAL &    VOLUME CONTROi.
CLASS 2 SECTION XI COMPLETE COMPONENTS N      0 ASME                                  0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION  
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                     ITEM NO MET HOO    PROCEDURE        c MR      **CALIBRATION BLOCK**
-------------------------------------
3-CV-2160 ~REF. DWG. NO. B-722 359840 3-CV-2160-42                       C-F-1     PT         VS1SSISZZQ003Q   x         W.O. 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW                    C5.21    UT45      VS1SSISZZ0014Q    - x   - WELD REPLACED  
3-CV-2160 DWG. NO. B-722 359840 3-CV-2160-42 PIPE TO ELBOW 359860 3-CV-2160-43 ELBOW TO PIPE 359880 3-CV-2160-44 PIPE TO ELBOW 2-CV-2170 i aw&. NO. B-81l 366000 2-CV-2170-1 REDUCER TO ELBOW 2-CV-2167 CREF. DWG. NO: B-90> 366620 2-CV-2167-7 PIPE TO REDUCER 2-CV-2164 CREF. DWG. NO. B-90) 368300 2-CV-2164-1 REDUCER TO PIPE CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY ITEM NO C-F-1 C5.21 C-F-1 CS.21 C-F-1 C5.21 C-F-1 C5.30 C-F-1 C5.30 C-F-1 C5.30 EXAM MET HOO PROCEDURE
----------
---------------
PT VS1SSISZZQ003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN UTOL VS1SSISZZ0018Q PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN UTOL VS1SSl.SZZ0018Q PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN UTOL VS1SSISZZ0018Q PT VS1SSISZZ0003Q PT VS1SSISZZ0003Q PT VS1SSISZZ0003Q N 0 0 G T R E H E 0 E REMARKS c M R **CALIBRATION BLOCK** ----------------------------------------
x W.O. 931121035 TO PERFORM NOE. THIS -x -WELD REPLACED  


==SUMMARY==
==SUMMARY==
  #359800, DUE TO x ALARA CONCERNS.
  #359800, DUE TO UT45T                        x         ALARA CONCERNS. THEWELD WAS LOCATED UT45TAN                      x . -     INSIDE THE SEAL WATER INJECTION FILTER UTOL      VS1SSISZZ0018Q    x         ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE WELD ROOT.
THEWELD WAS LOCATED x . -INSIDE THE SEAL WATER INJECTION FILTER x ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE WELD ROOT. **3-SS-160-.451-30-SAM**
                                                                                                **3-SS-160-.451-30-SAM**
x --W.O. 931121035 TO PERFORM NOE. THIS -x -WELD REPLACED  
359860 3-CV-2160-43                      C-F-1    PT        VS1SSISZZ0003Q    x - -   W.O. 931121035 TO PERFORM NOE. THIS ELBOW TO PIPE                    CS.21    UT45      VS1SSISZZ0014Q    - x   - WELD REPLACED  


==SUMMARY==
==SUMMARY==
  #359820, DUE TO x ALARA CONCERNS.
  #359820, DUE TO UT45T                        x         ALARA CONCERNS. THE WELD WAS LOCATED UT45TAN                      x - -     INSIDE THE SEAL WATER INJECTION-FILTER UTOL      VS1SSl.SZZ0018Q  x         ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE COUNTERBORE.
THE WELD WAS LOCATED x --INSIDE THE SEAL WATER INJECTION-FILTER x ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE ':'.* COUNTERBORE.  
                                                                                                **3-SS-160-.451-30-SAM**
**3-SS-160-.451-30-SAM**
359880 3-CV-2160-44                      C-F-1    PT          VS1SSISZZ0003Q  x         W.O. 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW                    C5.21    UT45        VS1SSISZZ0014Q    - x   - WELD REPLACES  
x W.O. 931121035 TO PERFORM NOE. THIS -x -WELD REPLACES  


==SUMMARY==
==SUMMARY==
  #360000, DUE TO x ALARA CONCERNS.
  #360000, DUE TO UT45T                        x         ALARA CONCERNS. THE WELD WAS LOCATED UT45TAN                      x   - -   INSIDE THE SEAL WATER INJECTION FILTER UTOL        VS1SSISZZ0018Q  x   - -   ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE COUNTERBORE.
THE WELD WAS LOCATED x --INSIDE THE SEAL WATER INJECTION FILTER x --ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE COUNTERBORE.  
                                                                                                **3-SS-160-.451-30-SAM**
**3-SS-160-.451-30-SAM**
2-CV-2170  ~REF i aw&. NO. B-81l 366000 2-CV-2170-1                        C-F-1      PT        VS1SSISZZ0003Q    x - -   W.0.#931121035 TO PERFORM NOE.
x --W.0.#931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NOE. . ! 
REDUCER TO ELBOW                  C5.30 2-CV-2167 CREF. DWG. NO: B-90>
, DATE: ,03/04/94 REVISION:
366620 2-CV-2167-7                        C-F-1      PT        VS1SSISZZ0003Q    X -   - W.0.#931121035 TO PERFORM NOE.
0
PIPE TO REDUCER                  C5.30 2-CV-2164 CREF. DWG. NO. B-90) 368300 2-CV-2164-1                        C-F-1    PT        VS1SSISZZ0003Q    X - -     W.0.#931121035 TO PERFORM NOE.
& VOLUME CONTROL *
REDUCER TO PIPE                    C5.30
 
    , DATE: ,03/04/94                               SALEM NUCLEAR POWER STATION UNIT                                    PAGE: 36 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
~CHEMICAL SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS
              & VOLUME CONTROL N      0 ASME                                  0  G T SEC. XI                              R E    H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION 2-CV-2158 CREF. DWG. NO. B-90) 369620 2*CV-2158-7 PIPE TO REDUCER SALEM NUCLEAR POWER STATION UNIT OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: C-F-1 C5.30 PT VS1SSISZZ0003Q X -W.0.#931121035 TO PERFORM NOE. 36 
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD      PROCEDURE        C M R    **CALIBRATION BLOCK**
-----------, DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 37 R!iVISION:
2-CV-2158 CREF. DWG. NO. B-90) 369620 2*CV-2158-7                     C-F-1   PT         VS1SSISZZ0003Q   X ~  - W.0.#931121035 TO PERFORM NOE.
0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS AFETY INJECTION N 0 ASHE 0 G T SEC. XI R E H  
PIPE TO REDUCER                C5.30
 
                                                                                                                                        ~<.~~
, DATE: 03/04/94                                     SALEM NUCLEAR POWER STATION UNIT 1                                 PAGE:     37 R!iVISION:     0                           OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS AFETY INJECTION N     0 ASHE                                   0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** -------------------------------------
EXAMINATION AREA                   CATGY     EXAM                         E 0 E     REMARKS NUMBER IDENTIFICATION                       ITEM NO METHOD       PROCEDURE         c M R     **CALIBRATION BLOCK**
----------
4*SJ-2113 ~REF. DWG. NO. B-98l 383820 4-SJ-2113-3                         C-F-1     PT         VS1SSISZZ0003Q   x - -   w.o.#931121035 TO PERFORM NOE. THE UT45 FLANGE TO PIPE                     C5.21     UT45       VS1SSISZZ0014Q   - x -   INDICATION.IS A GEOMETRIC REFLECTOR FROM UT45T                       x         THE WELD ROOT.
---------------
UT45TAN                     x UTO       VS1SSISZZ0018Q   x - -   **4-SS-160-.533-28-SAM-R**
----------------------------------------
383940 4-SJ-2113-15                         C-F-1     PT         VS1SSISZZ0003Q   x         W.0.#931121035 TO PERFORM NOE.
4*SJ-2113 DWG. NO. B-98l 383820 4-SJ-2113-3 C-F-1 PT VS1SSISZZ0003Q x --w.o.#931121035 TO PERFORM NOE. THE UT45 FLANGE TO PIPE C5.21 UT45 VS1SSISZZ0014Q  
ELBOW TO PIPE                     C5.21     UT45       VS1SSISZZ0014Q   - x -     LIMITATION: EXAM LIMITED TO 73X, DUE TO UT45T                       x         THE PROXIMITY OF THE CONCRETE STRUCTURE.
-x -INDICATION.IS A GEOMETRIC REFLECTOR FROM UT45T x THE WELD ROOT. UT45TAN x UTO VS1SSISZZ0018Q x --**4-SS-160-.533-28-SAM-R**
UT45TAN                     x - "     THE UT45 INDICATION IS A G~OMETRIC UTO       VS1SSISZZ0018Q   x - -     INDICATION FROM THE WELD ROOT.
383940 4-SJ-2113-15 C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q  
                                                                                              **4-SS-160-.533-28-SAM-R**
-x -LIMITATION:
4-SJ-2113 ~REF. DWG. NO. B-100) 384200 4-SJ-2113-29                         C-F-1     PT         VS1SSISZZ0003Q   x         W.O. 931121035 TO PERFORM NDE. THIS PIPE TO ELBOW                     C5.21     UT45       VS1SSISZZ0014Q   - x-   . WELD REPLACED  
EXAM LIMITED TO 73X, DUE TO UT45T x THE PROXIMITY OF THE CONCRETE STRUCTURE.
UT45TAN x -" THE UT45 INDICATION IS A UTO VS1SSISZZ0018Q x --INDICATION FROM THE WELD ROOT. **4-SS-160-.533-28-SAM-R**
4-SJ-2113 DWG. NO. B-100) 384200 4-SJ-2113-29 C-F-1 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NDE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q  
-x-. WELD REPLACED  


==SUMMARY==
==SUMMARY==
  #384280, DUE TO UT45T x HANGER INTERFERENCE.
  #384280, DUE TO UT45T                       x         HANGER INTERFERENCE. THE UT45 UT45TAN                     x -. -     INDICATIONS ARE GEOMETRIC REFLECTORS UTOL.     VS1SSISZZ0018Q   x         FROM THE WELD ROOT.
THE UT45 UT45TAN x -. -INDICATIONS ARE GEOMETRIC REFLECTORS UTOL. VS1SSISZZ0018Q x FROM THE WELD ROOT. **4-SS-160-.533-28-SAM-R**
                                                                                              **4-SS-160-.533-28-SAM-R**
384220 4-SJ-2113-30 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NDE. THIS ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q x WELD REPLACES  
384220 4-SJ-2113-30                         C~F-1    PT         VS1SSISZZ0003Q   x         W.O. 931121035 TO PERFORM NDE. THIS ELBOW TO PIPE                     C5.21     UT45       VS1SSISZZ0014Q   x         WELD REPLACES  


==SUMMARY==
==SUMMARY==
  #384300, DUE TO UT45T x HANGER INTERFERENCE.  
  #384300, DUE TO UT45T                       x         HANGER INTERFERENCE.
-UT45TAN x .. UTO VS1SSISZZ0018Q x **4-SS-160-.533-28-SAM-R**
                                                    - UT45TAN                     x
384260 4-SJ-2113-32 C-F-1 PT VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NDE. THE UT45 PIPE TO FLANGE C5.21 UT45 VS1SSISZZ0014Q  
                          ~ .~~..                     UTO       VS1SSISZZ0018Q   x         **4-SS-160-.533-28-SAM-R**
-x -INDICATION IS A GEOMETRIC REFLECTOR FROM UT45T x THE WELD ROOT. UT45TAN x UTOL VS1SSISZZ0018Q x --**4-SS-160-.533-28-SAM-R**  
384260 4-SJ-2113-32                         C-F-1     PT         VS1SSISZZ0003Q   x   - -   W.0.#931121035 TO PERFORM NDE. THE UT45 PIPE TO FLANGE                     C5.21     UT45       VS1SSISZZ0014Q     - x -     INDICATION IS A GEOMETRIC REFLECTOR FROM UT45T                       x         THE WELD ROOT.
---2-SJ-2126 CREF. DWG. NO; B-104) 386600 2-SJ-2126-6R C-F-1 PT VHSSSSPZZ0204Q x --PSI BASELINE EXAMINATION WAS PERFORMED, REDUCER TO ORIFICE C5.30 DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930628119, ACT #5)
UT45TAN                     x UTOL       VS1SSISZZ0018Q   x   - -   **4-SS-160-.533-28-SAM-R**
'DATE: 03/04/94 REVISION:
2-SJ-2126 CREF. DWG. NO; B-104) 386600 2-SJ-2126-6R                         C-F-1     PT         VHSSSSPZZ0204Q   x   - -   PSI BASELINE EXAMINATION WAS PERFORMED, REDUCER TO ORIFICE                 C5.30                                             DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930628119, ACT #5)
0 INJECTION
 
  'DATE: 03/04/94                                 SALEM NUCLEAR PO\IER STATION UNIT 1                                PAGE:    38 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
~AFETY SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS INJECTION N    0 ASME                                  0 G T SEC. XI                                R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\IER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 38 2-SJ-2126 (REF. DWG. NO. B-104) 386620 2-SJ-2126-7R ORIFICE TO REDUCER 2-SJ-2123 (REF. DWG. NO. B-105) 387100 2-SJ-2123-6R REDUCER TO ORIFICE 387120 2-SJ-2123-7R ORIFICE TO REDUCER
EXAMINATION AREA                 CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R   **CALIBRATION BLOCK**
* C5.30 C-F-1 C5.30 C5.30 PT VHSSSSPZZ0204Q PT VHSSSSPZZ0204Q PT VHSSSSPZZ0204Q X --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930628119, ACT #5) X --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5) . X --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5)
2-SJ-2126 (REF. DWG. NO. B-104) 386620 2-SJ-2126-7R                     C~F-1   PT         VHSSSSPZZ0204Q     X -   - PSI BASELINE EXAMINATION WAS PERFORMED, ORIFICE TO REDUCER              C5.30                                          DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930628119, ACT #5) 2-SJ-2123 (REF. DWG. NO. B-105) 387100 2-SJ-2123-6R                      C-F-1    PT        VHSSSSPZZ0204Q    X -   - PSI BASELINE EXAMINATION WAS PERFORMED, REDUCER TO ORIFICE              C5.30                                          DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5)                 .
' DATE: '03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: REVISION:
387120 2-SJ-2123-7R                      C-F~1    PT        VHSSSSPZZ0204Q    X -   - PSI BASELINE EXAMINATION WAS PERFORMED, ORIFICE TO REDUCER              C5.30                                          DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5)
0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS AUXILIARY FEEDWATER SYSTEM ASME SEC. XI  
 
' DATE: '03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE: 39 REVISION:     0                         OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS AUXILIARY FEEDWATER SYSTEM N      0 ASME                                   0 G T SEC. XI                               R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD AF1053 CREF. DWG. NO. AF-1,3A 01) 500145 14AFWG-002 GUIDE 500150 14AFWG-003 GUIDE F-C F3.10 F-C F3.10 AF1063 CREF. DWG. NO. AF-1-3A 01) 500390 13AFWA-046 ANCHOR D-A 01 .20 AF1075 CREF. DWG. NO. AF-1-3A 01) 500630 12AFWG-002 GUIDE AF1089 5oono 11AFWS-050 SUPPORT 500785 11AFWG-050A GUIDE DWG. F-C F3.10 NO. AF-1-3A 01l F-C F3.10
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE        C M R    **CALIBRATION BLOCK**
.. F-C F3.10 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** x --PRESERVICE PER 1EC-3226-01, CJP# PS-93-004.
AF1053 CREF. DWG. NO. AF-1,3A 01) 500145 14AFWG-002                     F-C       VT-3      S1SSISZZ0020Q    x  - -   PRESERVICE PER 1EC-3226-01, W.0.#
x --PRESERVICE PER 1EC-3226-01, 930203123, CJP# PS-93-004.
GUIDE                           F3.10                                           930203~23,  CJP# PS-93-004.
W.0.# W.0.# X --PRESERVICE PER 1EC-3226-01, W.0.# 930203123, CJP# PS-93-004. X --PRESERVICE PER 1EC-3226-01, W.0.# 930203123, CJP# PS-93-004.
500150 14AFWG-003                      F-C       VT-3       S1SSISZZ0020Q     x - -   PRESERVICE PER 1EC-3226-01, W.0.#
x --PRESERVICE PER 1EC-3226-01, W.0.# 930203123, CJP# PS-93-004.
GUIDE                          F3.10                                            930203123, CJP# PS-93-004.
x --PRESERVICE PER 1EC-3226-01, W.0.# 930203123, CJP# PS-93-004.
AF1063 CREF. DWG. NO. AF-1-3A 01) 500390  13AFWA-046                      D-A      VT-3        S1SSISZZ0020Q    X -     - PRESERVICE PER 1EC-3226-01, W.0.#
39
ANCHOR                          01 .20                                          930203123, CJP# PS-93-004.
* DATE: *03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 40 REVISION:
AF1075 CREF. DWG. NO. AF-1-3A 01) 500630 12AFWG-002                        F-C      VT-3        S1SSISZZ0020Q    X -     - PRESERVICE PER 1EC-3226-01, W.0.#
0 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS COMPONENT COOLING SYSTEM ASME SEC. XI  
GUIDE                            F3.10                                          930203123, CJP# PS-93-004.
AF1089  ~REF. DWG. NO. AF-1-3A 01l 5oono  11AFWS-050                      F-C      VT-3        S1SSISZZ0020Q    x   - -   PRESERVICE PER 1EC-3226-01, W.0.#
SUPPORT                          F3.10                                          930203123, CJP# PS-93-004.
                          ""'~ ..
500785  11AFWG-050A                      F-C      VT-3        S1SSISZZ0020Q    x - -   PRESERVICE PER 1EC-3226-01, W.0.#
GUIDE                            F3.10                                            930203123, CJP# PS-93-004.
* DATE: *03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:   40 REVISION:     0                         OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS COMPONENT COOLING SYSTEM N      0 ASME                                   0  G T SEC. XI                               R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD CC1010 (REF. DWG. NO. CC-1-2A 02) 501255 1A-CCH*404 HANGER CC1022 CREF. DWG. NO. CC-1-2A 02) 501355 1A-CCH-405 HANGER CC1051 CREF. DWG. NO. CC-1-2A 02) 501380 1A-CCH-402 HANGER 501390 1A*CCH-403 HANGER F-C F3.10 CC1066 CREF. DWG. NO. CC-1-2A 02) 501425 1A-CCH-406 HANGER 501430 1A-CCH-082 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** THIS SUPPORT (SUM.# 501255) WAS DELETED PER EC-3255/PS-93-050/930610082. .THIS SUPPORT (SUM.# 501355) WAS DELETED PER 1EC-3255/PS-93-050/930610082.
EXAMINATION AREA               CATGY    EXAM                        E 0 E      REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD       PROCEDURE        C M R    **CALIBRATION BLOCK**
THIS SUPPORT (SUM.# 501380) WAS DELETED PER 1EC-3255/PS-93-050/930610082.
CC1010 (REF. DWG. NO. CC-1-2A 02) 501255 1A-CCH*404                               VT-3                                    THIS SUPPORT (SUM.# 501255) WAS DELETED HANGER                                                                           PER EC-3255/PS-93-050/930610082.
THIS SUPPORT (SUM.# 501390) WAS DELETED PER 1EC-3255/PS-93-050/930610082.
CC1022 CREF. DWG. NO. CC-1-2A 02) 501355  1A-CCH-405                              VT-3                                   .THIS SUPPORT (SUM.# 501355) WAS DELETED HANGER                                                                          PER 1EC-3255/PS-93-050/930610082.
THIS SUPPORT (SUM.# 501425) WAS DELETED PER 1EC-3255/PS-93-050/930610082. X --PRESERVICE PER 1EC-3255-1, CJP# PS-93-50 & W.0.# 930610082.
CC1051 CREF. DWG. NO. CC-1-2A 02) 501380 1A-CCH-402                                VT-3                                    THIS SUPPORT (SUM.# 501380) WAS DELETED HANGER                                                                          PER 1EC-3255/PS-93-050/930610082.
' DATE: *03/04/94 REVISION:
501390 1A*CCH-403                      F-C      VT-3                                    THIS SUPPORT (SUM.# 501390) WAS DELETED HANGER                          F3.10                                            PER 1EC-3255/PS-93-050/930610082.
0 CONTAINMENT SPRAY SYSTEM  
CC1066 CREF. DWG. NO. CC-1-2A 02) 501425  1A-CCH-406                              VT-3                                    THIS SUPPORT (SUM.# 501425) WAS DELETED HANGER                                                                          PER 1EC-3255/PS-93-050/930610082.
501430 1A-CCH-082                                VT-3        S1SSISZZ0020Q    X -     - PRESERVICE PER 1EC-3255-1, CJP# PS-93-50 HAN~ER                                                                          & W.0.# 930610082.
 
' DATE: *03/04/94                               SALEH NUCLEAR POWER STATION UNIT 1                                PAGE:    41 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS CONTAINMENT SPRAY SYSTEM N      0 ASHE                                  0 G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEH NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASHE SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 41 SJ1094 CREF. DWG. NO. CS-1-1A 01) 502910 1A-CSS-158 SUPPORT F-C F3.10 VT-3 S1SSISZZ0020Q X " -W.0.#931121035 TO PERFORM NOE. RE-EXAM FROM 1RF0#10.
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
' DATE: .03/04/94 REVISION:
SJ1094 CREF. DWG. NO. CS-1-1A 01) 502910 1A-CSS-158                     F-C       VT-3       S1SSISZZ0020Q     X " -     W.0.#931121035 TO PERFORM NOE. RE-EXAM SUPPORT                        F3.10                                            FROM 1RF0#10.
0 CHEMICAL AND VOLUME CONTROL SYSTEM  
 
' DATE: .03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                          PAGE:  42 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS CHEMICAL AND VOLUME CONTROL SYSTEM N  0 ASME                                            0 G T SEC. XI                                        R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION
EXAMINATION AREA                 CATGY   EXAM                                   E 0 E REMARKS NUMBER IDENTIFICATION                    ITEM NO METHOO .               PROCEDURE       c M R **CALIBRATION BLOCK**
------------------------------
CV1161 ~REF. DIJG. NO. CV-1-2B 02l 503235 1A-CVCS-383                     F-C     VT-3                   S1SSISZZ002QQ   - - x IJ.0.#931121035 TO PERFORM NOE.
SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H CATGY EXAM E 0 E REMARKS ITEM NO METHOO . PROCEDURE c M R **CALIBRATION BLOCK** PAGE: 42 ......................
SUPPORT                          F3.10                                                  RESCHEDULED FROM 1RF0#10. NEED TO REMOVE CONCRETE BLOCK FOR EXAM. THE INSPECTION FOUND BORON ON THE SUPPORT.
---------------
IJ.O. #931027158 CLEANED THE BORON OFF.
----------------------------------------
A RE-EXAM IJAS SCHED. FOR S1RF0#12 (ACCESSIBILITY PROBLEMS).
CV1161 DIJG. NO. CV-1-2B 02l 503235 1A-CVCS-383 SUPPORT RC1077 503945 1C-CVCH-326 HANGER 503970 1C-CVCG-276 GUIDE DIJG. NO. F-C VT-3 S1SSISZZ002QQ F3.10 CV-1-4B 01l VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q --x IJ.0.#931121035 TO PERFORM NOE. RESCHEDULED FROM 1RF0#10. NEED TO REMOVE CONCRETE BLOCK FOR EXAM. THE INSPECTION FOUND BORON ON THE SUPPORT. IJ.O. #931027158 CLEANED THE BORON OFF. A RE-EXAM IJAS SCHED. FOR S1RF0#12 (ACCESSIBILITY PROBLEMS).
RC1077  ~REF. DIJG. NO. CV-1-4B 01l 503945  1C-CVCH-326                              VT-3                  S1SSISZZ0020Q  x - - THIS SUPPORT IJAS MODIFIED PER HANGER                                                                                  1EC-3167/PS-92-40/920805116.
x --THIS SUPPORT IJAS MODIFIED PER 1EC-3167/PS-92-40/920805116. X --.THIS SUPPORT IJAS MODIFIED PER 1EC-3167/PS-92-40/920805116.
503970 1C-CVCG-276                                VT-3                  S1SSISZZ0020Q  X - - .THIS SUPPORT IJAS MODIFIED PER GUIDE                                                                                    1EC-3167/PS-92-40/920805116.
' DATE: '03/04/94 REVISION:
 
0 .MAIN STEAM SYSTEM  
  ' DATE: '03/04/94                             SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    43 REVISION:     0                      OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS
.MAIN STEAM SYSTEM N      0 ASME                                  0 G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 43 MS1003 CREF. DWG. NO. MS-1-2 04) 504315 1P-MS-VS006 1 LUG MS1112 CREF. 504535 1P-MSH-122T HANGER MS1269 CREF. 504710 1P-MSH-124T HANGER ** DWG. MS-1-2 DWG. NO. MS-1-2 F-C F3.10 04) 04) VT-3 S1SSISZZ0020Q VT-3/4 S1SSISZZ0020Q VT-3/4 S1SSISZZ0020Q X --W.0.#931121035 TO PERFORM NDE. RE-EXAM FROM 1RF0#10. x --PRE-SERVICE INSPECTION WAS PERFORMED UNDER W.O. #931121035  
EXAMINATION AREA             CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
& 931002088, DUE TO THE DISASSEMBLY OF THE '2MS167 VALVE ACTUATOR.
MS1003 CREF. DWG. NO. MS-1-2 04) 504315 1P-MS-VS006                   F-C     VT-3       S1SSISZZ0020Q     X -   - W.0.#931121035 TO PERFORM NDE. RE-EXAM 1 LUG                        F3.10                                          FROM 1RF0#10.
ADDITIONAL STEEL PLATE AND GOUGE MARKS IN THE SUPPORT CHANNELS WERE FOUND TO BE ACCEPTABLE PER NON DR. x --PRE-SERVICE INSPECTION WAS PERFORMED UNDER W.O. #931121035  
MS1112 CREF. DWG. NO~ MS-1-2 04) 504535 1P-MSH-122T                            VT-3/4    S1SSISZZ0020Q    x - -   PRE-SERVICE INSPECTION WAS PERFORMED HANGER                                                                        UNDER W.O. #931121035 & 931002088, DUE TO THE DISASSEMBLY OF THE '2MS167 VALVE ACTUATOR. ADDITIONAL STEEL PLATE AND GOUGE MARKS IN THE SUPPORT CHANNELS WERE FOUND TO BE ACCEPTABLE PER NON DR.
& 931002089, DUE TO THE DISASSEMBLY OF THE 14MS167 VALVE ACTUATOR.
MS1269 CREF. DWG. NO. MS-1-2 04) 504710 1P-MSH-124T                            VT-3/4    S1SSISZZ0020Q    x - -   PRE-SERVICE INSPECTION WAS PERFORMED HANGER                                                                        UNDER W.O. #931121035 &931002089, DUE TO THE DISASSEMBLY OF THE 14MS167 VALVE ACTUATOR. NO MODIFICATIONS WERE PERFORMED ON THIS HANGER. CSEE NON DR, FOR ADDITIONAL INFORMATION)
NO MODIFICATIONS WERE PERFORMED ON THIS HANGER. CSEE NON DR, FOR ADDITIONAL INFORMATION)
 
, DATE: 03/04/94 REVISION:
  , DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                    PAGE:    44 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
0 PRESSURIZING SYSTEM  
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI CIJ4PLETE CIJ4PONENTS PRESSURIZING SYSTEM N      0 ASME                                    0 G T SEC. XI                                  R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION  
EXAMINATION AREA               CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE           C M R     **CALIBRATION BLOCK**
----------
RC1276 (REF. DWG. NO. RC-1-1A 01>
SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI CIJ4PLETE CIJ4PONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 44 RC1276 (REF. DWG. NO. RC-1-1A 01> 505065 1C-PSH-001 HANGER 505066 R-239776-1 505067 R-239776-2 505068 R-239776-3 05069 R-239776-4 505070 1C-PSH-002 HANGER 505071 R-239776-5 505072 R-239776-6 505073 R-239776-7
505065 1C-PSH-001                       F-C       VT-3       S1SSISZZ0020Q       X - -     W.0.#931121035 TO PERFORM NOE. EXAMINED HANGER                        F3.10                                              PER NRC BULLETIN 88-11.
** F-C VT-3 F3.10 A-E VT-3 NB88-11 A-E VT-3 NB88-11 A-E VT-3 NB88-11 A-E VT-3 NB88-11 F-C VT-3 F3.10 A-E VT-3 NB88-11 A-E VT-3 NB88-11 A-E VT-3 NB88-11 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED.
505066 R-239776-1                      A-E      VT-3      S1SSISZZ0020Q      X -   - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11                                            PER NRC BULLETIN 88-11.
PER NRC BULLETIN 88-1.1. X --W.0.#931121035 TO .PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11.
505067 R-239776-2                      A-E      VT-3      S1SSISZZ0020Q      X -   - W.0.#931121035 TO PERFORM NOE. EXAMINED.
'DATE: 03/04/94 REVISION:
NB88-11                                            PER NRC BULLETIN 88-1.1.
0 SYSTEM
505068 R-239776-3                      A-E      VT-3      S1SSISZZ0020Q        X -   - W.0.#931121035 TO .PERFORM NOE. EXAMINED NB88-11                                            PER NRC BULLETIN 88-11.
05069 R-239776-4                      A-E      VT-3        S1SSISZZ0020Q      X -   - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11                                            PER NRC BULLETIN 88-11.
505070 1C-PSH-002                        F-C      VT-3        S1SSISZZ0020Q      X -   - W.0.#931121035 TO PERFORM NOE. EXAMINED HANGER                          F3.10                                              PER NRC BULLETIN 88-11.
505071  R-239776-5                    A-E      VT-3        S1SSISZZ0020Q      X -   - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11                                            PER NRC BULLETIN 88-11.
505072 R-239776-6                      A-E      VT-3        S1SSISZZ0020Q      X -   - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11                                            P~R NRC BULLETIN 88-11.
505073 R-239776-7                      A-E      VT-3        S1SSISZZ0020Q      X -   - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11                                            PER NRC BULLETIN 88-11.
 
    'DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    45 REVISION:     0                        OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0)
~PRESSURIZING SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS SYSTEM N      0 ASME                                  0  G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 45 RC1276 (REF. DWG. NO. RC-1-1A 01> 505075 1C-PSH*003 HANGER F*C F3.10 VT-3 S1SSISZZ0020Q X *
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
* W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88*11.
RC1276 (REF. DWG. NO. RC-1-1A 01>
'DATE: 03/04/94 REVISION:
505075   1C-PSH*003                     F*C     VT-3       S1SSISZZ0020Q     X *
0 PRESSURIZER RELIEF SYSTEM  
* W.0.#931121035 TO PERFORM NOE. EXAMINED HANGER                        F3.10                                          PER NRC BULLETIN 88*11.
 
  'DATE: 03/04/94                               SALEM NUCLEAR PO\JER STATION UNIT 1                                PAGE: 46 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS PRESSURIZER RELIEF SYSTEM N    0 ASME                                  0  G T SEC. XI                                R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\JER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: RC1287 (REF. DWG. NO. RC-1-2B 01) 505300 1C-PRH-177 HANGER
EXAMINATION AREA               CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD     PROCEDURE         C M R   **CALIBRATION BLOCK**
* VT-3 S1SSISZZ0020Q X --THIS SUPPORT WAS MODIFIED PER 1EC-3168/PS-92-41/920805117.
RC1287 (REF. DWG. NO. RC-1-2B 01) 505300 1C-PRH-177                             VT-3       S1SSISZZ0020Q     X -   - THIS SUPPORT WAS MODIFIED PER HANGER                                                                        1EC-3168/PS-92-41/920805117.
46 
 
' DATE: '03/04/94 REVISION:
    ' DATE: '03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE: 47 REVISION:     0                      . CXJTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
0 .RESIDUAL HEAT REMOVAL SYSTEM  
SECOND INTERVAL, SECOND PERIOD, SECOND CXJTAGE C93RF)
CLASS 2 SECTION XI COMPLETE COMPONENTS
.RESIDUAL HEAT REMOVAL SYSTEM N      0 ASME                                    0  G T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 . CXJTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND CXJTAGE C93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: RH1013 CREF. DWG. NO. RH-1-1A 02) 505755 1A-RHRA-PS30 ANCHOR ** F-C F3.10 VT-3 S1SSISZZ0020Q X --W.0.#931121035 TO PERFORM NOE. 47 
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE         C M R     **CALIBRATION BLOCK**
' DATE: 03/04/94 REVISION:
RH1013 CREF. DWG. NO. RH-1-1A 02) 505755 1A-RHRA-PS30                   F-C       VT-3       S1SSISZZ0020Q     X -   - W.0.#931121035 TO PERFORM NOE.
0 SAFETY INJECTION SYSTEM  
ANCHOR                          F3.10
 
' DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                PAGE:    48 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N      0 ASME                                    O G T SEC *. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC *. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 O G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 48 RC1023 CREF. DWG. NO. RH*1-3F 01) 506195 1C*11SIS*133 SUPPORT F-C F3.10 VT*3 S1SSISZZ0020Q X -* W.0.#931121035 TO PERFORM NOE. RE*EXAM FROM 1RF0#10.
EXAMINATION AREA               CATGY      EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE         C M R   **CALIBRATION BLOCK**
' DATE: ,D3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 49 REVISION:
RC1023 CREF. DWG. NO. RH*1-3F 01) 506195   1C*11SIS*133                   F-C       VT*3       S1SSISZZ0020Q     X -
0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM ASME SEC. XI  
* W.0.#931121035 TO PERFORM NOE. RE*EXAM SUPPORT                        F3.10                                            FROM 1RF0#10.
 
' DATE: ,D3/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:   49 REVISION:     0                       OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N      0 ASME                                 0  G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOO SW1136 CREF. DWG. NO. SW-1-7K 01> 508920 1MSWPG-049A GUIDE D-B D2.20 SW1169 CREF. DWG. NO. SW-1-3B 01> 508990 A1-SWG-364 GUIDE 508995 A1-SWA-354 ANCHOR 509000 A1-SWG-366 GUIDE 509005 A1-SWG-367 GUIDE SW1176 CREF. DWG. NO. SW-1-38 01) 509010 A1-SWA-345 ANCHOR 509015 A1-SWG-344 GUIDE 509020 A1-SWG-316 GUIDE VT-3 VT-3 VT-3. VT-3 VT-3 VT-3 VT-3 VT*3 PROCEDURE S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS GUIDE WAS DISSASSEMBLED AND A NEW WELD WAS ADDED TO FACILITATE THE REMOVAL OF PIPE SPOOL RD-1-SW-75, .UNDER CJP #S-92-332 AND W.O. #920512075  
EXAMINATION AREA               CATGY    EXAM                        E 0 E      REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOO     PROCEDURE        C M R      **CALIBRATION BLOCK**
*. x --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/9304220!3.
SW1136 CREF. DWG. NO. SW-1-7K 01>
x --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
508920   1MSWPG-049A                   D-B     VT-3       S1SSISZZ002QQ     X -   -   THIS GUIDE WAS DISSASSEMBLED AND A NEW GUIDE                          D2.20                                            WELD WAS ADDED TO FACILITATE THE REMOVAL OF PIPE SPOOL RD-1-SW-75, .UNDER CJP
X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
                                                                                          #S-92-332 AND W.O. #920512075 *.
X --THIS SUPPORT WAS MODIFIED*PER . 1EC-3149/PS-93-030/930422073.
SW1169 CREF. DWG. NO. SW-1-3B 01>
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
508990 A1-SWG-364 GUIDE VT-3      S1SSISZZ0020Q    x - -     THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/9304220!3.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
508995 A1-SWA-354                                VT-3.      S1SSISZZ0020Q    x - -     THIS SUPPORT WAS MOOIFIED PER ANCHOR                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509000 A1-SWG-366                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
I DATE: g3/04/94 REVISION:
509005 A1-SWG-367                                VT-3      S1SSISZZ002QQ    X -   -   THIS SUPPORT WAS MODIFIED*PER GUIDE                                                                          . 1EC-3149/PS-93-030/930422073.
0 WATER SYSTEM  
SW1176 CREF. DWG. NO. SW-1-38 01) 509010 A1-SWA-345                                VT-3      S1SSISZZ002QQ    X -   -   THIS SUPPORT WAS MODIFIED PER ANCHOR                                                                          1EC-3149/PS-93-030/930422073.
509015 A1-SWG-344                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
509020 A1-SWG-316                                VT*3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
 
I DATE: g3/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE: so REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS_(S1RF0#11, REV.0)"
~SERVICE SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N      O ASME                                  0 G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS_(S1RF0#11, REV.0)" SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1176 (REF. DWG. NO. SW-1-3B 01) 509025 A1*SWA-315 ANCHOR 509030 A1-SWH-314 HANGER 509035 A1-SWG-313 GUIDE 509040 A1-SWG-324 GUIDE 09045 A1*SWH-323 HANGER 509050 A1-SWA-WS08 ANCHOR D-B D2.20 D-B D2.20 SW1181 CREF. DWG. NO. SW-1-3B 01) 509055 A1-SWG-378 GUIDE 509060 A1-SWA*358 ANCHOR 509065 A1-SWG-377 GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q x THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS*93-030/930422073.
SW1176 (REF. DWG. NO. SW-1-3B 01) 509025 A1*SWA-315                       D-B     VT-3       S1SSISZZ0020Q     x         THIS SUPPORT WAS MODIFIED PER ANCHOR                        D2.20                                            1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509030 A1-SWH-314                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3149/PS*93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509035 A1-SWG-313                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93*030/930422073.
509040 A1-SWG-324                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
09045 A1*SWH-323                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3149/PS-93*030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS*93-030/930422073.
509050 A1-SWA-WS08                      D-B                  S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER ANCHOR                        D2.20                                            1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
SW1181 CREF. DWG. NO. SW-1-3B 01) 509055 A1-SWG-378                                VT-3      S1SSISZZ0020Q    X -     - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS*93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509060 A1-SWA*358                                VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER ANCHOR                                                                          1EC-3149/PS-93-030/930422073.
so 
509065 A1-SWG-377                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
'DATE: 93/04/94 REVISION:
 
0 SERVICE WATER SYSTEM  
'DATE: 93/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:  51 REVISION:     0                      OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N      0 ASME                                  0 G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1181 CREF. DWG. NO. SW-1-3B 012 509070 A1-SWG-376 GUIDE VT-3 S1SSISZZ002QQ X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
51 509075 A1-SWG-348 GUIDE VT-3 THIS SUPPORT (SUM.# 509075) WAS DELETED PER 1EC-3149/PS-93-030/930422073.
SW1181 CREF. DWG. NO. SW-1-3B 012 509070 A1-SWG-376                               VT-3       S1SSISZZ002QQ     X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
509080 A1-SWG-347 GUIDE 509085 A1-SWG-346 GUIDE SW1185 CREF. DWG. NO. SW-1-3B 012 509090 A1-SWS-369 SUPPORT 509095 A1-SWG-368 GUIDE 509100 A1-SWA-356 ANCHOR 509105 A1-SWG-370 GUIDE SW1191 CREF. DWG. NO. SW-1-1B 022 509110 P1-SWA-WS12 ANCHOR D-B D2.20 VT-3 VT-3 VT-3 VT-3 VT-3 vr-3 VT-3 S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ002QQ X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509075 A1-SWG-348                               VT-3                                   THIS SUPPORT (SUM.# 509075) WAS DELETED GUIDE                                                                          PER 1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509080 A1-SWG-347                               VT-3       S1SSISZZ0020Q     X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509085 A1-SWG-346                                VT-3      S1SSISZZ002QQ    X -     - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
SW1185 CREF. DWG. NO. SW-1-3B 012 509090 A1-SWS-369                                VT-3        S1SSISZZ002QQ    X -     - THIS SUPPORT WAS MODIFIED PER SUPPORT                                                                        1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. , X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509095 A1-SWG-368                                VT-3      S1SSISZZ002QQ    X -     - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --PRESERVICE PER 1EC-3150-1/PS-93-006/930615162.
509100 A1-SWA-356                                VT-3      S1SSISZZ002QQ    X -   - THIS SUPPORT WAS MODIFIED PER ANCHOR                                                                          1EC-3149/PS-93-030/930422073.
'DATE: 03/04/94 REVISION:
509105 A1-SWG-370                                vr-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
0 WATER SYSTEM  
SW1191 CREF. DWG. NO. SW-1-1B 022 509110 P1-SWA-WS12                      D-B      VT-3      S1SSISZZ002QQ    X -   - PRESERVICE PER ANCHOR                        D2.20                                            1EC-3150-1/PS-93-006/930615162.
 
    'DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                    PAGE:  52 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~SERVICE    WATER SYSTEM CLASS 3 SECTION XI COMPLETE COMPONENTS N      0 ASME                                  0  G  T SEC. XI                                R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 52 SW1197 CREF. DWG. NO. SW-1-1A 02) 509160 C-13SWH-2 HANGER 509165 C-13SWG-3C GUIDE SW1220 CREF. DWG. NO. SW-1-1A 02) 509270 C-12SWH-1 HANGER 509275 C-11SWG-3B GUIDE .,,.,,., C-11SWG-4B GUIDE 509285 C-11SWG-5B GUIDE 509290 C-12SWG-3A GUIDE 509295 C-12SWG-4 ANCHOR 509300 C-11SWG-9B GUIDE VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOO.) PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
SW1197 CREF. DWG. NO. SW-1-1A 02) 509160 C-13SWH-2                                 VT-3       S1SSISZZ0020Q     X -   - THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3054-2/PS-93-021/920115113.
THIS SUPPORT (SUM.# 509280) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOO.) PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS.MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
509165 C-13SWG-3C                                VT-3      S1SSISZZ0020Q    X -   - PRESERVICE (NO MOO.) PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
THIS SUPPORT (SUM.# 509300) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.
SW1220 CREF. DWG. NO. SW-1-1A 02) 509270 C-12SWH-1                                VT-3        S1SSISZZ0020Q    X -     -   THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3054-2/PS-93-021/920115113.
' DATE: *03/04/94 0
509275 C-11SWG-3B                                VT-3        S1SSISZZ0020Q    x   - -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
* SERVICE WATER SYSTEM  
.,,.,,.,    C-11SWG-4B GUIDE VT-3                                    THIS SUPPORT (SUM.# 509280) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.
509285 C-11SWG-5B                                VT-3        S1SSISZZ0020Q    X -   - PRESERVICE (NO MOO.) PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
509290 C-12SWG-3A                                VT-3      S1SSISZZ0020Q    X -   - PRESERVICE (NO MOD.) PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
509295 C-12SWG-4                                  VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS.MODIFIED PER ANCHOR                                                                            1EC-3054-2/PS-93-021/920115113.
509300 C-11SWG-9B                                VT-3                                    THIS SUPPORT (SUM.# 509300) WAS DELETED GUIDE                                                                            PER 1EC-3054-2/PS-93-021/920115113.
 
  ' DATE: *03/04/94                                 SALEM NUCLEAR PO\IER STATION UNIT 1                                PAGE:    53 R~VISION:      0                       ClJTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND ClJTAGE (93RF)
CLASS 3 SECTION XI CQ4PLETE COMPONENTS
* SERVICE WATER SYSTEM N    0 ASME                                    0 G T SEC. XI                                R E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION  
EXAMINATION AREA               CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE         C M R   **CALIBRATION BLOCK**
--------------------------------------
SW1220 CREF. DWG. NO. SW-1-1A 02>
SALEM NUCLEAR PO\IER STATION UNIT 1 ClJTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND ClJTAGE (93RF) CLASS 3 SECTION XI CQ4PLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 53 SW1220 CREF. DWG. NO. SW-1-1A 02> 509305 C-11SIJG-11A GUIDE 509310 C-11SWG-6 GUIDE 509315 C-12SWG-7A GUIDE 509320 C-12SWH-9 HANGER
509305 C-11SIJG-11A                               VT-3       S1SSISZZ002QQ     X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
* 5.09345 SW1220 CREF. DWG. C-12SWG-12 GUIDE NO. SW-1-5B 02> F-C F3.10 SW1238 (REF. DWG. NO. SW-1-1A 02> 509370 C-11SWH-1 HANGER 509375 C-11SWG*3A GUIDE 509380 C-11SWG-4A GUIDE 509385 C-11SWG-5A GUIDE VT-3 S1SSISZZ002QQ VT-3 S1SSISZZ002QQ VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 VT-3 S1SSISZZ0020Q X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
509310 C-11SWG-6                                  VT-3      S1SSISZZ002QQ      X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
509315 C-12SWG-7A                                VT-3      S1SSISZZ0020Q      X -   - PRESERVICE (NO MOD.) PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.
509320 C-12SWH-9 HANGER VT-3      S1SSISZZ0020Q      x - -   THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
SW1220 CREF. DWG. NO. SW-1-5B 02>
x . -THIS SUPPORT WAS MODIFIED PER 1EC*3054-2/PS*93*021/920115113.
* 5.09345  C-12SWG-12                      F-C      VT-3      S1SSISZZ0020Q      x .   - THIS SUPPORT WAS MODIFIED PER GUIDE                          F3.10                                            1EC*3054-2/PS*93*021/920115113.
X * -THIS SUPPORT WAS MODIFIED PER 1EC-3054*2/PS-93-021/920115113.
SW1238 (REF. DWG. NO. SW-1-1A 02>
X * -THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
509370 C-11SWH-1                                  VT-3      S1SSISZZ0020Q      X *   - THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3054*2/PS-93-021/920115113.
THIS SUPPORT (SUM.# 501390) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.
509375 C-11SWG*3A                                  VT-3      S1SSISZZ0020Q      X *   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.
509380 C-11SWG-4A                                  VT-3                                  THIS SUPPORT (SUM.# 501390) WAS DELETED GUIDE                                                                            PER 1EC-3054-2/PS-93-021/920115113.
'DATE: 03/04/94 SALEM NUCLEAR STATION UNIT 1 . PAGE: REVISION:
509385 C-11SWG-5A                                  VT-3      S1SSISZZ0020Q      X -   - PRESERVICE (NO MOD.) PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
0 WATER SYSTEM OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERICX>, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI  
 
    'DATE: 03/04/94                                 SALEM NUCLEAR P~R STATION UNIT 1                                   . PAGE: 54 REVISION:     0                       OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0)
~SERVICE SECOND INTERVAL, SECOND PERICX>, SECOND OUTAGE (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N    0 ASME                                   0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHCX> SW1238 CREF. DWG. NO. SW-1-1A 02) 509395 C-11SWG-8A GUIDE 509400 C-11SWG-9A GUIDE 509405 C-11SWH-10 HANGER D-B D2 SW1238 CREF. DWG. NO. SW-1-5A 02) 509425 C-11SWG-13 GUIDE SW1365 CREF. DWG. NO. SW-1-3B 01) 509525 A1-SWG-343 GUIDE 509530 A1-SWG-325 GUIDE SW1366 CREF. DWG. NO. SW-1-3B 01) 509535 A1-SWG-326 GUIDE 509540 A1-SWG-327 GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MCX>IFIED PER 1EC-3054-2/PS-93-021/920115113.
EXAMINATION AREA               CATGY    EXAM                          E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHCX>     PROCEDURE          C M R    **CALIBRATION BLOCK**
X --PRESERVICE (NO Mex>.) PER 1EC-3054-2/PS-93-021/920115113.
SW1238 CREF. DWG. NO. SW-1-1A 02) 509395   C-11SWG-8A                     D-B     VT-3       S1SSISZZ0020Q     X -   -   THIS SUPPORT WAS MCX>IFIED PER GUIDE                          D2                                              1EC-3054-2/PS-93-021/920115113.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
509400 C-11SWG-9A                                VT-3      S1SSISZZ0020Q      X -   -   PRESERVICE (NO Mex>.) PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509405  C-11SWH-10                              VT-3      S1SSISZZ0020Q      X -   -   THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3054-2/PS-93-021/920115113.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
SW1238 CREF. DWG. NO. SW-1-5A 02) 509425 C-11SWG-13                                VT-3      S1SSISZZ0020Q      X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
54 
SW1365 CREF. DWG. NO. SW-1-3B 01) 509525 A1-SWG-343                                VT-3      S1SSISZZ0020Q      X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
' DATE: fJ3/04/94 REVISION:
509530 A1-SWG-325                                VT-3      S1SSISZZ0020Q      X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
0 SERVICE WATER SYSTEM  
SW1366 CREF. DWG. NO. SW-1-3B 01) 509535 A1-SWG-326                                VT-3        S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
509540 A1-SWG-327                                VT-3      S1SSISZZ0020Q      X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
 
  ' DATE: fJ3/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE: 55 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N      0 ASME                                  0  G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1366 (REF. DWG. NO. SW-1-3B 01) 509545 A1-SWG-304 GUIDE 509550 1A-SWA-303A GUIDE 509555 A1*SWG*303 GUIDE 509560 A1-SWH*302 HANGER
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
* 509565 A1*SWG*301 GUIDE 509570 A1*SWG*300 GUIDE 509575 A1*SWG-318 GUIDE 509580 A1-SWH*317 HANGER 509585 A1-SWA*WS05 ANCHOR D-B D2.20 D-B D2.20 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT*3 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q x -THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
SW1366 (REF. DWG. NO. SW-1-3B 01) 509545 A1-SWG-304                               VT-3       S1SSISZZ0020Q     x -       THIS SUPPORT WAS MODIFIED PER GUIDE                                                                        1EC-3149/PS-93-030/930422073.
X *
509550 1A-SWA-303A                      D-B      VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                          D2.20                                          1EC-3149/PS-93-030/930422073.
* THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.
509555 A1*SWG*303                                VT-3      S1SSISZZ0020Q    X *
x --THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073
* THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC*3149/PS*93*030/930422073.
* x --THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.
509560 A1-SWH*302 HANGER VT-3      S1SSISZZ0020Q    x - -   THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073 *
x --THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.
* 509565 A1*SWG*301 GUIDE VT-3      S1SSISZZ0020Q    x - -   THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.
X -* THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.
509570 A1*SWG*300 GUIDE VT-3      S1SSISZZ0020Q    x - -   THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.
X *
509575 A1*SWG-318                                VT-3      S1SSISZZ0020Q    X -
* THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93-030/930422073.
* THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC*3149/PS*93*030/930422073.
X *
509580 A1-SWH*317                                VT-3      S1SSISZZ0020Q    X *
* THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS-93*030/930422073.
* THIS SUPPORT WAS MODIFIED PER HANGER                                                                        1EC*3149/PS*93-030/930422073.
55 
509585 A1-SWA*WS05                      D-B      VT*3      S1SSISZZ0020Q    X *
'DATE: G3/04/94 REVISION:
* THIS SUPPORT WAS MODIFIED PER ANCHOR                        D2.20                                            1EC*3149/PS-93*030/930422073.
0 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 56 WATER SYSTEM OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS
 
* ASME SEC. XI CATGY EXAM
    'DATE: G3/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE:   56 REVISION:    0                          OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
~SERVICE    WATER SYSTEM CLASS 3 SECTION XI COMPLETE COMPONENTS N      0 ASME                                   0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION ITEM NO METHOD SW1373 CREF. DWG. NO. SW-1-3B 01) 509590 A1-SWG-328 GUIDE 509595 A1-SWG-329 GUIDE SW1377 CREF. DWG. NO. SW-1-3B 01) 509600 A1-SWS-351 SUPPORT 509605 A1-SWG-352 GUIDE SW1384 DWG. NO. 509635 C-14SWH-1 HANGER 509640 C-13SWG-3D  
EXAMINATION AREA               CATGY    EXAM                        E 0 E      REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE        C M R      **CALIBRATION BLOCK**
*. ""-" GUIDE SW-1-1A 02) SW1496 CREF. DWG. NO. SW-1-9H 01) 5o98o5 1A-SWS-091 SUPPORT SW1498 DWG. NO. SW-1-3B 01l 509815 A1-SWS-340 SUPPORT VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q
SW1373 CREF. DWG. NO. SW-1-3B 01) 509590 A1-SWG-328                                 VT-3      S1SSISZZ0020Q    X -    -  THIS SUPPORT WAS MODIFIED PER GUIDE                                                                             1EC-3149/PS-93-030/930422073.
509595 A1-SWG-329                                 VT-3                                    THIS SUPPORT (SUM.# 509595) WAS DELETED GUIDE                                                                             PER 1EC-3149/PS-93-030/930422073.
SW1377 CREF. DWG. NO. SW-1-3B 01) 509600 A1-SWS-351                                 VT-3                                    THIS SUPPORT (SUM.# 509600) WAS DELETED SUPPORT                                                                           PER 1EC-3149/PS-93-030/930422073.
509605 A1-SWG-352                                 VT-3                                    THIS SUPPORT (SUM.# 509605) WAS DELETED GUIDE                                                                             PER 1EC-3149/PS-93-030/930422073.
* SW1384 509635 C-14SWH-1 HANGER
                    ~REF. DWG. NO. SW-1-1A 02)
VT-3      S1SSISZZ0020Q    x -    -  THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
509640 C-13SWG-3D VT-3      S1SSISZZ0020Q    x  - -    PRESERVICE (NO MOD.) PER GUIDE                                                                              1EC-3054-2/PS-93-021/920115113.
SW1496 CREF. DWG. NO. SW-1-9H 01) 5o98o5 1A-SWS-091                                 VT-3      S1SSISZZ0020Q    x  - -    THIS SUPPORTS VERTICAL MEMBERS WERE SUPPORT                                                                           REPLACED UNDER CJP #S-93-141 AND W.O.
                                                                                              #920530148.
SW1498 ~REF. DWG. NO. SW-1-3B 01l 509815 A1-SWS-340                                 VT-3       S1SSISZZ0020Q    x  - -
* THIS SUPPORT WAS MODIFIED PER SUPPORT                                                                            1EC-3149/PS-93-030/930422073.


S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
    '  D~TE: '03/04/94                               SALEM NUCLEAR POWER STATION UNIT 1                                    PAGE: 57 REVISION:       0                        OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
x --x --x --x --THIS SUPPORT (SUM.# 509595) WAS DELETED PER 1EC-3149/PS-93-030/930422073.
~SERVICE SECOND INTERVAL, SECOND PERia>, SECOND OUTAGE (93RF)
THIS SUPPORT (SUM.# 509600) WAS DELETED PER 1EC-3149/PS-93-030/930422073.
CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N      0 ASME                                  0 G T SEC. XI                              R E    H
THIS SUPPORT (SUM.# 509605) WAS DELETED PER 1EC-3149/PS-93-030/930422073.
THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.
THIS SUPPORTS VERTICAL MEMBERS WERE REPLACED UNDER CJP #S-93-141 AND W.O. #920530148.
* THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.  
'
'03/04/94 REVISION:
0 WATER SYSTEM  


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERia>, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METH<X> PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1541 CREF. DWG. NO. SW-1-3B 01) 509840 A1-SWG-349 GUIDE 509845 A1-SWG-330 GUIDE 509850 A1-SWS-350 SUPPORT 509855 A1-SWG-382 GUIDE 509860 A1-SWA-357 ANCHOR 509865 A1-SWG-385 GUIDE '"<* *SW1542 DWG. NO. SW-1-38 01l 509870 A1-SWS-332 SUPPORT 509875 A1-SWG-312 GUIDE 509880 A1-SWA-311 ANCHOR D-B D2.20 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ00200 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
EXAMINATION AREA                 CATGY    EXAM                        E 0 E      REMARKS NUMBER IDENTIFICATION                     ITEM NO METH<X>     PROCEDURE         C M R     **CALIBRATION BLOCK**
X --THIS SUPPORT WAS MODIFIED PER '1EC-3149/PS-93-030/930422073.
SW1541 CREF. DWG. NO. SW-1-3B 01) 509840 A1-SWG-349                                 VT-3       S1SSISZZ0020Q     X -   -   THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
509845 A1-SWG-330                                  VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          '1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS Ma>IFIED PER 1EC-3149/PS-93-030/930422073.
509850 A1-SWS-350                                  VT-3      S1SSISZZ00200    X -   -   THIS SUPPORT WAS MOOIFIED PER SUPPORT                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509855 A1-SWG-382                                  VT-3      S1SSISZZ0020Q    X -     -   THIS SUPPORT WAS Ma>IFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
x --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509860 A1-SWA-357                                  VT-3      S1SSISZZ0020Q    X -     -   THIS SUPPORT WAS MODIFIED PER ANCHOR                                                                            1EC-3149/PS-93-030/930422073.
x -THIS SUPPORT WAS M<X>IFIED PER 1EC-3149/PS-93-030/930422073.
509865 A1-SWG-385                                VT-3        S1SSISZZ0020Q    x   - -     THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
              *SW1542  ~REF. DWG. NO. SW-1-38 01l 509870 A1-SWS-332                                  VT-3        S1SSISZZ0020Q    x -   ~
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
THIS SUPPORT WAS M<X>IFIED PER SUPPORT                                                                          1EC-3149/PS-93-030/930422073.
57 
509875 A1-SWG-312                                  VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
'DATE: 03/04/94 REVISION:
509880 A1-SWA-311                        D-B      VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER ANCHOR                          D2.20                                            1EC-3149/PS-93-030/930422073.
0 SALEM NUCLEAR POWER STATION UNIT 1 PAGE:
 
WATER SYSTEM OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS
      'DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                 PAGE:   58 REVISION:      0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
* ASME SEC. XI  
~SERVICE SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N      0 ASME                                 0 G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD SW1542 CREF. DWG. NO. SW-1-3B 01) 509885 A1-SWG-310 GUIDE 509890 A1-SWG-309 GUIDE SW1545 CREF. DWG. NO. SW-1-3B 01) 509895 A1-SWG-341 GUIDE 509900 A1-SWG-342 GUIDE SW1546 CREF. DWG. NO. SW-1-3B 01) VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q  
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD       PROCEDURE        C M R    **CALIBRATION BLOCK**
SW1542 CREF. DWG. NO. SW-1-3B 01) 509885 A1-SWG-310                                 VT-3        S1SSISZZ0020Q    X -    -  THIS SUPPORT WAS MODIFIED PER GUIDE                                                                         1EC-3149/PS-93-030/930422073.
509890 A1-SWG-309                                 VT-3        S1SSISZZ0020Q    X -    -  THIS SUPPORT WAS MODIFIED PER GUIDE                                                                         1EC-3149/PS-93-030/930422073.
SW1545 CREF. DWG. NO. SW-1-3B 01) 509895 A1-SWG-341                                 VT-3        S1SSISZZ0020Q    X -    -  THIS SUPPORT WAS MODIFIED PER GUIDE                                                                           1EC-3149/PS-93-030/930422073.
509900 A1-SWG-342                                 VT-3
* S1SSISZZ0020Q    X -    -  THIS SUPPORT WAS MODIFIED PER GUIDE                                                                           1EC-3149/PS-93-030/930422073.
* SW1546 CREF. DWG. NO. SW-1-3B 01) 509905 A1-SWS-331 SUPPORT VT-3                                   THIS SUPPORT (SUM.# 509905) WAS DELETED PER 1EC-3149/PS-93-030/930422073.
509910 A1-SWS-339                                  VT-3        S1SSISZZ002QQ    X -    -  THIS SUPPORT WAS MODIFIED PER SUPPORT                                                                        1EC-3149/PS-93-030/930422073.
509915 A1-SWG-375                                  VT-3       S1SSISZZ0020Q    X -    -  THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
509920 A1-SWS-374                                  VT-3       S1SSISZZ002QQ    X -    -  THIS SUPPORT WAS MODIFIED PER SUPPORT                                                                        1EC-3149/PS-93-030/930422073.
509925 A1-SWA-355                                  VT-3       S1SSISZZ0020Q   X -    -  THIS SUPPORT WAS MODIFIED PER ANCHOR                                                                          1EC-3149/PS-93-030/930422073.


S1SSISZZ0020Q S1SSISZZ0020Q
    ' DATE: *03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:  59 REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)
* S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
~SERVICE SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N      0 ASME                                  0 G T SEC. XI                              R E .H
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
58 509905 A1-SWS-331 SUPPORT VT-3 THIS SUPPORT (SUM.# 509905) WAS DELETED PER 1EC-3149/PS-93-030/930422073.
509910 A1-SWS-339 SUPPORT 509915 A1-SWG-375 GUIDE 509920 A1-SWS-374 SUPPORT 509925 A1-SWA-355 ANCHOR ** : *....:: .. VT-3 VT-3 VT-3 VT-3 S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ0020Q X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. 
' DATE: *03/04/94 REVISION:
0 WATER SYSTEM  


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E .H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 59 SW1546 CREF. DWG. NO. SW-1-3B 01) 509930 A1-SWG-384 GUIDE SW1550 CREF. DWG. NO. SW-1-3B 01) 509935 A1-SWA-353 ANCHOR 509940 A1-SWG-359 GUIDE-509945 A1-SWG-360 GUIDE 509950 A1-SWG-361 GUIDE 509955 A1-SWS-334 SUPPORT 509960 A1-SWG-333 GUIDE 509965 A1-SWG-383 GUIDE (REF. DWG. NO. SW-1-3B 01) 509966 A1-SWG-2433 GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT*3 VT-3 VT-3 S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
SW1546 CREF. DWG. NO. SW-1-3B 01) 509930 A1-SWG-384                                 VT-3      S1SSISZZ002QQ    X -   - THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                         1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
SW1550 CREF. DWG. NO. SW-1-3B 01) 509935 A1-SWA-353                                VT-3       S1SSISZZ0020Q     X -   - THIS SUPPORT WAS MOOIFIED PER ANCHOR                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
509940 A1-SWG-359                                VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER GUIDE-                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
509945 A1-SWG-360                                VT-3      S1SSISZZ002QQ    X -   - THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509950 A1-SWG-361                                VT-3      S1SSISZZ002QQ    X -   - THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
509955 A1-SWS-334                                VT-3      S1SSISZZ002QQ    X -   - THIS SUPPORT WAS MODIFIED PER SUPPORT                                                                        1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
509960 A1-SWG-333                                VT*3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509965 A1-SWG-383                                  VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
ANCHOR A1-SWA-383 WAS REPLACED WITH GUIDE A1-SWG-2433.
(REF. DWG. NO. SW-1-3B 01) 509966 A1-SWG-2433                                VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073. ANCHOR A1-SWA-383 WAS REPLACED WITH GUIDE A1-SWG-2433.
DATE: 03/04/94 ,REVISION:
 
0
DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE: 60
* SERVICE WATER SYSTEM  
  ,REVISION:     0                        OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS
* SERVICE WATER SYSTEM N      0 ASME                                  0  G T SEC. XI                              R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM -ITEM NO METHOO PROCEDURE . N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1551 CREF. DWG. NO. SW-1-3B 01) 509970 A1-SWG-322 GUIDE 509975 A1-SWH-321 HANGER 509980 A1-SWA-WS07 ANCHOR SW1556 {REF. 509985 A1-SWS-338 SUPPORT
EXAMINATION AREA                 CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                 - ITEM NO METHOO     PROCEDURE   . C M R     **CALIBRATION BLOCK**
* 509990 A1-SWS-336 SUPPORT 509995 A1-SWS-335 SUPPORT 510000 A1-SWG-337 GUIDE DWG. NO. D-B D2.20 SW-1-3B 01) SW1557 (REF. DWG. NO. SW-1-3B 01) 510005 A1-SWG-308 GUIDE 510010 1A-SWA-307A GUIDE D-B D2.20 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT*3 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED 1EC-3149/PS-93-030/930422073.
SW1551 CREF. DWG. NO. SW-1-3B 01) 509970 A1-SWG-322                                 VT-3       S1SSISZZ0020Q     X -   - THIS SUPPORT WAS MOOIFIED PER GUIDE                                                                          1EC-3149/PS-93-030/930422073.
x --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.
509975 A1-SWH-321                                VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3149/PS-93-030/930422073.
x --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
509980 A1-SWA-WS07                      D-B      VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED ~ER ANCHOR                          D2.20                                          1EC-3149/PS-93-030/930422073.
60 
SW1556 {REF. DWG. NO. SW-1-3B 01) 509985 A1-SWS-338                                VT-3      S1SSISZZ0020Q    x -     - THIS SUPPORT WAS MOOIFIED PER SUPPORT                                                                          1EC-3149/PS-93-030/930422073.
, DATE:, D3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: REVISION:
* 509990 A1-SWS-336                                VT-3        S1SSISZZ0020Q    x   - -   THIS SUPPORT WAS MODIFIED PER SUPPORT                                                                          1EC-3149/PS-93-030/930422073.
0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) . CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM ASME SEC. XI sutl4ARY EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD SW1557 CREF. DWG. NO. SW-1-3B 01) 510015 A1-SWG-307 GUIDE 510020 A1-SWG-306 GUIDE 510025 A1-SWG-305 GUIDE 510030 A1-SWA-WS06 ANCHOR D-B D2.20 SW1619 CREF. DWG. NO. SW-1-1A 02) 510135 C-14SWH-1 HANGER 510225 C-13SWG-3B GUIDE .. SW1640 'REF. DWG. NO. SW-1-1A 02l 510250 C-13SWH-1 HANGER .---*:*"\''
509995 A1-SWS-335                                VT-3        S1SSISZZ0020Q    X -     - THIS SUPPORT WAS MODIFIED PER SUPPORT                                                                          1EC-3149/PS-93-030/930422073.
., -,. .... 510255 C-13SWG-3A GUIDE SW1664 'REF. DWG. NO. SW-1-1A 02l 510395 C-12SWH-2 HANGER VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
510000 A1-SWG-337                                VT-3        S1SSISZZ002QQ    X -     - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
SW1557 (REF. DWG. NO. SW-1-3B 01) 510005 A1-SWG-308                                VT-3        S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
510010  1A-SWA-307A                    D-B      VT*3        S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                          D2.20                                            1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.
 
X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
, DATE:, D3/04/94                                       SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE: 61 REVISION:     0                             OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
                                                  . CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N    0 ASME                                   0  G  T SEC. XI                               R E H sutl4ARY EXAMINATION AREA                   CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                         ITEM NO METHOD     PROCEDURE        C M R    **CALIBRATION BLOCK**
x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
SW1557 CREF. DWG. NO. SW-1-3B 01) 510015 A1-SWG-307                                     VT-3       S1SSISZZ0020Q     X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                                1EC-3149/PS-93-030/930422073.
X --THIS SUPPORT-WAS MODIFIED PER 1EC-3054*2/PS-93*021/920115113.
510020 A1-SWG-306                                      VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                                1EC-3149/PS-93-030/930422073.
61  
510025 A1-SWG-305                                      VT-3      S1SSISZZ0020Q    X -   - THIS SUPPORT WAS MODIFIED PER GUIDE                                                                                1EC-3149/PS-93-030/930422073.
'DATE: 03/04/94 REVISION:
510030 A1-SWA-WS06                          D-B      VT-3      S1SSISZZ0020Q    X   - -   THIS SUPPORT WAS MODIFIED PER ANCHOR                              D2.20                                            1EC-3149/PS-93-030/930422073.
0 SERVICE WATER SYSTEM  
SW1619 CREF. DWG. NO. SW-1-1A 02) 510135 C-14SWH-1                                      VT-3        S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER HANGER                                                                                1EC-3054-2/PS-93-021/920115113.
510225 C-13SWG-3B                                      VT-3      S1SSISZZ0020Q    x - -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                                1EC-3054-2/PS-93-021/920115113.
                          ~ *-~..
SW1640 'REF. DWG. NO. SW-1-1A 02l 510250 C-13SWH-1                                        VT-3      S1SSISZZ0020Q    x - -   THIS SUPPORT WAS MODIFIED PER HANGER                .---*:*"\''                                                    1EC-3054-2/PS-93-021/920115113.
                                        ....~
510255 C-13SWG-3A                                      VT-3      S1SSISZZ0020Q    x - -     THIS SUPPORT WAS MODIFIED PER GUIDE                                                                                  1EC-3054-2/PS-93-021/920115113.
SW1664 'REF. DWG. NO. SW-1-1A 02l 510395 C-12SWH-2                                        VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT- WAS MODIFIED PER HANGER                                                                                1EC-3054*2/PS-93*021/920115113.
 
  'DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:    62 REVISION:     0                        OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)
                                            , CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N    O ASME                                  0 G T SEC. XI                              R  E  H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) , CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 62 SW1664 CREF. DWG. NO. SW-1-1A 02> 510400 C-11SWG-3D GUIDE 510405 C-11SWG-40 GUIDE 510410 C-11SWG-5D GUIDE 510415 C-12SWG-38 GUIDE 510420 C-12SWG-5 ANCHOR 510425 C-11SWG-90 GUIDE 510430 C-11SWG-11C GUIDE 510433 C-12SWG-6A GUIDE 510435 C-12SWG-58 GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ002QQ X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
EXAMINATION AREA               CATGY    EXAM                        E 0 E    REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE         C M R     **CALIBRATION BLOCK**
THIS SUPPORT (SUM.# 501405) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOD.) PER . 1EC-3054-2/PS-93-021/920115113. X --_pRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
SW1664 CREF. DWG. NO. SW-1-1A 02>
THIS SUPPORT (SUM.# 510425) WAS D.ELETED PER 1EC-3054-2/PS-93-021/920115113.
510400 C-11SWG-3D                                 VT-3       S1SSISZZ002QQ     X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOO.) PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.
510405 C-11SWG-40                                VT-3                                  THIS SUPPORT (SUM.# 501405) WAS DELETED GUIDE                                                                          PER 1EC-3054-2/PS-93-021/920115113.
'DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: REVISION:
510410 C-11SWG-5D                                VT-3      S1SSISZZ002QQ    X -   -   PRESERVICE (NO MOD.) PER .
0 .WATER SYSTEM OUTAGE ISi EXAMINATION RESULTS CS1RF.0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) . CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI  
GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
510415 C-12SWG-38                                VT-3      S1SSISZZ002QQ    X -   -   _pRESERVICE (NO MOD.) PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
510420 C-12SWG-5                                  VT-3      S1SSISZZ002QQ    X -   -   THIS SUPPORT WAS MODIFIED PER ANCHOR                                                                        1EC-3054-2/PS-93-021/920115113.
510425 C-11SWG-90                                VT-3                                  THIS SUPPORT (SUM.# 510425) WAS D.ELETED GUIDE                                                                          PER 1EC-3054-2/PS-93-021/920115113.
                        ~ **~*
510430 C-11SWG-11C                                VT-3      S1SSISZZ002QQ    x - -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
510433 C-12SWG-6A                                VT-3      S1SSISZZ0020Q    X -   -   PRESERVICE (NO MOO.) PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
510435 C-12SWG-58                                VT-3      S1SSISZZ002QQ    X -   -   PRESERVICE (NO MOD.) PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
 
                                                                                                                                  *. ~;;,,~;;~.
                                                                                                                                            *1
    'DATE: 03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                   PAGE: 63 REVISION:     0                       OUTAGE ISi EXAMINATION RESULTS CS1RF.0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)
~SERVICE    .WATER SYSTEM
                                                . CLASS 3 SECTION XI COMPLETE COMPONENTS N      O ASME                                 0  G T SEC. XI                               R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD SW1664 CREF. DWG. NO. SW-1-1A 022 510440 C-12SWG-7B GUIDE 510445 C-12SWG-8 GUIDE 510450 C-12SWG-10 GUIDE 510455 C-12SWH-11 HANGER SW1664 CREF. DWG. NO. SW-1-5B 022 510485 C-12SWG-16 GUIDE F-C F3.10 SW1684 CREF. DWG. NO. SW-1-5A 02) 510520 C-11SWG-17 GUIDE F-C F3.10 SW1684 CREF. DWG. NO. SW-1-1A 02> 510555 C-11SWH-2 HANGER 510560 C-11SWG-3C GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --PRESERVICE CNO MOD.) PER 1EC-3054-2/PS-93-021/920115113.
EXAMINATION AREA                 CATGY    EXAM                        E 0 E      REMARKS NUMBER IDENTIFICATION                   ITEM NO METHOD     PROCEDURE        C M R      **CALIBRATION BLOCK**
X --PRESERVICE CNO MOO.) PER 1EC-3054-2/PS-93-021/920115113.
SW1664 CREF. DWG. NO. SW-1-1A 022 510440 C-12SWG-7B                                 VT-3       S1SSISZZ002QQ     X -   -   PRESERVICE CNO MOD.) PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.
510445 C-12SWG-8                                  VT-3      S1SSISZZ002QQ    X -   -   PRESERVICE CNO MOO.) PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
X --THIS SUPPORT WAS MODIFIED PER 1EC-3054*2/PS-93-021/920115113._
510450 C-12SWG-10                                VT-3      S1SSISZZ002QQ    X -   -   THIS SUPPORT WAS MODIFIED PER GUIDE                                                                          1EC-3054-2/PS-93-021/920115113.
X -* THIS SUPPORT WAS MODIFIED PER 1EC-3054*2/PS*93*021/920115113.
510455 C-12SWH-11                                VT-3      S1SSISZZ0020Q    X -   -   THIS SUPPORT WAS MODIFIED PER HANGER                                                                          1EC-3054*2/PS-93-021/920115113._
X *
SW1664 CREF. DWG. NO. SW-1-5B 022 510485 C-12SWG-16                        F-C      VT-3      S1SSISZZ0020Q    X -
* THIS SUPPORT WAS MODIFIED PER 1EC*3054*2/PS*93*021/920115113.
* THIS SUPPORT WAS MODIFIED PER GUIDE                          F3.10                                            1EC-3054*2/PS*93*021/920115113.
X *
SW1684 CREF. DWG. NO. SW-1-5A 02) 510520 C-11SWG-17                        F-C      VT-3      S1SSISZZ002QQ    X *
* THIS SUPPORT WAS MOOIFIED PER 1EC*3054*2/PS*93*021/920115113.
* THIS SUPPORT WAS MODIFIED PER GUIDE                          F3.10                                            1EC*3054*2/PS*93*021/920115113.
X *
SW1684 CREF. DWG. NO. SW-1-1A 02>
* THIS SUPPORT WAS MODIFIED PER 1EC*3054*2/PS*93-021/920115113.  
510555 C-11SWH-2                                  VT-3      S1SSISZZ002QQ    X *
*.
* THIS SUPPORT WAS MOOIFIED PER HANGER                                                                          1EC*3054*2/PS*93*021/920115113.
*1 63 DATE: _ 03/04/94 'RE'flSI&deg;":
510560 C-11SWG-3C                                VT-3      S1SSISZZ002QQ      X *
0 _.SERVICE WATER SYSTEM  
* THIS SUPPORT WAS MODIFIED PER GUIDE                                                                            1EC*3054*2/PS*93-021/920115113.
 
DATE: _03/04/94                                 SALEM NUCLEAR POWER STATION UNIT 1                                  PAGE:  64
    'RE'flSI&deg;":     0                          OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)
SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE_ (93RF)
CLASS 3 SECTION XI COMPLETE COMPONENTS
_.SERVICE WATER SYSTEM N    0 ASME                                    0 G T SEC. XI                                  R E H


==SUMMARY==
==SUMMARY==
EXAMINATION AREA_ NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE_ (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 64 SW1684 CREF. DWG. NO. SW-1-1A 02> 510565 C-11SWG-4C GUIDE 510570 C-11SWG-5C GUIDE U0575 C-11SWG-7 ANCHOR 510580 C-11SWG-8B GUIDE 510585 *C-11SWG-9C GUIDE 510590 C-11SWG-11B GUIDE 510595 C-11SWH-12 HANGER SW1986 CREF. DWG. NO.-sw-1-3B 01> 510785 A1-SWG-320
EXAMINATION AREA_                CATGY    EXAM                          E 0 E  REMARKS NUMBER IDENTIFICATION                    ITEM NO METHOD      PROCEDURE          C M R  **CALIBRATION BLOCK**
-<t:_:
SW1684 CREF. DWG. NO. SW-1-1A 02>
510565 C-11SWG-4C                                  VT-3                                  THIS SUPPORT (SUM.# 510565) WAS DELETED GUIDE                                                                            PER 1EC-3054-2/PS-93-021/920115113.
510570 C-11SWG-5C                                  VT-3      S1SSl!lZZ0020Q      X -  -  PRESERVICE (NO MOD.) PER GUIDE                                                                            1EC-3054-2/PS-93-021/920115113.
U0575 C-11SWG-7                                    VT-3      S1SSISZZ0020Q      x - -  THIS SUPPORT WAS MODIFIED PER ANCHOR                                                                          1EC-3054-2/PS-93-021/920115113.
I 510580 C-11SWG-8B                                  VT-3      S1SSISZZ0020Q      x - -  PRESERVICE (NO MOD.) PER        -,
GUIDE                                                                            1EC-3054-2/PS
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l
_____ _ (name) (repair organization's P .0. no., job. no.,etc.)
*o~~~~-~ru~bul~i~c~s~e~~~1~*rn~-E~l~~~~i~c~&~~~~s~Co~.~-~~~c~l~e~e~r~De~p~t~~*--~~~~#~S~9~2k-~3~9~2          (name)                              (repair organization's P .0. no., job. no.,etc.)
Foot of Buttonwood.
Foot of Buttonwood. Roa.d. Hancocks Bridge, NJ                                                      08038 (address)
Roa.d. Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
(name)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 4. System Containment Spray Nuclear Class II 5. a: Component repaired, modified or replaced _,l,..2"-'CS=3=6_Vi......,,,al......,,Vi_.,e.__
Foot of Buttonwood Road, Hancocks Bridge, NJ                                                        08038 (address)
__________________________
: 3. Name, address and identification of nuclear power plant                          Salem Nuclear Generating Station Unit                                                                #1 Foot of Buttonwocx:l Road, Hancocks Bridge, NJ                                                      08038
_ b: Nameofmanufacrurer
: 4. System          Containment Spray                                                                                                                                        Nuclear Class II
_
: 5. a: Component repaired, modified or replaced _,l,..2"-'
c: Identifying nos. 12024/S?OWDD
___ N;.,_/_A __ _ (mfr's. serial no.) (Narl
Signed________________
Signed________________
V -/lt1'rt-1ru J}g_4,.J, I CERTIFICATE OF INSPECTION I, the undersigned, holding a issued by The National Board of of competency issued by the province of Y and employed cf have inspected the repair, modification or replacement described in this report on J"v1-1c 7 . 19 93 and state that to the best of 1'1Y knowledge and belief. this repair. modification or replacement has been made in accordance with Section XI of the ASME Cade and the National Board rules as defined 1n the publication NB-102, current edition. By signing this certificate.
                                                                                                                                      /J.,
neither the Inspector nor his employer makes any warranty .
UM../~ V - /lt1'rt-1ru J}g_4,.J,
* ssed or imp!ied. concerning the repair. modification or replacement described in this report. Furthermore.
                                                                                                                                                                      -/!-A                    Pr&#xb5;icipal                Engr.
neither the Inspector nor his employer shall be 1n any manner far any personal injury or property damage or a loss of any kind arising from or Engr. Assn. Date '. 7 . ig---2..1.__
I                                                                 (repair organization)                                            (authorized representa:>Ve)                                          (11!le)
Signed
CERTIFICATE OF INSPECTION I, the undersigned, holding a ~~i,,~~n issued by The National Board of ~~1~t5~mml~eetcate of competency issued by the stat~ province of                                   Y and employed                 by-----------------------~------
: 12. 1<?...,,._,, Commissions NlJ 7980 NI 8 s ;;:r PA-z z'--"o"-4-.'---_  
cf                     have inspected the repair, modification or replacement described in this report on                                           J"v1-1c 7                       . 19 93 and state that to the best of 1'1Y knowledge and belief. this repair. modification or replacement has been made in accordance with Section XI of the ASME Cade and the National Board rules as defined 1n the publication NB-102, current edition. By signing this certificate. neither the Inspector nor his employer makes any warranty .
.... g e-Co*sc-..... t?;:s*:s:a:e; o* :J*ov '"'Ce ,)'""Cr .. -*:i::*. This form may be obtained from The National Board of Bailer and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
ssed or imp!ied. concerning the repair. modification or replacement described in this report. Furthermore. neither the Inspector nor his employer shall be 1n any manner far any personal injury or property damage or a loss of any kind arising from or connecte'Fg~2jf:}9sru~                                                                        Engr.         Assn.
Date     '. 7       . ig---2..1.__   Signed     W.1~7~ 12. 1<?...,,._,, ~m:                                            Commissions NlJ 7980                                 NI 8 s       ;;:r             z PA- z'--"o"-4-.'---_
(l~s:ie~                                                      (~Jn:* BaJ~o.;*nc!~c .... g e-Co*sc- ..... t?;:s*:s:a:e; o* :J*ov '"'Ce     ,)'""Cr .. -*:i::*.
This form may be obtained from The National Board of Bailer and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l erk periormed
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l erk periormed
* Public SeJ:vice Electric & Gas Co. -Nuclear Dept. CJP #893-124 (name) (repair organization's P.O. no .. job. no .. e!c.) Foot 01 Butto:nwocxl Road, Hanax:ks Bridge, NJ 08038 (address) (name) Foot of Buttonwcxx:l Road, Hancocks Bridge, NJ 08038 (address) 3 Name. address and identification of nuclear power plant Salem Nuclear Generatincf station Unit #1 Foot of Buttonwcxx:l Road, Hancocks Bridge, NJ 08038 4. System Safety Injection Nuclear Class I 5. a: Component repaired.
* Public SeJ:vice Electric                       & Gas Co. -             Nuclear           Dept.                 CJP #893-124 (name)                               (repair organization's P.O. no .. job. no .. e!c.)
modified or replaced 13SJ156 Valve b: Name of manufacturer
Foot 01 Butto:nwocxl Road, Hanax:ks Bridge, NJ                                           08038 (address)
__
(name)
_____________________________________
Foot of Buttonwcxx:l Road, Hancocks Bridge, NJ                                           08038 (address) 3 Name. address and identification of nuclear power plant                 Salem       Nuclear Generatincf station                                   Unit   #1 Foot of Buttonwcxx:l Road, Hancocks Bridge, NJ                                           08038
_ c: Identifying nos. 78704 N/A N/A (Nat'l.Bd.No.)
: 4. System         Safety Injection                                                                                                                   Nuclear Class                 I
Ourisdictional no.) d: Construction Code (edition)
: 5. a: Component repaired. modified or replaced 13SJ156 Valve
: 6. Section XI 1983 N/A (addenda)
                                                        -"-'------------------------------------~
SUmroer 83 (ed1:ion) (addenda)
b: Name of manufacturer _ _V..._e~l,,,an....__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
N/A (other) NIA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs. modifications, or replacements were made: 1983 (edition)
c: Identifying nos. 78704                         N/A                                      N/A                               N/A                         1968 (mfr'~~Spec                (Nat'l.Bd.No.)               Ourisdictional no.)                      (other)                                  (year built) d: Construction Code __,6,,_7,_6=2=----4~1~---                      N/A                                              NIA                                    I (edition)                      (addenda)                                      (Code Case(s))                          (Code Class)
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *76241 E-Spec (edition) 1968 (year built) I (Code Class) N/A (Code Case(s)) 883 (accendai (Code Case(s)) N/A N/A (addenda) (Code Case(s)) PSE&G 9. Design responsibilities  
: 6. Section XI                       1983                                       SUmroer 83                                                                              N/A (ed1:ion)                                                   (addenda)                                                       (Code Case(s))
---------------------ik.,.,kt--------'l"'q()AEpr--------------'llil<f/,.,"i'!A.----------
: 7. Applicable edition of ASME Code Section XI under which repairs. modifications, or replacements were made:                           1983           883                ~N~/=A~--
: 10. Tests .co.nducted:
(edition)        (accendai        (Code Case(s))
pressure O pressure ____ psi Code Case(s) _________
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                         *76241             N/A                N/A PSE&G
_ 11 Description of work ---------------------------------------------
                                                      *~  E-Spec                                                                       (edition)           (addenda)         (Code Case(s))
* (use of add1t1onal sheet(s) or is acceptaoie if properly  
: 9. Design responsibilities ---------------------ik.,.,kt--------'l"'q()AEpr--------------'llil<f/,.,"i'!A.----------
---------Work OI:de:r #: 900715077 Ikficie11cy Repo:t t #: N;'A 12.Remarks:
: 10. Tests .co.nducted: hydrost~l~ced'n~{i.~ Jlsc~esign pressure                             O pressure _ _ _ _ psi                     Code Case(s) _ _ _ _ _ _ _ _ __
Design CltarxJe Package #: N/A ReV. N/A See at tad red pages for IXs::r iptio11 of Replaceme11L.
11 Description of work - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
N;'A **8Ys Len IllseJ:: vice Test Temp. NO!' CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or repla.cement of the items above conforms to Section XI of the ASME Code and the National Boarc:)'5'1es as defined in the publication NB-102,Me.nt
(use of add1t1onal sheet(s) or   s~etc~(es)  is acceptaoie if properly 1dent1~1eci; Work OI:de:r #: 900715077                                                         Ikficie11cy Repo:t t #: N;'A 12.Remarks: ---r'l=:,,...;-,.....--r......,,......,....,....~~.n,..,.,...,..---.11--oc-t~,,_--------r:,......,.---1<T-f"ft--------------------~
:fition. 94 Certificate of Authorization no. to use the "NR" stamp expires ' , 19 ___ _ Date IP/ "1 19,!/3.___.
Design CltarxJe Package #: N/A                                         ReV. N/A See at tad red pages for IXs::r iptio11 of Replaceme11L. N;'A
Signed PSE&G Co.-Nuclear r:ept.
                        **8Ys Len IllseJ:: vice Test                                           Temp. NO!'
Engr. (repair organ,zat!on) representative; CERTIFICATE OF INSPECTION I, the undersigned, holding a issued by The National Board of of competency issued by the province of Y and employed by ____________
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or repla.cement of the items ~escribed above conforms to Section XI of the ASME Code and the National Boarc:)'5'1es as defined in the publication NB-102,Me.nt :fition.
of have inspected the repair, modification or replacement described in this report on S-vN 6 7 . 19 93 and stale that to the best of my knowledge and belief. this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board ru:es as defined 1n the publicaticn NB-102. current ednion. By signing this cernficate.
94 Certificate of Authorization no.                     to use the "NR" stamp expires                           '       , 19_ _ __
neither the Inspector nor his employer makes any warranty.
Date     IP/ "1       19,!/3.___. Signed         PSE&G Co.-Nuclear r:ept.                               ~ j~o.A l,~l:};['ipal                                                Engr.
ssed or implied. concerning the repair. modification or replacement described in this report Furthermore.
(repair organ,zat!on)                                 (aut~.o,;zea representative; CERTIFICATE OF INSPECTION I, the undersigned, holding a ~~~~n issued by The National Board of ~M-i'ts%~1~ee!8cate of competency issued by the   stat~ province of                           Y and employed by _ _ _ _ _ _ _ _ _ _ _ _~------------------
neither the Inspector nor his employer shall be n any manner for any personal iniury or property damage or a loss of any kind arising from or Engr. Assn. Date 6 -2 . 19_&__ Signed wdka..
of                     have inspected the repair, modification or replacement described in this report on S-vN 6 7                               . 19 93 and stale that to the best of my knowledge and belief. this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board ru:es as defined 1n the publicaticn NB-102. current ednion. By signing this cernficate. neither the Inspector nor his employer makes any warranty.
ssed or implied. concerning the repair. modification or replacement described in this report Furthermore. neither the Inspector nor his employer shall be n any manner for any personal iniury or property damage or a loss of any kind arising from or connccte'F&&:~cysr.t\.I~l                                Engr. Assn.
Date     6 -2         . 19_&__     Signed   wdka.. Ir~~?~W                                              Commis1~:~~~~~:~~ ~;c;/!r.~~J:e ~,~c:~~c."-~~-
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
 
FORM NR*1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) ~
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1
~orkpertormedtJY~Pi~blbl.l.l.l~ic--~sen-=--&#xa5;r~i-c~e.__E~l~ect~Q;*~i~c...__&._....Gas~ c~o'+-.,--.=-~Nl-..lCw*l~eQa.r___..De~pt..__,~~--'-C~IP...._*#~S~9~3=-~J~4~9'--~~~~~
(name)                                                                  (repair organization's P.0. no., job. no.,etc.)
Foot  of  Buttonwood Road,                  HanCXX"Jcs          Bridge,                NJ            08038 (address)
(name)
Foot    of Buttonwood                Rrad, Hancocks Bridge, NI                                          08038 (address)
: 3. Name, address and identification of nuclear power plant --~S~a~l~em~...N1~1c                            ...l~e-.;:i~~r__,,G..,.;e_.n
                                                                                                                                          ...e rn .......t_i...ng~_..S....          t-21
                                                                                                                                                                                        .....,t_1..,'o..,.n....____..U...n....i""t..._.,.:ff...1________
Foot    of Bn:ttonwocd Road, HaJ'lCOC:ks Bridge, NJ 08038
: 4. System          Chemical VolJJDJe Control (OTC)                                                                                                                                                              Nuclear Cl ass IT
: 5. a: Component repaired, modified or replaced _,,N...,o...,.___.J_.J.__.Ch_,*
                                                                                ..,a....DJ~,_.i_.ng_._J?r
                                                                                                        ......mip                                                ............i ......f_i...c....~
                                                                                                              ........__-__.M'L1.._'n..._.i_..f_.1....aw....._-'Or                            ......-\,(....Ccmp
                                                                                                                                                                                                              ............__T.._D........_.1_..CVE....,._.u2 0y.)_ _ _ __
b: Name of manufacturer                Pacific Pump Inc.
c: Identifying nos.      45603                            N/A                                                    N/A                                                              N/A                                                    1970 (mfr's. serial no.)            (Nat'l.Bd.No.)                    Gurisdictional no.)                                                  (other)                                                                            (year built) d: Construction Code        W E Spec            6771.25                  N/A                                                                          N/A (edition)                      (addenda)                                                                (Code Case(s))                                                                      (Code Class)
: 6. Section XI                          1983                                                                                                                                                                                                            N/A (edition)                                                              (addenda)                                                                                                              (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                              1983                        S83                                ....
                                                                                                                                                                                                                                                                  ~~/~A_ __
(edition)                      (addenda)                        (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                        *N/A                                                                      N/A
                                                                              *N      E-Spec 677125                                                                                    (edition)                            (addenda)                          (Code Case(s))
: 9. Design responsibilities  __i:::.:2.1:.w..z__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic            IX      pneumatic    D      design pressure                  D **pressure                          3550 psi                                  Code Case(s)_~~-/~A-------
                                    'Tbe lI!CX'Jified miniflaw orifire                                    was replaced in accomance with the (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                    36      to use the "NR" stamp expires                          Oct. 3,                          , 19=9_,.4_ __
Date      j( - "2.3'        a 19,--1...i._. Signed_ _PSE&G ____      Co. _ _ _ _ _Dept.
_-Nuclear                    _ _ __                                                                                                                Principal Engr.
(repair organization)                                                        (authorized representative)                                                                                (title)
CERTIFICATE OF INSPECTION
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of          New Jersey              and employed by                                                '                                                                                        Co of        MA            have inspected the repair, modification or replacement described in this report on                                                                                                  , 19      9...J..,            and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in an.y manner for any personal injury or prop~rty      e_am~r a loss of any kind arising from or connected with this inspection.
              , ;_                                                  ~                                                                                                  Facto:cy Mutual, Engr. Assn.
Date  11/ZI 1
                          , 1~.            Signed      ~                                                                        Commissions                      ~-7 Z.-ofl:, 11..);s(JJ .J ,,LJT<C..?/
(Inspector)                                                                (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
FORM NR*1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1  
NB*81 Rev.6
......... (name) (repair organization's P .0. no., job. no.,etc.)
 
Foot of Buttonwood Road, HanCXX"Jcs Bridge, NJ 08038 (address) (name) Foot of Buttonwood Rrad, Hancocks Bridge, NI 08038 (address)
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION OR INSTALLATION OF REPLACEMENT(S) ~
: 3. Name, address and identification of nuclear power plant
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
...  
* Pa e 1 of 1 ork performed by                                            e.,,,~
...  
                                          .......l ...i ...c....-...s... ..........,l....
... e ..... rn ....... t_i ...  
                                --wl?1...Llb
.... t-21 ... ..,t_1..,'
* c...e--.E  ...ect
o..,.n....____..U
                                                                                                ...1  ...............r ....i ...c__..,&,___.,.Ga,..is                ~-___.N!.,.....1c_J...,ea...r-.De
... n .... i""t..._.,.:ff
                                                                                                                                                .............C...o.....
... 1 _______ _ Foot of Bn:ttonwocd Road, HaJ'lCOC:ks Bridge, NJ 08038 4. System Chemical VolJJDJe Control (OTC) Nuclear Cl ass IT 5. a: Component repaired, modified or replaced _,,N...,o...,.___.J_.J.__.Ch_,*
(name)
..,a ....  
                                                                                                                                                                                                  ....             ......p+'"-t---.....c...JP.....____,#ff"S.....9.,_,3. ._-__._J....
...... mip ....... .__-__.M'L1.._'
(repair organization's P.O. no., job. no.,etc.)
n..._.i_..f_.1
5...
.... aw....._-'Or
0 _ _ _ _ __
............
Foot of Bn:ttonwood Road, Hancocks Bridge,                                                                                                       NT            08038 (address)
i ...... f_i ... c .... ...... -\,( .... Ccmp .........
(name)
...__T.._D
Foot        of  B11ttonwood Raad,                                              Hanax:ks                            Bridge, NJ                                08038 (address)
........ _.1_..CVE....,._.u2
: 3. Name, address and identification of nuclear power plant _ _....S...a....l"""em...wL.....L:Nt                                                              1c~l..,e
....... 0y.) ____ _ b: Name of manufacturer Pacific Pump Inc. c: Identifying nos. 45603 N/A (mfr's. serial no.) (Nat'l.Bd.No.)
                                                                                                                                                              .....       ..e.........                ..:ra r__,.C"...i=!.,...,n...,e .......u.t....iu.ng-"!f.....JS...,...ta......,.t_i._.o...,n.....___..U....n.._i'"'t..._JJ:#...l~------
d: Construction Code W E Spec 6771.25 (edition)
Foot of Bi rttor1wood Road, Hancccks Bridge, NT 08038
: 6. Section XI 1983 N/A (addenda)
: 4. System            Cbemi 03] Va] ume Contra] (OTC)                                                                                                                                                                                                                   Nuclear Class I I 5.~ Componentrepa~e~modified~re~~ed~Nua~.~1~2~~~~a~~~iu.ng~....JB~~~~-~M~iu.n~i~f~J..,~~~~~i~f_i..,c~~~*(C~~~~~I~D~l~~~~2~1~)_ _ _ __
N/A Gurisdictional no.) (edition) (addenda)
b: Name of manufacturer                          Pacific l?ump Inc c: Identifying nos.        45604                                                          N/A                                                                      N/A                                                                  N/A                                                      1970 (mfr's. serial no.)                                        (Narl.Bd.No.)                                      Qurisdictional no.)                                                              (other)                                                                    (year built) d: Construction Code          W E-Spec                              677125                                              N/A                                                                                        N/A (edition)                                                     (addenda)                                                                                 (Code Case(s))                                                                      (Code Class)
N/A (other) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
: 6. Section XI                                  1983                                                                                                                                                                                                                                                      N/A (edition)                                                                                                              (addenda)                                                                                                                    (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A 1970 (year built) (Code Class) N/A (Code Case(s)) S83 ....
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                                                                      J    983                          S83                      N;~/A~--
__ _ (addenda) (Code Case(s)) N/A *N E-Spec 677125 (edition) (addenda) (Code Case(s)) 9. Design responsibilities
(edition)                          (addenda)            (Code Case(s))
__i:::.:2.1:.w..z_
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                                                              *N;/A                                      N/A                    ~N;~/~A~--
_______________________________________
                                                                                                                      *&#xa5;! E-Spec 677125                                                                                                        (edition)                                (addenda)              (Code Case(s))
_ 10. Tests conducted:
: 9. Design responsibilities - - l : : L : l . . l : : . l : l l ! " " - - - - - - - - - - - - - - - - - - - - _ _ : _ - - - - - - - - - - - - - - - - - - - -
hydrostatic IX pneumatic D design pressure D **pressure 3550 psi Code
: 10. Tests conducted: hydrostatic IX                                  pneumatic                  D design pressure D** pressure 3550 psi                                                                                                            Code Case(s)_~N;-&#xa5;-/A......__ _ _ _ __
'Tbe lI!CX'Jified miniflaw orifire was replaced in accomance with the (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
The modified mini fl                                                      aw              orifice                      was          repJaced in accmT3ance wjth the (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19=9_,.4 __ _ a PSE&G Co. -Nuclear Dept. Date j( -"2.3' 19,--1...i._.
NIA  I CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Signed _______________
Certificate of Authorization no.                                     36                    to use the "NR" stamp expires                                                Oct. 3,                                  , 199~4~--
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
Date    II -     J.. 3*  19,_fil_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by ' Co of MA have inspected the repair, modification or replacement described in this report on , 19 9...J.., and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in an.y manner for any personal injury or a loss of any kind arising from or connected with this inspection. , ;_ Facto:cy Mutual, Engr. Assn. Date 11/ZI , Signed Commissions Z.-ofl:, 11..);s(JJ .J ,,LJT<C..?/
PSE&G Co. -Nuclear Dept.                                                                                           / / t?
1 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION OR INSTALLATION OF REPLACEMENT(S) TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
4.4-?ah*                                    -
* Pa e 1 of 1 *ork performed by --wl?1 ... Llb ....... l ... i ... c....-...s
                                                                                                                                                                                                                                          ..4c-*                                        Principal Engr.
...
(repair organization)                                                                                  (authorized representative)                                                                      (title)
.......... ,l. ...
CERTIFICATE OF INSPECTION
* c ... e--.E ... 1 ... ect ...............
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of            New                Jersey                              and employed by                                                                                                                                                      ce Co of      MA              have inspected the repair, modification or replacement described in this report on                                                                                                                                                                          'J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
r .... i ... c__..,&,___.,.Ga,..is
* any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
.............
            , /.. f                                                                          ~                                                                                                                                      Facto:ry Mutual. Engr. Assn.
C ... o .....
Date~,  1 19 7~ . Signed ./JU~                                                                                                                                      Commissions                          A :z..o~                              A./1Os1.J jv'.:J '/.JI (Inspector)                                                                                        (Natl.Bd.No.(including endorsements)state or province and number)
.... a ... r-.De ...... p+'"-t---..... c ... JP.....____,#ff"S
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
..... 9.,_,3..._-__._J
NB-81 Rev.6
.... 5 ... 0 _____ _ (name) (repair organization's P.O. no., job. no.,etc.)
 
Foot of Bn:ttonwood Road, Hancocks Bridge, NT 08038 (address) (name) Foot of B11ttonwood Raad, Hanax:ks Bridge, NJ 08038 (address)
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)JS TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l 1
: 3. Name, address and identification of nuclear power plant __ .... S ... a .... l"""em...wL.....L:Nt
orkpertormedby __J?!i;:..u1h.....,,J~i~c........S~e~rv.......,.~i~c~-e;;;._Ei.:.u.l~ect
.....  
                                                                                            .......~r~ic....__~&.._.G~.;a~s"'---'C~n~~---__.Nt........,1c                  J~e-eur__,De....,..pt.~
.. e .........
                                                                                                                                                                        .......                             ..............__ _~c~IP......__#wS              9_3~--1~7~l....______~
r__,.C"...i=!.,...,n...,e
(name)                                                                        (repair organization's P.0. no., job. no.,etc.)
.. :ra ....... u.t .... iu.ng-"!f.....JS...,...ta......,.t_i._.o...,n.....___..U
Foot of Buttonwood. Road, Hancoc;"ks Bridge, NJ                                                                                                08038 (address)
.... n.._i'"'t..._JJ:#
(name)
...
Foot of Buttonwood. Road, Hancocks Bridge. NJ                                                                                                  08038 (address)
Foot of Bi rttor1wood Road, Hancccks Bridge, NT 08038 4. System Cbemi 03] Va] ume Contra] (OTC) Nuclear Class II
: 3. Name, address and identification of nuclear power plant _ __._s...al......,em,...._Nuu.w...                                            c..,l.,.e...e"""r~Gen!oil!iii;&.Jl!iiera:...._...i..ti...i..in;J.l..J!:,__.S""'ta:i.s.ot~,..i...a..n...__,U,,,,,ru.:._..,.',_,,t,,___,#~1=----------
____ _ b: Name of manufacturer Pacific l?ump Inc c: Identifying nos. 45604 N/A N/A N/A 1970 (mfr's. serial no.) (Narl.Bd.No.)
FCX>t of Bnttanwoad Road, Hancxx=:ks Bridge, NT                                                                                                08038
Qurisdictional no.) (other) (year built) d: Construction Code W E-Spec 677125 N/A N/A (edition) (addenda) (Code Case(s)) (Code Class) 6. Section XI 1983 N/A (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: J 983 (edition)
: 4. System        Safety Injec+/-i on                                                                                                                                                                                                                Nuclear C1ass I I
S83 (addenda) (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *&#xa5;! E-Spec 677125 *N;/A N/A (edition) ( addenda) (Code Case(s)) 9. Design responsibilities
: 5. a: Component repaired, modified or replaced                                                                          _____________________________
--l::L:l..l::.l:ll!""--------------------__:_--------------------
                                                                            ......,J,..1..,S..,J,_l..,3,.,4.....__.V.""al~v..,,e b: Name of manufacturer --..v..i::..u::u.i.--------------------------------------
: 10. Tests conducted:
c: Identifying nos. 1 540                                                  WA                                                                                                                                                                                  1988 (mfr's. serial no.)                             (Nat'l.Bd.No.)                                      Qurisdictional no.)                                                                                                                         (year built) d: Construction Code        W E-Spec 676258 ANSI B31.7 1969                    ~~or!l.970                    Add.                        (addenda)                                                                            (Code Case(s))                                                        (Code Class)
hydrostatic IX pneumatic D design pressure D** pressure 3550 psi Code
: 6. Section XI                             1983                                                              _ _.._$1...nmne  ............r...._8..._.3_ _ _ _ _ _ _ _ __                                                                                                  WA (edition)                                                                                            (addenda)                                                                                                            (Code Case(s))
_____ _ The modified mini fl aw orifice was repJaced in accmT3ance wjth the (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                                                    1983                      S83                .....,1'{.,__./A......___ _
NIA I CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, ,
(edition)                (addenda)          (Code Case(s))
I 3 PSE&G Co. -Nuclear Dept. / / t? -Date I -J..
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                                              *1969                            1970                N/A
* 19,_fil_.
                                                                                                          *ANSI B31.7JN E-Spec 676258                                                                                      (edition)                        (addenda)          (Code Case(s))
Signed _______________ . 4.4-?ah* ..4c-* Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
: 9. Design responsibilities --'.:..t.!.IOlll!.sr...._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by ce Co of MA have inspected the repair, modification or replacement described in this report on 'J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
: 10. T~sts conducted: hydrostatic              D pneumatic D design pressure D **pressure                                                                                                  NOP psi                              Code Case(s) _ _                N;.,./_A_______
1 , /.. f Facto:ry Mutual. Engr. Assn.
: 11. Description of work          Replaced. valve stem: bolt:ITTJ and pe.rfonned wel.g. repair on leak.-off (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ __.Wi~o~r~k_..Qnj~~e~r.._~#~*~9~3.......,0-7~0~8~1~0~4=-----------~De--f~1~*c~i-e-n_cy~-R~e~pa~rt-~---'ff#~*_.N~/~A~---------
19 . Signed Commissions A
Design Change Package #: N/'A                                                                                        Rev. N/'A See attached pages for Description of Replacement.                                                                                                                                   N/A
A./1Os1.J jv'.:J '/.JI (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)JS TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l 1 orkpertormedby
                        **    stem Inservice Test                                                                                                              . Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
__
Certificate of Authorization no.                           36              to use the "NR" stamp expires                                          Oct. 3,                                  , 19~9~4~--
........
II-                                                       PSE&G                eo.-Nuclear Dept.                                                                        t? .t?;                  -<-* :..4..,,.1                                  Principal Engr.
.......  
7~
.......
Date          3  d    19,_&#xa3;3_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
..........
(repair organization)                                                                          (authorized representative)                                                           (title)
...._ __
CERTIFICATE OF INSPECTION
......
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of          New Jersey                              and employed by                                              Arkwri                          t Mutual Insurance Co of        MA          have inspected the repair, modification or replacement described in this report on                                                                                                          3     c>                      , 19  lj>J      and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property~ge or a loss of any kind arising from or connected with this inspection.
_____ (name) (repair organization's P .0. no., job. no.,etc.)
                                                                        ~                                                                                                                                    .,,Facto:r:y Mutual Engr. Assn.
Foot of Buttonwood.
Date / /
Road, Hancoc;"ks Bridge, NJ 08038 (address) (name) Foot of Buttonwood.
1 I3o        , 1~.             Signed          -~
Road, Hancocks Bridge. NJ 08038 (address)
(Inspector)               .
: 3. Name, address and identification of nuclear power plant __ _._s ... al......,em,...._Nuu.w
Commissions                          f".4            2 OS~ VI HS IS' 0&deg; &#xa3;'.5 /
... c..,l.,.e  
(Natl.Bd.No.(including endorsements)state or province and number)
...  
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
... a ..
NB-81 Rev.6
FCX>t of Bnttanwoad Road, Hancxx=:ks Bridge, NT 08038 4. System Safety Injec+/-i on Nuclear C1ass II 5. a: Component repaired, modified or replaced
 
____________________________
r==._......_._..............===========*-*-**-------
_ b: Name of manufacturer
FORM NR*1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0
--..v..i::..u::u.i.--------------------------------------
  ./         '
c: Identifying nos. 1 540 WA (mfr's. serial no.) (Nat'l.Bd.No.)
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2
d: Construction Code W E-Spec 676258 ANSI B31.7 1969 Add. Qurisdictional no.) (addenda) (Code Case(s)) 6. Section XI 1983 __ .._$1 ... nmne ............
ork perfonned by                pnhl j              c Service                          El ectri c & C-.as Ca                                      -    Nucl ear D?pt.                                           OTP #593-181 (name)                                              (repair organization's P.0. no., job. no.,etc.)
r...._8..._.3
Foat of Bnttonwpcx'J Road, Haneocks Bridge, N.T                                                                                                    08038 (address)
_________
(name)
_ (edition) (addenda) 1988 (year built) (Code Class) WA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
Foot of Buttonwood. Road, Hancocks Bridge, NJ                                                                                                      08038 (address)
S83 .....,1'{.,__./A......__
: 3. Name, address and identification of nuclear power plant _ __,,S..,,al.....,em..,..~Nu.....,,..,,,c,..l~e~.-::i""r~Gen~~era~~t~ing~:l-!s~ta,,,,..t"""i""o,._,n,____,,U._.m"""'"'t,,,_.u.#.:::1,________
__ (addenda) 1970 (Code Case(s)) *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7JN E-Spec 676258 (edition) (addenda) (Code Case(s)) 9. Design responsibilities
Foot of Butt:oIJIMCXld Roadu Hancocks Bridge, N.T                                                                                                  08038
--'.:..t.!.IOlll!.sr....
: 4. System        Safecy Tnj ecti on                                                                                                                                                                                                      Nuclear Class I
_______________________________________
: 5. a: Component repaired, modified or replaced _1...1.........                                     s r....1....7'--V,...,a...l...v......,.,e~----------------------------
_ 10.
b: Name of manufacturer                                Boc:kwel 1 - Fdwams c: Identifying nos.              N/A                                                          N/A                                                        N/A                                            N/A                                          1968 (mfr's. serial no.)                                     (Nari.ad.No.)                               Ourisdictional no.)                                      (other)                                                      (year built) d: Construction Code                  WE-Spec 677264                                                                    NIA                                                              N/A ANSI B31. 7 1969 H!Jiitioffi970 Add.                                                                        (addenda)    '                                                  (Code Case(s))                                                      (Code Class)
conducted:
: 6. Section XI                                          1 983                                                                  _ ___.Siu.u.1!IDileW1.L=.ir__.8u.3J.-_ _ _ _ _ _ _ _ __                                                                          WA (edition)                                                                                              (addenda)                                                                                        (Code Case(s))
hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) __ N;.,./_A ______ _ 11. Description of work Replaced.
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                                    1983                            S83            =.;N,_,,/A=----
valve stem: bolt:ITTJ and pe.rfonned wel.g. repair on leak.-off (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:
(edition)                        (addenda)      (Code Case(s))
_
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                                 *1969                                  1970            NIA
Design Change Package #: N/'A Rev. N/'A See attached pages for Description of Replacement.
                                                                                                                          *ANSI B31.7/N E-Spec 677264                                                            (edition)                            (addenda)      (Code Case(s))
N/A ** stem Inservice Test . Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, ,
: 9. Design responsibilities -"~~"2...-----------------------------------------
PSE&G eo.-Nuclear Dept. t? .t?; Date II-3 d 19,_&#xa3;3_. Signed ________________ -<-* :..4..,,.1 Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
: 10. Tests conducted: hydrostatic D                                        pneumatic                  D design pressure D **pressure                                              NOP psi                        Code Case(s) __N;...,_/_.._A..___ _ _ _ __
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on 3 c> , 19 lj>J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or or a loss of any kind arising from or connected with this inspection.
: 11. Description of work                    Replaced. valve with valve of new design.
I .,,Facto:r:y Mutual Engr. Assn. Date / / 3 o , Signed Commissions f".4 2 VI HS IS' 0&deg; &#xa3;'.5 / 1 (Inspector) . (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 r==._......_._
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
..............
: 12. Remarks: _                          .............e...r........#,,..:-.-9._3....0....7...0~9....l_,_7_,5'-----------....De..-...f...i ....
===========*-*-**-------
___,w,......or...k~Ord                                                                                                                                c ....i ""'e._.n. _.cy*-B"'"'eqpaleAeC.Ji+.. . . _....j~*...........N;~/~A,.,___ _ _ _ _ __
/ . ' FORM NR*1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork perfonned by pnhl j c Service El ectri c & C-.as Ca -Nucl ear D?pt. OTP #593-181 (name) (repair organization's P .0. no., job. no.,etc.)
D;?sjgn Change Package :ft: JE0-2309 Pkg. 1 See attached pages for Description of Replacement.
Foat of Bnttonwpcx'J Road, Haneocks Bridge, N.T 08038 (address) (name) Foot of Buttonwood.
                            **             stem Insei:vice Test                                                                                           T
Road, Hancocks Bridge, NJ 08038 (address)
* Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
: 3. Name, address and identification of nuclear power plant __
Certificate of Authorization no.                                         36                   to use the "NR" stamp expires                                 Oct.       3,           , 19_9_4_ __
t,,,_.u.#.:::1,__
Principal Engr.
_____ _ Foot of Butt:oIJIMCXld Roadu Hancocks Bridge, N.T 08038 4. System Safecy Tnj ecti on Nuclear Class I 5. a: Component repaired, modified or replaced _1 ... 1 ... s ...... r .... 1 .... 7'--V,...,a
Date     I-   I Cf       19 *~-                        Signed_ _PS_E_&G                         __   eo_.-_Nu_c_l_ear               __De_p_t_._ _
... l ...
(repair organization)                                                     (authorized representative)                                                     (title)
b: Name of manufacturer Boc:kwel 1 -Fdwams c: Identifying nos. N/A N/A (mfr's. serial no.) (Nari.ad.No.)
CERTIFICATE OF INSPECTION
d: Construction Code WE-Spec 677264 ANSI B31. 7 1969 H!Jiitioffi970 Add. NIA ' (addenda)
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of                   New Jersey and employed by                                                                               Arkwri t Mutual Insurance Co of       :MA.           have inspected the repair, modification or replacement described in this report on                                                                                           { - //                     , 19                     and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty,
N/A N/A Ourisdictional no.) (other) N/A (Code Case(s)) 6. Section XI 1 983 _ ___.Siu.u.1!IDileW1.L=.ir__.8u.3J.-
                                                                                                                              / /)
_________
ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
_ (edition) (addenda) 1968 (year built) (Code Class) WA (Code Case(s)) S83 =.;N,_,,/A=----
                                                                                                              ~                                                                                          xa~ory 9
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
Mutual Engr. Assn.
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 677264 *1969 (addenda) 1970 (Code Case(s)) NIA (edition) (addenda) (Code Case(s)) 9. Design responsibilities
Date     /- l~        , 1~.                        Signed                         tnrYV "L* ~                                                                      Commission&<t/tfi[9'L(/lJ/l                                                       MLJ 7:J (Inspector)                                                           (Natl.Bd.No.(including endorsements)state or province and number)
: 10. Tests conducted:
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) __ N;...,_/_.._A..__
NB-81 Rev.6
_____ _ 11. Description of work Replaced.
 
valve with valve of new design. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
p;;..---'"=;;;;;;;;;====;;:;;;;;;;;;;;;;;==:-....------..;;:=:==========-*------**- -----*---------
: 12. Remarks: _ ___,w,...o
Page J _ of ....A:_
.... r ...
FORM NR-1 ATTACHMENT Code Job Package No.: S93-181 Work performed by:       Public Service Electric & Gas Co., Nuclear Dept.
.............
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner:                   Public Service Electric & Gas Co.
e ... r ........ #,,..:-.-9._3  
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:                 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System: Safety Injection                                       Nuclear Class: ------
.... 0 .... 7 ... .... l_,_7_,5'-----------
I
.... De..-...f  
        ==============================================================================
... i .... c .... i ""'e._.n.._.cy*-B"'"'eqpaleAeC.Ji+......._
      *ID of Component Replaced:
.... ...........
    ,. Name of Manufacturer:
______ _ D;?sjgn Change Package :ft: JE0-2309 Pkg. 1 See attached pages for Description of Replacement.  
~i~f  serial No. Nat' 1. Bd.       Jurist No.         Other       Year Built     ASME Code Stamp'd.?
** stem Insei:vice Test T
~-      original Const. Code:                                Edition           Addenda, Code Class f~-- Code Cases:
* Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ _ Date I -I Cf Signed __ PS_E_&G __ eo_. -_Nu_c_l_ear
ID of Replacement: --=1=1=S~J_1=7~_v_a=l_v~e""----------------"-------
__ De_p_t_. __ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
Name of Manufacturer: _,=E=d=w~a=r~d=-~V=a=l~v~e:;........:I=n=c=.....*~------------------
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of :MA. have inspected the repair, modification or replacement described in this report on { -// , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
AFX-55        N/A            =N~/=A'-=---      N/A          1993          Yes
Date /-, Signed tnrYV "L* Commission&<t/tfi[9'L(/lJ/l MLJ 7 :J 9 / /)
                                                                                  ~=---------...,-.,,----::~
Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 p;;..---'"=;;;;;;;;;====;;:;;;;;;;;;;;;;;==:-....------..;;:=:==========-*------**-
Serial No. Nat'l. Bd. Jurist No.                Other       Year Built    ASME Code Stamp'd.?
-----*---------
Replacement Const. Code: *ASME III 1989                  Edition NLA_ Addenda, Code Class A._
Page J_ of ....A:_ FORM NR-1 ATTACHMENT Code Job Package No.: S93-181 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:
Code Cases:N/A
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System: Safety Injection Nuclear Class: I ------==============================================================================  
        *ANSI B31.7 1969 Ed.t970 Add.
*ID of Component Replaced:  
        ==============================================================================
,. Name of Manufacturer:
serial No. Nat' 1. Bd. Jurist No. original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Edition Addenda, Code Class ID of Replacement:
Name of Manufacturer:
AFX-55 N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Replacement Const. Code: *ASME III 1989 Code Cases:N/A 1993 Yes Year Built ASME Code Stamp'd.?
Edition NLA_ Addenda, Code Class A._ *ANSI B31.7 1969 Ed.t970 Add. ==============================================================================
of Component Replaced:
of Component Replaced:
of Manufacturer:
of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Serial No. Nat'l. Bd.         Jurist No.         Other      Year Built    ASME Code Stamp'd.?
Original Const. Code:                                 Edition          Addenda, Code Class Code Cases: - - -
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No.                 Other       Year Built     ASME Code Stamp'd.?
Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?
Replacement Const. Code:                                  Edition         Addenda, Code Class _
Addenda, Code Class _
Code Cases: - - -
        ============================================~=================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd.         Jurist No.         Other       Year Built     ASME Code Stamp'd.?
Edition Addenda, Code Class ------------------------------------------------------------------------------
Original Const. Code:                                Edition           Addenda, Code Class Code Cases: - - -
ID of Replacement:
ID of Replacement:
Name of Manufacturer:  
Name of Manufacturer:
'al No. Nat'l. Bd. Jurist No. acement Const. Code: Code Cases: __ _ Other Year Built Edition ASME Code Stamp'd.?
          'al No. Nat'l. Bd. Jurist No.                 Other       Year Built     ASME Code Stamp'd.?
Addenda Code Class ' -==============================================================================
acement Const. Code:                                  Edition        Addenda Code Class Code Cases: _ __                                                                  '             -
-".* ..... FORM NR*1 REPORT OF REPAIR 0 MODIFICATION$
        ==============================================================================
OR INSTALLATION OF REPLACEMENT(S)
 
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 *o.rk performed by Puhl i c Service El ectri c & C..as C.O. -Nucl ear Dept. CJP =#S93-J 82 (name) (repair organization's P .0. no., job. no.,etc.)
                      -     ".* ..... FORM NR*1 REPORT OF REPAIR 0 MODIFICATION$ OR INSTALLATION OF REPLACEMENT(S)
Foot of Buttonwoad Roodu Hanmc'ks Bridger NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 (address)
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS D
: 3. Name, address and identification of nuclear power plant ___ S.....,al....,,em  
Page 1 of 2 o.rk performed by       Puhl i c             Service El ectri c               &     C..as C.O. - Nucl ear Dept.                                                                         CJP =#S93- J 82
..........
        *                                                                                                                          (name)                                                               (repair organization's P .0. no., job. no.,etc.)
Nu.,,...c,....,,l.,,.e  
Foot of Buttonwoad Roodu Hanmc'ks Bridger NJ                                                                         08038 (address)
... e ...  
(name)
... sta ..... ""t""1""'
Foot of Buttonwood Road, Hancocks Bridge, N.J                                                                       08038 (address)
t=-. .. #c.:1,,__
: 3. Name, address and identification of nuclear power plant ___S.....,al....,,em                   ..........Nu.,,...c,....,,l.,,.e...e...r.....,Gen~,....era:""""...,t""ing......,~...sta
______ _ Foot of Bnttonwoad Bnadr Han<X>Cks Bridger NT 08038 4. System Safecy Inject.ion NuclAAr Class I 5. a: Component repaired, modified or replaced _.,J,,..2.._SJ..._J._7L-V....._...a
                                                                                                                                                                                                          .....""t""1""'o,,,,.._.n.___,U,,.m~*t=-...#c.:1,,___ _ _ _ _ __
.... J_,v .... e..__ ____________________________
Foot of Bnttonwoad Bnadr Han<X>Cks Bridger NT 08038
_ b: Name of manufacturer Roekwel 1 F'Jiwarrls c: Identifying nos. TVA TVA 1968 (mfr's. serial no.) (Narl.Bd.No.)
: 4. System              Safecy Inject.ion                                                                                                                                                                        NuclAAr Class I
aurisdictional no.) (other) (year built) d: Construction Code WE-Spec 677264 J\IA ANSI B31. 7 1969 MLtior1l.970 Add. (addenda) (Code Case(s)) (Code Class) 6. Section XI 1 983
: 5. a: Component repaired, modified or replaced _.,J,,..2.._SJ..._J._7L-V....._...a....J_,v....e..___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
... mnneuw.i=l"'L....-'8
b: Name of manufacturer                      Roekwel 1 F'Jiwarrls c: Identifying nos.       TVA                                      TVA                                                                                                                                                            1968 (mfr's. serial no.)                  (Narl.Bd.No.)                  aurisdictional no.)                                                        (other)                                                     (year built) d: Construction Code           WE-Spec 677264                                                                                                                        J\IA ANSI        B31. 7   1969 MLtior1l.970 Add.                             (addenda)                                                                        (Code Case(s))                                               (Code Class)
....... 3'-----------
: 6. Section XI                                  1 983                                    --~Si...mnneuw.i=l"'L....-'.......      83 ' - - - - - - - - - - -                                                                                  WA (edition)                                                                   (addenda)                                                                                                 (Code Case(s))
WA (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 (edition) (addenda) 1970 (Code Case(s)) *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 677264 (edition) (addenda) (Code Case(s)) 9. Design responsibilities
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                  1983                      S83                  ~N:,_./A~--
--'J.O!.IL.:l.lll!Ol...
(edition)                (addenda)            (Code Case(s))
_______________________________________
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                *1969                          1970                  N/A
_ 10. Tests conducted:
                                                                                                    *ANSI B31.7/N                                  E-Spec                      677264                    (edition)                     (addenda)              (Code Case(s))
hydrostatic D pneumatic D design pressure D **pressure NOF psi Code
: 9. Design responsibilities      --'J.O!.IL.:l.lll!Ol..._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 11. Description of work Replaced valve with valve of new design. (use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks:
: 10. Tests conducted: hydrostatic                    D      pneumatic      D      design pressure                D **pressure                                      NOF psi                    Code Case(s)_~J\or/~A~------
_
: 11. Description of work                Replaced valve with valve of new design.
......
(use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: _ __,W~n~rL'k'~_,_O~rrl      ......e~r._~#~*-9~2~1.....,_1~1~7~1~4~7,__ _ _ _ _ _ _ _ _ _.De                                          .......f~1~*c......ie....._n~cy'"l'-~R~e~po~.....rt-_._~#~*____.,N&#xa5;/4A~---------
__________ .De .......
Desi..gn Change Package #: lEP--2309 Pkg. 2 See attached pages for Description of Replacement.
......
                                          **    stem Inservice Test                                                                  '11
.....
* Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Desi..gn Change Package #: lEP--2309 Pkg. 2 See attached pages for Description of Replacement.
Certificate of Authorization no.                            36        to use the "NA" stamp expires                              Oct.                 3,               , 19-=9'-4=---
** stem Inservice Test '11
Date          /-/      y                                        PSE&G Co. -Nuclear Dept.
* Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19-=9'-4=---
19,---i.t.-. Signed_ _ _ _ _ _ _ _ _ _ _ _ ,;- </44<* dd+-4'
Date /-/ y PSE&G Co. -Nuclear Dept. /J / / 19,---i.t.-.
                                                                                                                                                                            /J / /                                                       Principal Engr.
Signed ____________
(repair organization)                                                                (authorized representative)                                                  (title)
,;-</44<* dd+-4' Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
CERTIFICATE OF INSPECTION
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co Of MA have inspected the repair, modification or replacement described in this report on /-1 , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of                New Jersey                    and employed by                            Arkwri                              t Mutual Insurance Co Of              MA            have inspected the repair, modification or replacement described in this report on                                                                      /-1                      , 19                    and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National
*Date /-)_' . 1'U...]_.
              ~ard rules as defined in the publicati~n                    NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Signe c. Commissions/J&f"ff$f:&#xa3;'/l/  
          *,.*:--o*,_.:.,*                  _C/ J                      ~                  r- /                                                                                                  Factory Mutual Engr. Assn.
,4 tJ1,?7,i *,.*:--o*,_.:.,*
          *Date /-)_'                    . 1'U...]_. Signe                                c. U-~-                                                        Commissions/J&f"ff$f:&#xa3;'/l/,4                                            tJ1,?7,i
_ C/ J r-/ Factory Mutual Engr. Assn. * (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) , .. **/ ..
                                                            *                                (Inspector)                                                                        (Natl.Bd.No.(including endorsements)state or province and number)
may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229 * ..
  ,. **/. ;*:>~-~~.form                may be obtained from The National Board of Boiler and Pressure Vessel Inspectors,                                                                    1055 Crupper Avenue, Columbus, OH 43229*
1:_ NB-81 Rev.6 Page of FORM NR-1 A'rl'ACHMENT Code Job Package No.: S93-182 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 2. owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 3. Location:
    . :::J*:*::.~1::.\,::';::t,,:*-                                                                                                                                                                                                                                        NB-81 Rev.6 1:_
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Safety Injection Nuclear Class:
 
-==============================================================================
Page ~ of ~
FORM NR-1 A'rl'ACHMENT Code Job Package No.: S93-182 Work performed by:        Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 2. owner:                    Public Service Electric & Gas Co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 3. Location:                  Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. System: Safety Injection                                        Nuclear Class: ~I~----
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd.         Jurist No.             Other     Year Built     ASME Code Stamp'd.?
Edition Addenda, Code Class __ ID of Replacement:
Original Const. Code:                                  Edition         Addenda, Code Class _ _
____________________
Code Cases: - - -
_ Name of Manufacturer:
ID of Replacement: --=1=2=S=J~1~7.__V~a==lv--=e,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Edward Valve Inc.
Name of Manufacturer: Edward Valve Inc.
AFX-54 N/A N/A 1993
                        ----=~~~----~'"""'-'~~~~~~~~~~~~~~~~~~~~~~
________ _ Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
AFX-54       N/A             =N~/=A;..,.-__        N/A        1993         =Y~e=s.___ _ _ _ _ _ _ __
Replacement Const. Code: *ASME III 1989 Edition NL.A_ Addenda, Code Class .l_ Code
Serial No. Nat'l. Bd. Jurist No.                     Other     Year Built     ASME Code Stamp'd.?
________________  
Replacement Const. Code: *ASME III 1989                   Edition NL.A_ Addenda, Code Class .l_
*ANSI B31.7 1969 Ed.1970 Add. ==============================================================================
Code Cases:_N_/~A~- ________________ ~~~~ ~~~~
*ANSI B31.7 1969 Ed.1970 Add.
==============================================================================
of Component Replaced:
of Component Replaced:
of Manufacturer:
of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Serial No. Nat'l. Bd.       Jurist No.             Other    Year Built    ASME Code Stamp'd.?
Original Const. Code:                                   Edition        Addenda, Code Class Code Cases: - - -
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No.                     Other   Year B,uilt     ASME Code Stamp'd.?
Edition Addenda, Code Class Other Year B,uilt Edition ASME Code Stamp'd.?
Replacement Const. Code:                                  Edition        Addenda, Code Class _
Addenda, Code Class _ ==============================================================================
Code Cases: - - -
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No* Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Serial No* Nat'l. Bd.       Jurist No.             Other    Year Built      ASME Code Stamp'd.?
Name of Manufacturer:  
Original Const. Code:                                   Edition        Addenda, Code Class _ _
'al No. Nat'l. Bd. Jurist No. acement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Code Cases: - - -
Edition Addenda, Code Class __ Other Year Built Edition ASME Code Stamp'd.?
ID of Replacement:
Addenda, Code Class _ ==============================================================================
Name of Manufacturer:
  'al No. Nat'l. Bd. Jurist No.                     Other   Year Built     ASME Code Stamp'd.?
acement Const. Code:                                  Edition         Addenda, Code Class _
Code Cases: - - -
==============================================================================


-------...... ; -FORM NR*1 REPORT OF REPAIR D MODIFICATION INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of 2 ork performed by publ i c Service El ectri c & C..as Co. -Nucl ear Dept. CIP :/tS93-183 (name) (repair organization's P.O. no., job. no.,etc.)
~----------------,--- -                                                    -----
Foot of Buttonwocd Rood, Hanr.ac;ks Bridge, N.J 08038 (address) (name) Foot of Buttonwcxxl Road, Hancocks Bridge, NJ 08038 (address)
  -        ...... ; - FORM NR*1 REPORT OF REPAIR D MODIFICATION ~OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of 2
: 3. Name, address and identification of nuclear power plant __ _.S..,al .....
ork performed by       publ     i c Service       El ectri c & C..as Co. - Nucl ear Dept.                                                                     CIP     :/tS93-183 (name)                                         (repair organization's P.O. no., job. no.,etc.)
Faat of Buttonwood.
Foot of Buttonwocd Rood, Hanr.ac;ks Bridge, N.J                                                         08038 (address)
Boadr Hanr.ocks Bridger N.J 08038 4. System Safety Injection Nuclear Class I 5. a: Component repaired, modified or replaced  
(name)
..........
Foot   of   Buttonwcxxl           Road,   Hancocks                 Bridge, NJ                       08038 (address)
l._.7_V.,._,a  
: 3. Name, address and identification of nuclear power plant _ __.S..,al                   .....em.....,~Nu.._._,,,,,,c"'l,,,.e,,.a..,r,__,Gen=~era==t,,,ing=,__,,sta:~=t=i=o=n,___,U=m=*t~~#=l'-------
... l_Vi_._,,,e,__
Faat of Buttonwood. Boadr Hanr.ocks Bridger N.J 08038
____________________________
: 4. System         Safety Injection                                                                                                                                           Nuclear Class I
_ b: Name of manufacturer Backwel 1 -Fdwarrls c: Identifying nos. N/A N/A (mfr's. serial no.) (Narl.Bd.No.)
: 5. a: Component repaired, modified or replaced ~l..,3..,SJ  ..........
d: Construction Code WE-Spec: 677264 ANSI B31. 7 1969 MUtioaJ970 Add. 6. Section XI 1983 (addenda)
l._.7_V.,._,a
N/A (jurisdictional no.) $J TIT1IT!f>r 8 3 (edition) (addenda)
                                                                                    ...l_Vi_._,,,e,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
N/A 1968 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
b: Name of manufacturer               Backwel 1 - Fdwarrls c: Identifying nos.     N/A                            N/A                                                    N/A                                         N/A                           1968 (mfr's. serial no.)         (Narl.Bd.No.)                           (jurisdictional no.)                                (other)                                    (year built) d: Construction Code         WE-Spec:         677264                                                                                           N/A ANSI B31. 7         1969 MUtioaJ970           Add.                 (addenda)                                                        (Code Case(s))                                (Code Class)
S83
: 6. Section XI                           1983                                                   $J TIT1IT!f>r 8 3                                                                                 N/A (edition)                                                               (addenda)                                                                     (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 *ANSI B31. 7 /N E-Spec 677264 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities  
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                     1983             S83            N:~/~A~--
-"'"""'""&G"""'------------------------------------------
(edition)         (addenda)      (Code Case(s))
: 10. Tests conducted:
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                 *1969                     1970            N/A
hydrostatic D pneumatic D design pressure D **pressure NoP psi Code
                                                                                *ANSI B31. 7/N E-Spec                                       677264             (edition)               (addenda)       (Code Case(s))
: 11. Description of work Replaced.
: 9. Design responsibilities - " ' " " " ' " " & G " " " ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
valve with valve of new design. (use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks:  
: 10. Tests conducted: hydrostatic D               pneumatic     D design pressure D **pressure NoP psi                                                             Code Case(s)_~N~/=A=--------
.......  
: 11. Description of work           Replaced. valve with valve of new design.
........
(use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: --WMo~*rkA~Ord~~e~r..._*#~*-9~2-l.l.1+7.1~4~9~~~~~~~~~-1)9&,,0;;.f_ic                                                    .......ie~nury"""i'--B~e~pa
                                                                                                                                                              ........~rr_..__~#~*-Nu,~l~A~~~~~~~~
Design Change Package i: lE0-2309 Pkg. 3 See attached pages for Description of Replacement.
Design Change Package i: lE0-2309 Pkg. 3 See attached pages for Description of Replacement.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19=9-'4'----
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Date / -I<( 19._!J_y_. Signed __ PS_E_&G __ c_o_. -_N_u_c_l_ear
Certificate of Authorization no.                 36     to use the "NR" stamp expires                           Oct.         3,             , 19=9-'4'----
__ De_pt_. __ .....
Date / -         I<(   19 ._!J_y_. Signed_ _PS_E_&G   __   c_o_.-_N_u_c_l_ear           _ _De_pt_.__                   .....d.~'L-~""""-~:.&~~"------Pr-incipal Engr.
incipal Engr. 7 (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
7 (repair organization)                                                     (authorized representative)                             (title)
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / ""/J , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.  
CERTIFICATE OF INSPECTION
/ >> Factocy Mutual Engr. Assn. Date J-Jl, , 19qt./ . Signed (. lA-v-L--Commissions/JJ'Sf1'/
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of           New Jersey             and employed by                                 Arkwri t Mutual Insurance Co of       MA           have inspected the repair, modification or replacement described in this report on                                                 / ""/J           , 19             and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
tA/A d:fJ/} (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The Nation al Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6
                                                                                  /         >>                                                             Factocy Mutual Engr. Assn.
,** Page _L of _.L FORM NR-1 ATTACHMENT Code Job Package No.: S93-183 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:
Date   J- Jl,         , 19qt./       . Signed       ~              (.         lA-v-L--                                   Commissions/JJ'Sf1'/                         tA/A d:fJ/}
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 system: Safety Iniection Nuclear Class:  
(Inspector)                                                         (Natl.Bd.No.(including endorsements)state or province and number)
============================================================================== ID of Component Replaced:
This form may be obtained from The Nation al Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
                    ~.
Page _L of _.L FORM NR-1 ATTACHMENT Code Job Package No.: S93-183 Work performed by:   Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 owner:               Public Service Electric & Gas Co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:             Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 system: Safety Iniection                           Nuclear Class: ~I~~~~-
~**;1
~{'      ==============================================================================
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd.             Jurist No.     Other  Year Built    ASME Code Stamp'd.?
Edition Addenda, Code Class ID of Replacement:
Original Const. Code:                               Edition        Addenda, Code Class Code Cases: - - -
ID of Replacement: _,:.1=3~S=J~1~7-'-~V~a=l~v~e::......~~~~~~~~~~~~~~--'-~~~~~~
Name of Manufacturer: Edward Valve Inc.
                                        -=~~~~==.......,"---'~~~~~~~~~~~~~~~~~~~~~
AFX-53              N/A          =N~/=A...,.___ N/A      1993        =Y~e=s"--~~~~~~~~....,,--
Serial No. Nat'l. Bd. Jurist-No.                  Other   Year Built   ASME Code Stamp'd.?
Replacement Const. Code: *ASME III 1989                Edition NLA__ Addenda, Code Class 1._
Code Cases:N/A
        *ANSI B31.7 1969 Ed.1970 Add.
        ==============================================================================
ID of Component Replaced:
      .illlllllllif    of Manufacturer:
      ~                      Nat'l. Bd. Jurist No.      Other  Year Built    ASME Code Stamp'd.?
Original Const. Code:                                Edition        Addenda, Code Class Code Cases: - - -
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
Edward Valve Inc.
Serial No. Nat'l. Bd. Jurist No.                 Other   Year Built   ASME Code Stamp.' d. ?
AFX-53 N/A N/A Serial No. Nat'l. Bd. Jurist-No.
      .Replacement Const. Code:                                Edition       Addenda, Code Class _
Other Replacement Const. Code: *ASME III 1989 Code Cases:N/A 1993 Year Built ASME Code Stamp'd.?
Code Cases: - - -
Edition NLA__ Addenda, Code Class 1._ *ANSI B31.7 1969 Ed.1970 Add. ==============================================================================
        ==============================================~===============================
ID of Component Replaced: .illlllllllif of Manufacturer: Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. .Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp.' d. ? Addenda, Code Class _
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd.             Jurist No.     Other   Year Built   ASME Code Stamp'd.?
Edition Addenda, Code Class ------------------------------------------------------------------------------
Original Const. Code:                                Edition       Addenda, Code Class Code Cases: - - -
ID of Replacement:
ID of Replacement:
Name of Manufacturer:  
Name of Manufacturer:
'al No. Nat'l. Bd. Jurist No. acement Const. Code: Other Year Built Edition ASME Code Stamp'd.?
                  'al No. Nat'l. Bd. Jurist No.           Other   Year Built   ASME Code Stamp'd.?
Addenda, Code Class _
acement Const. Code:                        Edition      Addenda, Code Class _
r:;=======----*----* . -* .. FORM NR-1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT($)
        ======~=======================================================================
0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 ork performed by pnbl i c Send cp El ec+/-ri c & C'..as Co -Nuclear Dept. CIP f593-184 (name) (repair organization's P .0. no., job. no.,etc.)
 
Foot of Buttonw'ood Road, Hancocks Bri dgeJ NI 08038 (address) (name) Foot of ruttonwood.
r:;=======----*----*             . -*
Rbad, Hancocks Eri.dqe. NJ 08038 (address)
        ~ .. FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT($) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 ork performed by       pnbl i c Send cp El ec+/-ri c                                 &     C'..as           Co               -       Nuclear Dept.                                                       CIP f593-184 (name)                                                               (repair organization's P .0. no., job. no.,etc.)
: 3. Name, address and identification of nuclear power plant __ _.s..,a ....... l...,em....._  
Foot of Buttonw'ood Road, Hancocks Bri dgeJ NI                                                                                 08038 (address)
.... Nu....,c.,..l  
(name)
... e,,..;:i.,....,r._,,Gen..,.,, ....  
Foot of       ruttonwood. Rbad, Hancocks Eri.dqe.                                                           NJ                 08038 (address)
...  
: 3. Name, address and identification of nuclear power plant           _ __.s..,a                                                                             ....era,,.,,.,~t...inq......,~...
... s...,,ta......,t.,.1..,'  
                                                                                                    .......l...,em....._....Nu....,c.,..l...e,,..;:i.,....,r._,,Gen..,.,,                         s...,,ta......,t.,.1..,'o.,.n...___,,,U~m..,'=:t=-.....#_,.l,_________
..... #_,.l,__ ______ _ FCXJt of Bnttanwood Road, Hanccx:ks Bridge, NT 08038 4. System Safecy Injection Nuclear Class I 5. a: Component repaired, modified or replaced _l..,4,.,S....,.J_.l_.7--'V.  
FCXJt of Bnttanwood Road, Hanccx:ks Bridge, NT                                                                                 08038
.... a ... J .... y,_,._,_e,__
: 4. System         Safecy Injection                                                                                                                                                                                           Nuclear Class I
____________________________
: 5. a: Component repaired, modified or replaced _l..,4,.,S....,.J_.l_.7--'V.....a...J....y,_,._,_e,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
_ b: Name of manufacturer Ro<:::krAre] l -F.dwarr'ls c: Identifying nos. NjA N,LA N/A N/A .1968 serial no.) (Narl.Bd.No.)
b: Name of manufacturer             Ro<:::krAre] l - F.dwarr'ls c: Identifying nos. NjA                             N,LA                                                                         N/A                                                       N/A                                               .1968 (mf~s. serial no.)           (Narl.Bd.No.)                                     Ourisdictional no.)                                                         (other)                                                             (year built) d: Construction Code       W   E-Spec 677264                                   N/A                                                                                           N/A ANSI B31. 7       1969 flidJtio!l}970 Add.                       (addenda)                                                                                     (Code Case(s))                                                           (Code Class)
Ourisdictional no.) (other) (year built) d: Construction Code W E-Spec 677264 N/A N/A ANSI B31. 7 1969 flidJtio!l}970 Add. (addenda) (Code Case(s)) (Code Class) 6. Section XI 1983 Srlllmler 83 N/A (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) 583
: 6. Section XI                         1983                                                             Srlllmler 83                                                                                                                                         N/A (edition)                                                                               (addenda)                                                                                                       (Code Case(s))
__ (addenda) 1970 (Code Case(s)) *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/.N E-Spec 677264 (edition) (addenda) (Code Case(s)) 9. Design responsibilities
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                             1983                       583                      ?{~/A...__ _
____ -,-------------------------------------
(edition)                 (addenda)               (Code Case(s))
: 10. Tests conducted:
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                       *1969                              1970                      N/A
hydrostatic D pneumatic D design pressure D **pressure NOP psi Code
                                                                                *ANSI B31.7/.N E-Spec 677264                                                                                             (edition)                         (addenda)                 (Code Case(s))
: 11. Description of work Repl aced valve with va]ve of new design. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)  
: 9. Design responsibilities ---1;~.:dl!l!,,;[__ _ _ _- , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
** CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current.edition.  
: 10. Tests conducted: hydrostatic D             pneumatic     D design pressure D **pressure NOP psi                                                                                                       Code Case(s)_~N;~/=A~------
*Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, *, 19-=9'--'4=----(title). (repair organization) 7 (authorized representative)
: 11. Description of work         Repl aced valve with va]ve of new design.
Principal Engr. Date i-J 4 PSE&G Co.-Nuclear Dept.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
Signed _______________
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current.edition.
_ CERTIFICATE OF INSPECTION
    *Certificate of Authorization no.                 36       to use the "NR" stamp expires                                               Oct. 3,                           *, 19-=9'--'4=----
_I, the undersigned, *holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /""' // , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National B d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Signed_ _PSE&G _ _ _ Co.-Nuclear                                          Dept.                                                                                                                 Principal Engr.
Date / -J.G , 1 Signe  
Date     i- J 4     19,~.                                     _______                                                _ _ __
&#xa3;:(/ '{. kM ........-*
7 (repair organization)                                                                                  (authorized representative)                                                            (title).
Commissions  
CERTIFICATE OF INSPECTION
!i/fSf?'/
_I, the undersigned, *holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of         New Jersey               and employed by                                               Arkwri t Mutual Insurance Co of       MA           have inspected the repair, modification or replacement described in this report on                                                                                 /""' //                         , 19                   and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National B d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, q                      //
:Ct! t1 11J.f f 1} r,1, / q / / n Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Page _L of _L FORM NR-1 ATTACHMENT Code Job Package No.: S93-184 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:
ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. system: Safety Injection Nuclear Class:  
r,1, /                                                                        n                                                                                Factory Mutual Engr. Assn.
Date   / -   J.G ,1~* Signe                   ~~.a?'\ &#xa3;:(/ '{.                       kM . . . . -*                                                 Commissions                   !i/fSf?'/ :Ct!t1 11J.f f 1}
(Inspector)                                                                                         (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
Page _L of _L FORM NR-1 ATTACHMENT Code Job Package No.: S93-184 Work performed by:   Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner:               Public Service Electric & Gas Co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:           Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. system: Safety Injection                         Nuclear Class: --=I"--~~~-
==============================================================================
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No. Other   Year Built     ASME Code Stamp'd.?
Edition Addenda, Code Class ID of Replacement:
Original Const. Code:                      Edition       Addenda, Code Class Code Cases: - - -
Name of Manufacturer:
ID of Replacement: --=1~4=S=J~1~7""-~V~a=l~v~e:::;.,....~~~~~~~~~~~~~~~~~~~~~~
AFX-52 .N/A N/A 1993 Serial No. Nat'l. Bd. Jurist No. Other Replacement Const. Code: *ASME III 1989 Year Built ASME Code Stamp'd.?
Name of Manufacturer: .....;:E~d~w~a~r=-=d~V~a~l~v~e=-=I~n~c~*~~~~~~~~~~~~~~~~~~-
Edition NLA_ Addenda, Code Class .l_ Code Cases:N/A  
AFX-52     .N/A         =N~/=A.____  N/A      1993         ~Y=e=s'--------~~-
*ANSI B31.7 1969 Ed.1970 Add. ==============================================================================
Serial No. Nat'l. Bd. Jurist No.       Other   Year Built     ASME Code Stamp'd.?
Replacement Const. Code: *ASME III 1989      Edition NLA_ Addenda, Code Class .l_
Code Cases:N/A
*ANSI B31.7 1969 Ed.1970 Add.
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
of Manufacturer:
of Manufacturer:
ial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
ial No. Nat'l. Bd. Jurist No. Other    Year Built    ASME Code Stamp'd.?
Original Const. Code:                     Edition        Addenda, Code Class Code Cases: - - -
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No.       Other   Year Built     ASME Code Stamp'd.?
Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?
Replacement Const. Code:                      Edition       Addenda, Code Class _
Addenda, Code Class _ ==============================================================================
Code Cases: - - -
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Serial No. Nat'l. Bd. Jurist No. Other    Year Built    ASME Code Stamp'd.?
Name of Manufacturer:
Original Const. Code:                      Edition        Addenda, Code Class Code Cases: - - -
'al No. Nat'l. Bd. Jurist N6. acement Const. Code: Other Year Built ASME Code Stamp'd.?
ID of Replacement:
Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?
Name of Manufacturer:
Addenda, Code Class _ ==============================================================================
  'al No. Nat'l. Bd. Jurist N6.      Other    Year Built    ASME Code Stamp'd.?
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)
acement Const. Code:                      Edition      Addenda, Code Class _
!]' TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS f Pa e 1 o 1 ork performed by Pnblic Service Electric & Gas Co -
==============================================================================
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) !]'
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS                                                                                                                                                                  f Pa e 1 o 1 ork performed by      Pnblic              Service                    Electric & Gas Co                                  - Nucl ear Dept                                                          CJP #893-190 (name)                                                          (repair organization's P.0. no., job. no.,etc.)
Foot    of Buttonwood                      Road,                Hancxx:ks              Bridge,            NT            08038 (address)
(name)
Foot    of  Buttonwood Road, Hancocks                                                Bridge,              NJ            08038 (address)
: 3. Name, address and identification of nuclear power plant _ ___.S..,a                              ....l...em_,,._.,Nu~c....l..e,,.e,,,_r'-"Gen.,,.,.""era,,,,..,.._,,t..,ing~,,___,S""ta""""'._.t~i'&deg;'o""n._.____,,U"'Ill...,',,__t=-..u.#-=1,___ _ _ _ _ __
Foot of l311ttonwood Road, Hanc.cx:ks Bridge, NT 08038
: 4. System        Fuel Transfer system                                                                                                                                                                              Nuclear Class II 5.~ Componentrepa~~.modffiedorre~aced~-~~e~l~~~~n~s~~~e~.r~~~s~~
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
Public Service Electric and Gas co. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant                                Salem Nuclear Generating Station                                                    Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NI                                                            08038
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Steam/Turl:>ine Bypass Nuclear Class II 5.
: 4. System        Residual          Heat        Removal                                                                                                                    Nuclear Class I I 5.~ Compoo~tre~~d.m~ffi~orre~oc~_l~2~~~1~8~&#xa5;~a~.l~v~e~-----------------------------
__ 2_0_0 ___________________________ b: Name of manufacturer
b: Name of manufacturer _ _.._._..,.,_..........__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
_
c: Identifying nos. 11319                                        Nil>,
c: Identifying nos. N/A N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)
I                                      JVA                                          JVA                        1988 (mfr's. serial no.
d: Construction Code ANSI B31. 7 1969 6. Section XI (edition) 1983 Uurisdictional no.) 1970 (addenda) summer 83 (edition) (addenda) (other) N/A (Code Case(s)) 1983 (year built) II (Code Class) N-416 (Code Case(s)) S83 N-416 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: -----(edition)
*1969 (edition) (addenda) (Code Case(s)) 1970 N-416 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31. 7 -----(addenda) (Code Case(s)) 9. Design responsibilities
-=PS=E=.:&G=-------------
==============================================================================
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No. Other     Year Built     ASME Code Stamp'd.?
Edition Addenda, Code Class ID of Replacement:
Original Const. Code:                    Edition         Addenda, Code Class Code Cases: - - -
Pressurizer Manway Cover Name of Manufacturer:
ID of Replacement: Pressurizer Manway Cover Name of Manufacturer: _,._W~e~s_t_i~*n~g_h~o~u=s~e~~---------------------
C42744 N/A N/A 1987 =N=o;.__ ________ Serial No. Nat'l. Bd. Jurist No. Other Replacement Const. Code: ASME III 1983 Year Built ASME Code Stamp'd.?
C42744       N/A         N/A         =N~/=A,__  1987         =N=o;.___ _ _ _ _ _ _ _~
Edition S83_ Addenda, Code Class .l_ Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add. ==============================================================================
Serial No. Nat'l. Bd. Jurist No.     Other     Year Built     ASME Code Stamp'd.?
Replacement Const. Code: ASME III 1983        Edition S83_ Addenda, Code Class .l_
Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add.
==============================================================================
of Component Replaced:
of Component Replaced:
of Manufacturer:
of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Serial No. Nat'l. Bd. Jurist No. Other    Year Built    ASME Code Stamp'd.?
Original Const. Code:                     Edition        Addenda, Code Class Code Cases: - - -
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No.     Other     Year Built     ASME Code Starnp'd.?
Edition Addenda, Code Class Other Year Built Edition ASME Code Starnp'd.?
Replacement Const. Code:                      Edition       Addenda, Code Class _
Addenda, Code Class _
Code Cases: - - -
===========~==========================================================~=======
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Serial No. Nat'l. Bd. Jurist No. Other    Year Built    ASME Code starnp'd.?
Original Const. Code:                     Edition        Addenda, Code Class Code Cases: - - -
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
Nat'l. Bd. Jurist No. acement Const. Code: Other Year Built ASME Code starnp'd.?
Nat'l. Bd. Jurist No. Other     Year Built     ASME Code Starnp'd.?
Edition Addenda, Code Class Other Year Built ASME Code Starnp'd.?
acement Const. Code:                      Edition       Addenda, Code Class _
Edition Addenda, Code Class _ Code Cases: ---==============================================================================  
                          --------~-
-----------
Code Cases: - - -
FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) lEJ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS *ark performed by PIIDlic Sm:vice Electric & Gas Co. -Nuclear Dept. (name) Foot of Buttonwood Road, Hancocks Bridge, m 08038 (address)
==============================================================================
: 2. Owner Public Service Electric anC! Gas Co. {name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 {address)
 
CJP #S93 260 (repair organization's P .0. no., job. no.,etc.)
FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) lEJ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS ark performed by       PIIDlic Sm:vice Electric & Gas Co. - Nuclear Dept.                                                             CJP #S93 260 (name)                               (repair organization's P.0. no., job. no.,etc.)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Upjt #J Foot of Buttonwood Road, Hancocks Bridge, ID 08038 4. System Reactor Coolant N'11clear Class II 5. a: Component repaired, modified or replaced Pressurizer Relief Tank-Flanges-lRCEll b: Name of c: Identifying nos. Ir-10662 61420 {mfr's. serial no.) (Nat'l.Bd.No.)
Foot of Buttonwood Road, Hancocks Bridge,                                         m       08038 (address)
d: Construction Code ASME III 1968 ANSI B31. 7 1969 Add. 6. Section XI 1983 {edition)
: 2. Owner       Public Service Electric anC! Gas Co.
N/A uurisdictional no.) N/A (addenda) (addenda)
{name)
N/A 1969 {other) {year built) N/A (G) 2 (Code Case(s)) {Code Class) N/A {Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
Foot of Buttonwood Road, Hancocks Bridge, NJ                                               08038
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1989 *ASME III/ANSI B31. 7 1969 Ed. 1970 Add. (edition) 883 N,rl=A---(addendaJ (Code Case{s)) 89 NIA {bode Case{s)) (addenda)
{address)
: 9. Design responsibilities
: 3. Name, address and identification of nuclear power plant                 Salem Nuclear Generating Station                                       Upjt     #J Foot of Buttonwood Road, Hancocks Bridge, ID 08038
_____________________________________
: 4. System       Reactor Coolant                                                                                                                     N'11clear Class II
_ 10. Tests conducted:
: 5. a: Component repaired, modified or replaced       Pressurizer Relief Tank-Flanges-lRCEll b: Name of manu~acturer --'lwi/<f=='es~t,,.iJOfngh-kHcfl9C=JUStfht:C!-----------------------------------
hydrostatic D pneumatic D design pressure &deg;** pressure NOP psi Code
c: Identifying nos. Ir-10662                          61420                                    N/A                               N/A                         1969
: 11. Description of work Replace pressurizer
{mfr's. serial no.)         (Nat'l.Bd.No.)                uurisdictional no.)                    {other)                                  {year built) d: Construction Code        ASME III 1968                            N/A                                            N/A                                     (G) 2 ANSI B31. 7          1969 F.cfl.ditis_~70 Add.                    (addenda)                                      (Code Case(s))                           {Code Class)
:r:elief tank rupture disc flanges -vrith upgraded (use of additional sheet(s) or sketch{ es) is acceptable if properly identified)
: 6. Section XI                        1983                                                                                                                              N/A
NIA I CERTIFICATE OF COMPLIANCE We certify that the statements made ,in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct 3 1 ,
{edition)                                                  (addenda)                                                      {Code Case(s))
? Principal Engr. Date !-I 4 19 ,--2._L. Signed __ PS_E_&G __ c_o_._-_N_u_c_l_ear
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                           1983           883                N,rl=A---
__ De_p_t_. __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
(edition)        (addendaJ        (Code Case{s))
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New .Jersey and employed by ___
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                         *1989               89                NIA
ot MA have inspected the repair, modification or replacement described in this repart*an and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Bciard rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner tor any personal injury or property damage or a loss of any kind arising from or connected with this inspection.  
                                                      *ASME III/ANSI B31. 7                   1969       Ed. 1970     Add.         (edition)           (addenda)         {bode Case{s))
....
: 9. Design responsibilities   -E>~oo..,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
__ , 1u.i__.  
: 10. Tests conducted: hydrostatic          D      pneumatic    D      design pressure          &deg;**    pressure      NOP        psi      Code Case(s)_N..,,.,+l~A-----------
'L* CommissionsN[frCjl/
: 11. Description of work          Replace pressurizer :r:elief tank rupture disc flanges -vrith upgraded (use of additional sheet(s) or sketch{ es) is acceptable if properly identified)
WI/ Jl,t[f/} /,I , I i* /' I 11 :i;;as:::t;o:cy J1q.tual Engr..., . Assn. * (Inspector) (Natl.Bd.No.{including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR*1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)fe:j TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by
NIA I
___ _ (name) (repair organization's P.O. no., job. no.,etc.)
CERTIFICATE OF COMPLIANCE We certify that the statements made ,in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Foot of Buttonwocx:l Road, Hancocks Bridge, NJ. 08038 (address) (name) Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 (address)
Certificate of Authorization no.                 36     to use the "NR" stamp expires             Oct     31          , 1~-=4~--
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generatirig Station Unit #1 Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 4. System Reactor Coolant Nuclear Class I
Date   !-   I 4       19 ,--2._L. Signed _ _PS_E_&G     __c_o_._-_N_u_c_l_ear   __     De_p_t_._ _                                                      Principal Engr.
__
                                                                                                                ?
__ era __ t_o_r ________________________
(repair organization)                               (authorized representative)                           (title)
_ b: Name of manufacturer Westinghouse c: Identifying nos. 1203 68-51 N/A (mfr's. serial no.) (Nat'l.Bd.No.)
CERTIFICATE OF INSPECTION
uurisdictional no.) d: Construction Code ASME Sec. III 196=5 __
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of         New .Jersey             and employed by _ _ _--L:l~Ulll..1~4LJJL-..JL!!U..1.U1C....1-LI..Ji::u..L.LLl......._....._-"'4"'-7-l----------
: 6. Section XI (edition) 1983 (addenda)
ot      MA            have inspected the repair, modification or replacement described in this repart*an                                                          and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Bciard rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
SUrrnner 83 (edition) (addenda) 1971 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
                            /,I , I Date~/_....~/~?__ , 1u.i__. Signed~
S83 (addenda)
i* /'
S66 (Code Case(s)) N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME Sec. III *1965 (edition) (addenda) (Code Case(s)) 9. Design responsibilities
any manner tor any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
__ PSE __ &G ________________________________________
                                                                'L* ~
_ 10. Tests conducted:
I 11 (Inspector)
hydrostatic D pneumatic D design pressure D *l'fressure N/A psi Code Case(s) __
CommissionsN[frCjl/
Replace (1) bolt in kind from folio on #14 Steam Generator (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
:i;;as:::t;o:cyJ1q.tual Engr..., . Assn.
: 12. Remarks: _ __,W_,_,,o=r=k"--"'O=rd=er=--
WI/ Jl,t[f/}
..... #_._:---=9=3_,.,1"""'1"""0""'5=-0=33..__
(Natl.Bd.No.{including endorsements)state or province and number)
_________
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
De __ f.._1.,..'
NB-81 Rev.6
c ..... 1...,'
 
.........
FORM NR*1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)fe:j TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by ---=Pub-==l=i=c'--=S=erv~-=i=ce'-=---=E=l=ectr===i=c'--"&,__,,Gas=~Co=._--=Nu==c=l=e=a=tr'--=De'=.l:'p-=t=*------=CJP=-==____..#_,,,S=9-=3'---=2=6=2,___ _ __
Desiqn Change Package #: N/A Rev. N/A See attached pages for Description of Replacement.
(name)                                    (repair organization's P.O. no., job. no.,etc.)
N/A ** stem Inservice Test @ NOP or CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, ,
Foot of Buttonwocx:l Road, Hancocks Bridge, NJ. 08038 (address)
Date I -J Cf 4 v PSE&G Co. -Nuclear Dept. / / /
(name)
* 19,_L_f-*
Foot of Buttonwocx:l Road, Hancocks Bridge, NJ                                                            08038 (address)
Signed __________ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on II ' 19 L and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
: 3. Name, address and identification of nuclear power plant                                    Salem Nuclear Generatirig Station                                            Unit #1 Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038
C /  
: 4. System          Reactor Coolant                                                                                                                                          Nuclear Class I 5.~ Componemrepa~ed,modffiedmre~~ed __                                 #_1_4_._S_~---~          __  era
)1utual Assn. Date /-J.Y-'1,jL.
__t_o_r_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
c.. C/-vk Commissions tJfi:I.r'i tf .J.AIA ;JJ} n ,. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 *rk performed by Public Service Electric & Gas CO. -Nuclear Dept. CJP #893-266 (name) (repair organization's P.O. no., job. no.,etc.)
b: Name of manufacturer                Westinghouse c: Identifying nos.      1203                                            68-51                                  N/A                                                                 1971 (mfr's. serial no.)                    (Nat'l.Bd.No.)                   uurisdictional no.)                           (other)                                 (year built) d: Construction Code          ASME      Sec. III 196=5_ _~S,..../_,,,1=9-=6=6,___                                                            N/A (edition)                                     (addenda)                                             (Code Case(s))                         (Code Class)
: 6. Section XI                            1983                                                        SUrrnner      83                                                                          N/A (edition)                                                                  (addenda)                                                            (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                       1983          S83            _N=---/~A~_
(edition)       (addenda)       (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                 *1965                S66                N/A
                                                                                            *ASME Sec. III                                                  (edition)           (addenda)         (Code Case(s))
: 9. Design responsibilities __PSE  __&G  _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic D                pneumatic                  D        design pressure D *l'fressure                            N/A psi        Code Case(s) _ _=N,,./~A~-----
Replace (1) bolt                                in kind          from folio on #14 Steam Generator (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: _ __,W_,_,,o=r=k"--"'O=rd=er=--.....
                                                #_._:---=9=3_,.,1"""'1"""0""'5=-0=33..___ _ _ _ _ _ _ _ _De                __f.._1.,..'c..... en~cy."'r--~R~e~po 1...,'          .........rt~....,#~:~~or-/~A~-------
Desiqn Change Package #: N/A                                                              Rev. N/A See attached pages for Description of Replacement.                                                                            N/A
                        **    stem        Inservice Test                              @NOP or CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                      36            to use the "NR" stamp expires                    Oct. 3, , 19_9_4_~
4 v                              PSE&G Co. -Nuclear Dept.                                              / / /
* Principal Engr.
Date      I - J  Cf    19,_L_f-* Signed_ _ _ _ _ _ _ _ _ _ ~
(repair organization)                                      (authorized representative)                          (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of            New Jersey and employed by                                                  Arkwri t Mutual Insurance Co of         MA        have inspected the repair, modification or replacement described in this report on                                                /~  II          ' 19 L      and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
C        /                                                            F~~o:cy )1utual ~. Assn.
Date      /-J.Y-      '1,jL.          Signed~ c..                                          C/-vk                          Commissions              tJfi:I.r'i tf        .J.AIA ;JJ}        n
                                                    ,.                            (Inspector)                                            (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)                                                                                0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 rk performed by          Public Service Electric & Gas CO. -                                    Nuclear Dept.                        CJP #893-266
*                                                                                              (name)                              (repair organization's P.O. no., job. no.,etc.)
Foot of Buttonwood Road,                    Hancocks            Bridge, NJ 08038 (address)
Public Service Electric and Gas Co.
(name)
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
Public Service Electric and Gas Co. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant                  Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Reactor Coolant Nuclear Class II
: 4. System          Reactor Coolant                                                                                                                  Nuclear Class I I 5.~ Componentrepa~ed,modffiedorre~aced_1_~                __8_1_-_&#xa5;_~_v_e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
__
b: Name of manufacturer _ _. . . . : A l = = - = O ' - L - - ' C O = = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
___________________________
c: Identifying nos.      70/A627-3                      N/A                                    N/A                              N/A                          1970 (rnfr's. serial no.)        (Nat'l.Bd.No.)                Uurisdictional no.)                    (other)                                  (year built) d: Construction Code          WE-Spec G-67624~1~-~R~e~'V~*~l_ _                                                        N/A                                    II ANSI B31. 7 1969 ~i6lnJl970 Add.                            (addenda)                                      (Code Case(s))                          (Code Class)
_ b: Name of manufacturer
: 6. Section XI                            1983                                     
__ ....:Al==-=O'-L--'CO==-------------------------------------
c: Identifying nos. 70/A627-3 N/A N/A (rnfr's. serial no.) (Nat'l.Bd.No.)
Uurisdictional no.) (other) d: Construction Code WE-Spec
__ N/A ANSI B31. 7 1969 Add. (addenda)
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Edition--""'"!
Serial No. Nat'l. Bd.                       Jurist No.           Other      Year Original Const. Code:                                                   Edition--""'"!
Code Cases:
          ~~-~~-;~~~~~~~~~~~------------------------------~~::;~~
Name of Manufacturer:
Name of Manufacturer:
ial No. Nat'l. Bd. Jurist No. lacement Const. Code: Code Cases: ---Other ==============================================
ial No. Nat'l. Bd. Jurist No.                             Other lacement Const. Code:
' FORM NR*1 REPORT OF REPAIR D OR INSTALLATION OF REPLACEMENT(S)
Code Cases: - - -
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pae 1 of 2 *ork performed by Public Service Electric:  
          ==============================================
& Gas Co -Nuclear Dept GIP #PS92-D41  
 
-7 * (name) (repair organization's P .0. no., job. no.,etc.) . Foot of Buttonwood Road, Hancocks Bridge, Iil 08038 (address) (name) Foot of Buttonwocd Road, Hanccx:ks Bridge, NT 08038 (address)
                    ' FORM NR*1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D
: 3. Name, address and identification of nuclear power plant Sal em NJJCl ear C'..enerati ng stat i an Unit :jfl Foot of Buttonwood Road, Han.cocks Bridge, Jil 08038 4. System Reactor Coolant Nuclear Cl ass I 5. a: Component repaired, modified or replaced
              ,.~,,                      TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
_____________________________
                      *'~                                                                                                                                                                                        Pae 1 of 2 ork performed by             Public Service Electric:                                                       &   Gas Co         - Nuclear Dept                                     GIP #PS92-D41
_ b: Name of manufacturer c: Identifying nos. -N ....  
                            - 7             *                                                                                       (name)                                       (repair organization's P.0. no., job. no.,etc.)
.. (mfr's. serial no.) N/A (Nat'l.Bd.No.)
*            . Foot of Buttonwood Road, Hancocks Bridge, Iil                                                                                 08038 (address)
N/A Qurisdictional no.) d: Construction Code Spec 69-6430 :Rev-. (edition) (addenda)
(name)
: 6. Section XI 1983 (edition) (addenda) (other) N/A (Code Case(s)) 1974 (year built) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1 983 (edition)  
Foot of Buttonwocd Road, Hanccx:ks Bridge, NT                                                                                 08038 (address)
$83 (addenda) (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *S-C-MBX>-MI:s-043 N;f A (edition) ( addenda) (Code Case(s)) 9. Design responsibilities  
: 3. Name, address and identification of nuclear power plant                                                         Sal em NJJCl ear C'..enerati ng stat i an                                       Unit       :jfl Foot of Buttonwood Road, Han.cocks Bridge, Jil 08038
-&u."""';z_-----------------------------------------
: 4. System         Reactor Coolant                                                                                                                                                                 Nuclear Cl ass I
: 10. Tests conducted:
: 5. a: Component repaired, modified or replaced                         ...1IL.>C..:-::::;PR~J.JHi;:::-::..Jl._7,__7,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
hydrostatic D pneumatic D design pressure D** pressure N/A psi Code Case(s) _ _,N_.,,F/A""'-------
b: Name of manufacturer -----,!;<a,ie.ei~-------------------~-----------------
: 11. Description of work Merli fi cation of pipe suppart (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
c: Identifying nos.       -N..../~A~.. - - - - -                              N/A                                                    N/A                                      N/A                              1974 (mfr's. serial no.)                       (Nat'l.Bd.No.)                                   Qurisdictional no.)                      (other)                                            (year built) d: Construction Code               Spec           69-6430           :Rev-.-5~-,j,ljN~/~Ao-----                                                            ~IA (edition)                                             (addenda)                                      (Code Case(s))                                          (Code Class)
: 12. Remarks:  
: 6. Section XI                                 1983                                                                                                                                                                     N/A (edition)                                                                                 (addenda)                                                                 (Code Case(s))
..... :--7796'2'd0e-80..,,5dcl=-1=-7+------------.De......,f0=1..,..*  
: 7. Applicable edition of ASME Code Section XI                         under which repairs, modifications, or replacements were made:                                               1 983             $83              N;~/A~*---
... n-c;_,,__r  
(edition)           (addenda)         (Code Case(s))
.... e""po""""':ct.--41#-*-N>r-/A  
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                               N;f A            ~N;~/~A~--
...
                                                                                                          *S-C-MBX>-MI:s-043                                                         (edition)             (addenda)         (Code Case(s))
Desi gn Change Package #* lEC-3168 O
: 9. Design responsibilities - & u . " " " ' ; z _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
* See atta9hPd pages far Description  
: 10. Tests conducted: hydrostatic D                               pneumatic           D design pressure D** pressure N/A psi                                                           Code Case(s) _ _,N_.,,F/A""'-------
** CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires act. 3, ,
: 11. Description of work               Merli fi cation                     of         pipe suppart (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
Date/ 2
*r--~~~~~~~~
* 3 c;.., PSE&G Co.-Nuclear Dept. 11 / / * / 19,___L,,,2__.
: 12. Remarks: ---&#xa5;&#xa5;~lo7.tr~k,._._...o.,,,,m~eo:r,.....-'fl#.....:--7796'2'd0e-80..,,5dcl=-1=-7+------------.De......,f0=1..,..*c~i""ei                    ...n-c;_,,__r..,.,~....e""po""""':ct.--41#-*-N>r-/A
Signed __________ <"4.<A6-'
                                                                                                                                                                                                            ...~.,--------
Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
Desi gn Change Package #* lEC-3168                                                                                       O
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by i Mutual urance Co of MA have inspected the repair, modification or replacement described in this report on ::J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, essed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property age-or a loss of any kind arising from or connected with this inspection.
* See atta9hPd pages far Description CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
I Factory....,Mutual Engr. Assn. Date I 2. I Y . 19 '/ J . Signed b_ f Commissions p 4 2-0-5 f:1 .lj I 0 J I J tUT If 3 / r (Inspector) (Natl.Bd.No.(including endorsements)state or province and rfU!l;ber)
Certificate of Authorization no.                                 36       to use the "NR" stamp expires                                 act. 3,           , 199~4~--
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Page J_ of _L FORM NR-1 ATTACHMENT Code Job Package No.: PS92041 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 2. Owner: Public Service Electric & Gas co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 3. Location:
Date/     2
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4.
* 3                 c;..,                               PSE&G Co.-Nuclear Dept.
Chemical Volume Control Nuclear Class:  
19,___L,,,2__. Signed _ _ _ _ _ _ _ _ _ _ .~ <"4.<A6-'
                                                                                                                                                      ~    11 /            / * /                          Principal Engr.
(repair organization)                                         (authorized representative)                                         (title)
CERTIFICATE OF INSPECTION
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of               New Jersey                         and employed by                                                   i     Mutual                           urance Co of       MA             have inspected the repair, modification or replacement described in this report on                                                                                               ::J     and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, essed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property                                       age-or a loss of any kind arising from or connected with this inspection.
Factory....,Mutual Engr. Assn.
Date   I 2. I r
IY .           19 '/   J . Signed b_ f (Inspector)
Commissions       p4              2-0-5 f:1 .lj I 0 J I J tUT If 3 /
(Natl.Bd.No.(including endorsements)state or province and rfU!l;ber)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
Page J_ of _L FORM NR-1 ATTACHMENT Code Job Package No.: PS92041 Work performed by:   Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 2. Owner:               Public Service Electric & Gas co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 3. Location:             Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. Syst~m:  Chemical Volume Control                 Nuclear Class: --=I=I~~~~
==============================================================================
==============================================================================
ID of Component Replaced: __,::1~-~C~V~C=A=---=6=5=3~~~~~~~~~~~~~~~~~~~~~
Name of Manufacturer: PSE&G
                      -=-=-~=-~~~~~~~~~~~~~~~~~~~~~~~~~
N/A          N/A          =N~/=A..___~  N/A      1980        =N~/A=-----------
Serial No. Nat'l. Bd. Jurist No.        Other  Year Built    ASME Code Stamp'd.?
Original Const. Code: Spec 69-6445 Rev9 Edition N/A        Addenda, Code Class J.I__
Code Cases: N/A ID of Replacement: --=i~-~C~V~C=A~--6~5~3~~~~~~~~~~~~~~~~~~~~~~~
Name of Manufacturer: PSE&G
                      -=-=-~=-~~~~~~~~~~~~~~~~~~~~~~~~~
N/A          N/A          N/A          N/A      1993        =N~/=A'---------~
Serial No. Nat'l .. Bd. Jurist No.      Other  Year Built    ASME Code Stamp'd.?
Replacement Const. Code: Spec S-C-MBOO-MDS Edition NL.A_ Addenda, Code Class II Code Cases:N/A            -043_ ~-- _ _ __
==================================================================~===========
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
PSE&G N/A N/A N/A 1980 Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
al No. Nat'l. Bd. Jurist No. Other   Year Built   ASME Code Stamp'd.?
Original Const. Code: Spec 69-6445 Rev9 Edition N/A Addenda, Code Class J.I__ Code Cases: N/A ------------------------------------------------------------------------------
ginal Const. Code:                       Edition       Addenda, Code Class Code Cases: - - -
ID of Replacement:
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
PSE&G N/A N/A N/A N/A 1993 Serial No. Nat'l .. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No.         Other   Year Built   ASME Code Stamp'd.?
Replacement Const. Code: Spec S-C-MBOO-MDS Edition NL.A_ Addenda, Code Class II Code Cases:N/A
Replacement Const. Code:                       Edition       Addenda, Code Class Code Cases: - - -
-043_ ___ _
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
al No. Nat'l. Bd. Jurist No. ginal Const. Code: Code Cases: ---ID of Replacement:
Serial No. Nat'l. Bd. Jurist No. Other  Year Built    ASME Code Stamp'd.?
Original Const. Code:                       Edition        Addenda, Code Class Code Cases: - - -
--------------------------------------------------~---------------------------
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No.       Other  Year Built    ASME Code Stamp'd.?
Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?
Const. Code:                      Edition      Addenda, Code Class _
Addenda, Code Class ==============================================================================
* Cases: - - -
ID of Component Replaced:
==============================================================================
 
FbRM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by          Public Service Electric & Gas Co. - Nuclear Dept.                                                                                                  GJP #PS93-012 (name)                                      (repair organization's P.O. no., job. no.,etc.)
Foot of Buttonwocx:l Road,                                                Hancocks Bridge, NJ                              08038 (address) 2.0wner_'-Pub=-==l=1='c=----:S~erv==-~1='ce==~E=l=ectr==-===ic=-and=-==--Gas===-Co==~*-------------------------
(name)
Foot of Buttonwocx:l Road,                                              Hancocks Bridge, NJ                              08038 (address)
: 3. Name, address and identification of nuclear power plant                                                  Salem Nuclear Generating Station                                                Unit #1 Foot of Buttonwocx:l Road, Hanccx:::ks Bridge, NJ 08038
: 4. System          Control Air                                                                                                                                                              Nuclear Class I I
: 5. a: Componentrepa~ed, modffiedorre~aced _1_1_~                                          __      3~0~and~~1=2~3~~~~3~0~~~al~~~~~--------------------
b: Name of manufacturer _ _,,Maso_.,,,,,=n....,,.e,,.i,,.l,,,an,,._.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
c: Identifying nos.        N-00133-1-1&2                                              N/A                                      N/A                                      N/A                          1992 (mfr's. serial no.)                                  (Nat'l.Bd.No.)                    (jurisdictional no.)                            (other)                                (year built) d: Construction Code ASME I I I 1971                                                                  S/1971                                            N/A ANSI B31. 7 1969 W,~tioilt:)70 Add.                                                            (addenda)                                      (Code Case(s))                                    (Code Class)
: 6. Section XI                                  1983                                                                SUmrner        83                                                                          N/A (edition)                                                                              (addenda)                                                              (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                  1983              S83              ~N~/A~~~
(edition)        (addenda)      (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                  *1971                S71            N/A
                                                                  *ASME III/ANSI B31. 7 1969 Ed. 1970 Add.                                                                    (edition)            (addenda)        (Code Case(s))
: 9. Design responsibilities _PS==E=-=&G:=.._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic D                              pneumatic                    D design pressure D** pressure NOP psi                                              Code Case(s) _ _.N""/_.A""-------
Description of work            Replaced stem assembly and bolting on 11~30.                                                                                        Replace stem assembly (use of additional sheet(s) or sketch( es) is acceptable if properly identified) on 12~30.                    Stem assembli~ install to match new                                                                  soft seats.
                                                                                      ...1~2...,4,.___ _ _ _ _ _ _ __..J.D=.......,fc...iuc~iu:e""n.J.l.cy.q_-1R""e::J>po.LUJrt~--:<#~*.__,,N,.,/uAi-_ _ _ _ _ _ __
: 12. Remarks: _ _,Wi"-'o,,..r,,_,k"-'Ord"""'""er"""----l#r...i:L__o9,,,,.2"'0.c.4,..2..,1 Design Change Package #:                                                        lEC-3170 Pkg. 1 See attached pag~ for Description of Replacement.                                                                                          N/A
                        **      stem Inservice T~t                                                                              T
* Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                                36                  to use the "NR" stamp expires                  Oct. 3,            , 1g3::......::4_ __
Engr.
                                '13 . Signed. _ _PSE&G                                        Co.-Nuclear Dept.                                                                                  Principal Date      i L. - :2.. c  19,                                                _ _ _ _ _ _ _ _ _ _ _ _ __
(repair organization)                                (authorized representative)                                  (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of              New Jersey                                    and employed by                          Arkwright Mutual Insurance Co of        MA            have inspected the repair, modification or replacement described in this report on                                              /I*-          2 1<              , 19 '?:I      and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
C---'--.,                                                                    Facto:ry Mutual_ Engr. Assn.
                                                                  //2,{~
1 1
Date j 2    *-J f'J      , 9J .
19                    Signed                                                                                      Commissions        4          2 oS' {::> /f/ l Jf',J I J /(./_r : / J /
(Inspector)                                        (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB*Bl Rev 6
 
                                                                                                                                                                                                <1
_.-.--                                                                                                                                                                              '/-
FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S):g(
* TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS                                                                                              * .. ,. **, 0'.
* Page      *1.* of 2 ork performed by --=Pub=-===1==1=*c~serv"-==--'-"'1=*ce~~El~ectr-~1_*c_&_Gas~-Co~*~-~Nu~c=l=e=~=ir=--=De=p"-'t::..:.,____ __,CJP"""""'--'#u::PS!:..!=!.:9:!..:3:t..-~Oo!:4:!!5~----
(name)                              (repair organization's P.O. no., job. no.,etc.)
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) 2.0wner _ _      Pub
__l_i_c_Serv _ _i_ce    __E_l_ectr    _ _i_c_and              _ _Gas  _ _Co_.________________________~
(name)
Foot of      Buttonwood              Road,                Hancocks Bridge, NJ                            08038 (address)
: 3. Name, address and identification of nuclear power plant                                    salem Nuclear Generating Station                                      Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. system          Generator Blowdown                                                                                                                                Nuclear Class I I 5.~ Compone~repa~ed,modmedorre~~ed_l_l_G_B4~,_1_2_G_B4_L,_1_3_G_B4~,~1_4_G_B4                                              __~_~_v_e_~_~          ____s____________
b: Name of manufacturer              Masoneillian c: Identifying nos. See      Attch.                                  N/A                                      N/A                              N/A                          1974 (mfr's. serial no.)                      (Narl.Bd.No.)                    Uurisdictional no.)                      (other)                                  (year built) d: Construction Code        ANSI B31. 7                                                  1969                                            None                                  2 (edition)                                        (addenda)                                      (Code Case(s))                          (Code Class)
: 6. Section XI                          1983                                                          Slllmner 83                                                                            N/A (edition)                                                                    (addenda)                                                      (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                            1983            S83                _N~/_A_ _
(edition)        (addenda)          (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                            *N/A                1969                N/A
                                                *ANSI B31. 7                        /ASME        Sec. I I I 1971 - Slllmner 71 (edition)                                  (addenda)            (Code Case(s))
: 9. Design responsibilities _PS  __E_&G  _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic O                pneumatic O                          design pressure O            pressure          **      psi      Code Case(s)_~N,_/A~-----
: 11. Description of work          Replace GB4 valve internals IAW DCP lEC-3226-01.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: __Wi"'"""o=r=k=--Ord==er=-_#u...:....:_,9""'3"""'0,,_,2,,_,0"""3'""1=2=3'---_ _ _ _ _ _ _ __,,,De=f=i=c=i=en=cy~R.....,e""poE"=rt~_#..._._:_,N=o=n~e=---------
Design Change Package #: lEC-3226                                                          Rev. 01 See attached pages for Description of Replacement.
                      ** NOP                                                                                      Temp. Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                  36                to use the "NA" stamp expires                    Oct. 3,            , 19_9_4_ __
Date~        -23 PSE&G Co. -Nuclear Dept.
19,__2J::'Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ ...,~h,'4v I    .P iJ                              Principal                Engr.
(repair organization)                                (authorized representative)                            (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of        New Jersey                          and employed by                          Arkwright Mutual Insurance Co .
of        MA          have inspected the repair, modification or replacement described in* this report on                                        2 - Zh          , 19zj q        and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacemen.t described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date    2-"Jfr
                            ,I
                      . 1{/_:J__. Signed~:/~
                                                  ~                                < ~-
                                                                                          / ,                                                    Facto~ Mutual ~. Assn.
Commissionsl\/tJ)f7'{ ..J.'1/1.:/              A.JcJJ7J                        *
                                                                        .          (Inspector)                                        (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The Nation al Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
I Page _.L of _.L FORM NR-1 ATTACHMENT Code Job Package No.: PS93045 by:        Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Public Service Electric & Gas Co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System:    Generator Blowdown                                                                    Nuclear Class:    2
                                                                                                                                    ~~----
          '=============================================================================
i/ID of Component Replaced: ~1=-=l~G:=-:B::-:4~V..:..=a=l-'-v..:::e=---=I...._n-'-'t=..:e=r=:..:n=a=l"'s,_ _ _ _ _ _ _ _ _ _ _ _ _ __
JName of Manufacturer: -=-M=a=s~o=n=e=i=l=l=a=n~-~------------------~
/:;; N2/N001301-l N/A
?*~;-
N/A
                                            ~"""""----
N/A                            -=1=9_,_7_.4'----
Serial No. Nat'l. Bd.            Jurist No.                    Other                      Year Built            ASME Code Stamp'd.?
Original Const. Code: ANSI B31.7                                          Edition 1969 Addenda, Code Class~
Code Cases: N/A      --~A=S=M==E--=S~e=c~.'--'I=I==I--=1=9~7~1=---__,S=:...u=m=m==e=r'---'7~1=--
ID of Replacement:      12GB4 Valve Internals Name of Manufacturer: -=-==="-=====-=-===----------------------~
Masoneillan N2/N001301-2 N/A                  N/A                        N/A                            =1=9_,_7~4~--
Serial No. Nat'l. Bd.            Jurist No.                    Other                       Year Built             ASME Code Stamp'd.?
original Const. Code: ANSI B31.7                                          Edition 1969_ Addenda, Code Class~--
Code Cases: N/A              ASME Sec. III 1971 - Summer 71
          ==============================================================================
ID of Component Replaced: --=l=l~G~B~4=-V~a==l~v~e'---=I=n~t=e=r=n==a=l=s,_ _ _ _ _ _ _ _ _ _ _ _ _ __
e of Manufacturer: -=-==-==-=====.::::.=
Masoneillan_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
001301-3 N/A                =N_/=A'----                N/A                            1974 al No. Nat'l. Bd.            Jurist No.                    Other                       Year_B_u_i_l_t        ASME Code Stamp'd.?
Original Const. Code: ANSI B31.7                                          Edition 1969_ Addenda, Code Class ~--
Code Cases : _ N/A_ --~A=S=M==E--=S~e=c~.'--'I=I==I--=1=9~7~1=----__,S::...u=m=m=e=r=--7'-=1.
ID of Replacement:      12GB4 Valve Internals Name of Manufacturer:          Masoneillan N2/N00130 l - 4 N/A
                                      -=-==="-=====-=-===-----------------------
N/A* - - -                N/A                            -=1=9_,_7-'=4~--
Serial No. Nat'l. Bd.            Jurist No.                    0ther                      Year Built             ASME Code Stamp'd.?
Original Const. Code: ANSI B31.7                                            Edition 1969_ Addenda, Code Class ~
Code Cases: N/A              ASME Sec. III 1971 - Summer 71
        ==============================================================================
ID of component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
Serial No.     Nat'l. Bd.       Jurist No.                     Other                      Year Built            ASME Code Stamp'd.? . '''"'
Edition Addenda, Code Class ID of Replacement:
g~~~i~:!e~~nst. Code:                                                      Edition                          Addenda, code class ~.Jr~:~;,
        ~~:~;:~~~!~~~:~~~~::~--------------------------------------------------------~,
              'al No. Nat'l. Bd. Jurist No.                              Other                      Year Built            ASME Code stamp'd.j~;<f':'.*~~t~
* li    acement Const. Code:
Cases :
        =======================================================================~~~f;~;~:*:**
Edi ti on                  Addenda Code Class.?&sect;:.
                                                                                                                                  '            :* *..:..~-*>'(.......-:: .,r
                                                                                                                      ... . 't    *jGij~~,Bt**
 
FORM NR-1 REPORT OF REPAIR D MODIFICATION _MOR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l
~rkpertormedby -~B~1uh41L1~*c. . _...s~e~rv'-"- ~i~CP~- -. .E~luect'" " '. . . ._r~i~c. ._ .&, ._ ,G~.;au.; ;s._ _, ,Ca-n~-L- - ~Nu" "'c~l~e~-a~r. ._.De=,i,pt, . . _.L- ~CIP~.._~#~PS~9~3~-_,,0~5~3~-----
(name)
(repair organization's P.O. no., job. no.,etc.)
Foot of Buttonwocrl                        RoadJ                  Hancocks          Bridge,        NJ        08038 (address)
(name)
Foot of        Buttonwcxxl                Road,                  Hancocks          Bridge,        NJ        08038 (address)
: 3. Name, address and identification of nuclear power plant --~S=al=em=~Nu=c=l=e=ie3=Lr~~Gen~""era==t=ing=-o..~S~ta~~t=i=o~n~_U_m_'_t_#,,__l_ _ _ _ _ __
Foot of Buttonwood                        RoadJ                  Hancocks          Bridge,        NJ        08038
: 4. System        Reactor        Coolant                                                                                                                                                    Nuclear Class I 5.~ Componentrepa~ed,modffiedorre~~ed_~~~-&#xa5;~a_l~v~e~-----------------------------
b: Name of manufacturer -~C          ...o....pe.,......-S~"S...l!...11,..c
                                                                              ....o:=i~~n~----------------------------------
c: Identifying nos. 6910-95001-J 64-J                                  N/A                                    N/A                                              N/A                                  1969 (mfr's. serial no.)                            (Narl.Bd.No.)                ourisdictional no.)                                    (other)                                          (year built) d: Construction Code      W E-Spec E676270 _ _ _N...,,-F-/=A.___ __                                                                                  WA                                                  I ANSI B31. 7 1969 Eticiitio!J..l970 Add.                                            (addenda)                                                  (Code Case(s))                                        (Code Class)
: 6. Section XI                        ]983                                                          SJ.nnmer 83                                                                                                  N/A (edition)                                                                      (addenda)                                                                                (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                              1983                  S83                N~/~A  _ __
(edition)              (addenda)        (Code Case(s))
B. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                            *1969                        1970              N/A
                                                                                            *ANSI B31. 7          ITfi    E-Spec E-676270 (edition)                                                  (addenda)        (Code Case(s))
9: Design responsibilities _,."""'E,,,,&G=---------------------------------------~-
: 10. Tests conducted: hydrostatic D                    pneumatic                  D design pressure D**pressure NOP psi                                                      Code Case(s) _ _,N'-'J-/=A=*--~---
Replaced. valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: __w....._a~r~k....._.Qnj....._.~e~r.L-~#~*-9~3~0~1~2c..u6~1~5~0,___ _ _ _ _ _ _ _ _~n=                              ........-f~j~c~i~e~n~cyq....~B~e~:pc:2[!o<'-<-rt...._~#&#xb5;:.___.1'{~/~A....__ _ _ _ _ _-'----
Design Change Package #: lEC-3219 Pkg. 1 See attached pages for Description of Replacement.                                                                                      N/A
                        **SVstem          Inservice Test                                                            Temo.            Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                      36                  to use the "NA" stamp expires              Oct. 3,                        , 19_9_4_ __
                              ~- w                              PSE&G Co. -Nuclear Dept.                                                                                                              Principal Engr.
Date I~    (2        19,__'__L_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ __
(repair organization)                                            (authorized representative)                                        (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by
-the state or province of          New Jersey                                and employed by                    Arkwriaht Mutual Insurance Co of      MA            have inspected the repair, modification or replacement described in this report on                                                          f *- f I              , 19 ~ L/            and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer make~ any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
* any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
(/                          &#xa3;:        -                                                                    Facto:i:Y Mutual ~. Assn.
Date /- /      1 ,      19 C/ &#xa3;/    . Signed YQ-pwV v*                                    1.,-J____                                CommissionstVtf)JJ'l'/                        J.  /I/;-/ 1UJ            J//
                                                      /                              (Inspector)                                                  (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB*B1 Rsv.6
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION r&sect;' OR INSTALLATION OF REPLACEMENT($) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER P~ANTS Page l of l rkpertormedby_=Pub==-l=1=*c~S=erv==--'--=ice=='-=E=l=ectr====i=c'--=&'--"'Ga==s--=C=o~._-___;Nuo.=c=l=e=a=tr=-De==pt~~*---CJP==,,__#~PS==9~3=---=05=4-=-----
(name)                                (repair organization's P .0. no., job. no.,etc.)
Foot of Buttonwood Road, Hancocks Bridge, NJ                                              08038 (address)
(name)
Foot of Buttonwood Road, Hancocks Bridge, NJ                                              08038 (address)
: 3. Name, address and identification of nuclear power plant ___S_al7""-_em            __Nu_c_l_ear___Gen    __era __t_ing_~S_ta_t_i_o_n__U_ni_'_t_#~l_ _ _ _ _ __
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. System        Reactor Coolant                                                                                                                    Nuclear Class I
: 5. a: Component repaired, modified or replaced 1PR2 Valve b: Name of manufacturer -------'C""o""pes==--VUl=-==can=-=--------------------------------------
c: Identifying nos. 6910-95001-164-2 N/A                                                    N/A                                N/A                          1969 (mfr's. serial no.)          (Nat'l.Bd.No.)                aurisdictional no.)                      (other)                                  (year built) d: Construction Code        W E-Spec E676270 _ _~N~/A~--                                                                N/A                                    I ANSI B31. 7 1969 E'$ditioa.J970 Add.                            (addenda)                                      (Code Case(s))                            (Code Class)
: 6. Section XI                          1983 (edition)
Surrrrner 83 (addenda)                                                      (Code Case(s))
NIA
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                            1983            883                =Nr-=/A=------
(edition)        (addenda)          (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                            *1969              1970                N/A
                                                                            *ANSI B31.7/N E Spec E676270 (edition)                                          (addenda)          (Code Case(s))
: 9. Design responsibilities _PS_E_&_G    _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic O              pneumatic      O design pressure O **pressure NOP psi                                    Code Case(s) __N~/_A        _ _ _ _ __
Replaced valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: -~W~o=r=k~O=rd~e=r__,,_#~:~9~3=0~1-2=6-1~5~0_ _ _ _ _ _ _ _ _De~f_1_*c~i-*en~cy~~R~e"oEpo~rt~_,.:/f~=~N;'r-/~A~----,-----
Desiqn Change Package #: lEC-3219                                          Pkg. 1 See attached pages for Description of Replacement.                                                        N/A
                        **Svstem Inservice Test NOP                                                Temn. NOT CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                36      to use the "NR" stamp expires              act. 3,              , 19_9_4_ __
f'                      PSE&G Co.-Nuclear Dept.                                                                              Principal              Engr.
Date    rJ-    I 2      19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
                                                                                                                    ~'
(repair organization)                                (authorized representative)                            (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of        New Jersey              and employed by                    Arkwrioht Mutual Insurance Co of        lYIA          have inspected the repair, modification or replacement described in this report on                        / - if                q
                                                                                                                                                      , 19 l/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
                                                                      -/
* 1n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
              - { c*                              ~*1                                                                            ~act:qry ~tual Engr. Assn.
Date        1    1    , 1g_jj__. Signed (          M?'\.Zt/    ~. (..,~                                  Commissions      Mz ~        '1'1 JN      if        J JV f7]
(Inspector)                                        (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION [gl OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l orkpertormedby    -~P1........1h~l~i~c~S~e-~~~i~c-!e~E~l~ect~~r_i~c~~&~C...;:i~~s~C~o~._-___.NJ.......,1c~l......e~e~r_ .De" '" lp~t. . _._.___CIP""""'...._~#&#xb5;PS
                                                                                                                                                                              ........~9~3~-~0~5~2..___ _ _ _~
(name)                                        (repair organization's P.O. no., job. no.,etc.)
Foot of ButtonwOCJd Road, Hancocks Bridge: NI                                                    08038 (address)
(name)
Foot    of Buttonwood Road,                        Hanccx::::ks      Bridge, NJ                08038 (address)
: 3. Name, address and identification of nuclear power plant ___S=al~em=~Nu==c=l=e=!a=tr~Gen==era==t=mg='                                    =~S'""'ta=t=1='=o=n~_,U=ni='t=---'#'-=1=----------
Foot of Buttonwood Road: Hancocks Bridge, NJ 08038
: 4. System        Reactor Coolant                                                                                                                                  Nuclear Class I I
: 5. ~ Componentrepa~ed, modffiedorre~aced ~1-C~--~~~-~4-0~4~~~~~~-~~------------------------
b: Name of manufacturer ---=--=......- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
c: Identifying nos. __.N;-&#xa5;-/A=-----                                                                    N/A                                        N;/A                              1976 (mfr's. serial no.)                (Nat'l.Bd.No.)                aurisdictional no.)                              (other)                                        (year built) d: Construction Code        J?S Spec 69-6445                                NIA J                                                      N/A SGS/M-FD-1                          (edition)                        (addenda)                                            (Code Case(s))                                    (Code Class)
: 6. Section XI                            1983                                          SJ l!JD1Jffr 83                                                                                      N/A (edition)                                                        (addenda)                                                                  (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                            1983              883                  ~N~/=A~~-
(edition)          (addenda)          (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                          *NIA                  N/A                    N/A
                                                                                    *PS Spec S-C-MBJO-MIE-043                                              (edition)            (addenda)              (Code Case(s))
: 9. Design responsibilities ~PS~E=&G~----------------------------------------
: 10. Tests conducted: hydrostatic D                    pneumatic      D design pressure D **pressure                              WA          psi      Code Case(s)_~N,,_,,_/A"-=-------
Modified pressurizer piping supports.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                      36        to use the "NR" stamp expires              Oct. 3,                    , 19_9_4_ __
PSE&G co.-Nuclear Dept.                                                                                          Principal                Engr.
Date    i2 - 8'      19, Cf-3 . Signed _ _ _                _ _ _ _ _ _ _ _ _ _ _ _ __
(repair organization)                                    (authorized representative)                                    (title)
CERTIFICATE OF INSPECTION
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of          New Jersey                  and employed by                      Arkwright Mutual Insurance Co of        MA          have inspected the repair, modification or replacement described in this report on 2. O 06C.                                                , 19 lf .3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification o e I cement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal inju~                  o e            ge or a ss f any k" d arising from or connected with this inspection.
* Facto:ry Mutual Engr. Assn.
Date    zo Dec...' 19 Q3.                  Signed                                                                Commissions                    N8 ll.2o :;i.        r    A) ,4            H.J/~L:G,J (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB*81 Rev.6
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l rk performed by                      Pnblic Service El ec:tri c & Gas co                                                                    - Nuclear Dept                            GIP #PS93-055 (name)                                (repair organization's P.O. no., job. no.,etc.)
M'oat of But+om,zoaj Raad, Hancacks Bridge, NT                                                                                                08038 (address)
(name)
Foot of Buttonwood Road. Hancocks Bridge. NJ                                                                                                  08038 (address)
: 3. Name, address and identification of nuclear power plant _ _..,S.,,a...l""'ern,.,...~Nu.o=.,,c""l...,e,,,,e,.,r..__,,,Gen=..,era""",,.t==ing~;l---'S,.,ta=..,,t:::i""o""n..___U=m=',_,t"-J#,_,1=--------
Foat of Buttonwocx] Road, Hancacks Bridge, NI                                                                                                08038
: 4. System        Reactor Cool ant                                                                                                                                                                      Nuclear Class I
: 5. a: Component repaired, modified or replaced                                                  PR!'              Pipe Spcxlls Sl-RC-3220 and Sl-RC-3222 b: Name of man.ufacturer _ __.,T..,.JE.,.&,,.,C._,~/.,..PS""""E""&G"""''------------------------------------
c: Identifying.nos. -N-+/..                  A-----                                                    N/A                                                                          N/A                          1974 (mfr's. serial no.)                                      (Nat'l.Bd.No.)                          Uurisdictional no.)                      (other)                                  (year built) d: Construction Code                          ANSI B31 7 1969                                                              1970                                          N/A ANSI B31.1 1967                                          (edition)                                                    (addenda)                                    (Code Case(s))                            (Code Class)
: 6. Section XI                                                1983                                                                      simrrner 83                                                                          N/A (edition)                                                                                  (addenda)                                                        (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                1983              883              N._,,/c...:A-=----
(edition)          (addenda)      (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                              *1969                  1970            N/A
                                                                                                                              *ANSI B31.7/ANSI B31.l 1967                                  (edition)            (addenda)        (Code Case(s))
: 9. Design responsibilities ......i;:.i.2.1,;~;;r._----------------------------------------
: 10. Tests conducted: hydrostatic D                                        pneumatic                                D design pressure D** pressure NOP psi                                      Code Case(s)_~N""/~A~------
: 11. Description of work                            Modi f j ed pressurizer relief                                                            tank small bore piping.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: _        _..w.....o...~rik...........Ord
                                                    ............eM!r~#r-.'-"'9.....3.....0....l....2-..6....l....5....0..,.__ _ _ _ _ _ _ ____.De....._.f._j~c~1~*e....n.....cy...q-~R~e--ipa~rt~_,:/J:""':~~..,.l~A~--------
Desi gn Change Package j: JEC-3219 Pkg. 1 See attached. pages for Description of Replacement. N/A
                          **SVstem Inservice Test                                                                                                    Ti=>mn. NOT CERTIRCATEOFCOMPLIANCE Wffcertify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME *code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                                          36                        to use the "NR" stamp expires                        Oct. 3,              , 199~4_ __
c; u                                    PSE&G Co.-Nuclear Dept.                                                          d / /              ,                    Principal Engr.
Date      f-      2        19,______L_,L.. Signed _ _ _ _ _ _ _ _ _ _ _ _ .,,~&~-Cu~
(repair organization)                                (authorized representative)                          (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by
-the state or province of                            New Jersey                                    and employed by                              Ark.wriaht Mutual                    Insurance Co of        MA                have inspected the repair, modification or replacement described in this report on                                                                        / *- //          , 19.&-/ l/      and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, Date
            /.- 1I          , 1g_j{_.
e, Signed q {;
d or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be ny manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
{\/~                            *
(Inspector)
                                                                                                                                    ~-                          Commissions Facto:cy Mutual EngJ::. Assn.
                                                                                                                                                                                    ,1.fF J8"1 Y J:iUIJ A.ff ?7 3 (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
FORM NR*1 REPORT OF REPAIR 0 MODIFICATION-q] OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l ork performed by _        .........L.l~i..,c"'---'SeJ::v,,,..,.._,,_...
_...Pub                                    ice,,.,,.'-""'E....l.,.ectr""'"""                  ........_,Co""""'*.__-___.Nu~c,.,l,..e,,,,oa....._r_..De~p,_,,t._,*._____
                                                                                                              ......i""c"--"&.__,,Gas                                                                      __,CJP....,_,..__:tt~PS......,J.9_,.,3_-_,,,0CL7_,,,0'---"R,.,,e.,__,vu....l..___
(name)                                                (repair organization's P.O. no., job. no.,etc.)
Foot of Buttonwood Road. Hancocks Bridge. NJ                                                                                                08038 (address)
(name)
Foot of Buttonwood Road, Hancocks Bridge, NJ                                                                                                08038 (address)
: 3. Name, address and identification of nuclear power plant                                                              Salem Nuclear Generating Station                                                                    Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. System        Control Air                                                                                                                                                                                                Nuclear Class II 5.a: Componentrepa~ed,modlliedorre~aced ~P=i~pe~~~~~=l~l=~~~3=1=0~-------------------------
b: Name of manufacturer _ _Mu..t.....              t. J'-'"'---'Ib"""';y_~....l,.,,,e..___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
c: Identifying nos.      N/A                                                            N/A                                                      N/A                                            N/A                                              1974 (mfr's. serial no.)                                    (Nat'l.Bd.No.)                                Qurisdictional no.)                                        {other)                                                            (year built) d: Construction Code          B31.1 1967/B31. 7 1969 None                                                                                                                          None (edition)                                                      (addenda)                                                        (Code Case(s))                                                    (Code Class)
: 6. Section XI                                1983                                                                            Summer              83                                                                                                            N/A (edition)                                                                                              (addenda)                                                                                      (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                            1983                        S83                            ~N'r-'/A~--
(edition)                    {addenda)                      (Code Case{s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                          *1967                            N/A                              None
                                                                                                                  *ANSI B31.l/B31. 7 1969                                                            (edition)                      (addenda)                        {Code Case{s))
: 9. Design responsibilities - - = P S = - = E = & G = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
: 10. Tests conducted: hydrostatic D                              pneumatic [){ design pressure O **pressure                                                                      142 psi                  Code Case(s)_~N~o=n=e~-----
: 11. Description of work            Added break flanges to pipe spool piece 1CA2310.
(use of additional sheet{s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ __.Wi~o~r~k"'--'On'J"'"'-'~e....._r-'ll#~=-9u3~D~6...,_..._1~5~1~3~5,___ _ _ _ _ _ _ _ _~De~~f~i~c~i~e-n~c:y-r-B~e~po~rt-~~#~:~N~a~n~-e~-------
Design Change Package #: lEC-3150-1 Rev.                                                                                                o See attached pages for Description of Replacement.                                                                                                                    N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                                36                to use the "NR" stamp expires                                      Oct. 3, , 19~9_4~--
e'1  I/                                        PSE&G Co. -Nuclear Dept.                                                                                                                                    Principal Engr.
Date ') -    '"'2-L    19,~.                Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
{repair organization)                                                      (authorized representative)                                                            (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of          New Jersey                                      and employed by                                          Arkwri t Mutual Insurance of        MA          have inspected the repair, modification or replacement described in this report on                                                                                                                                          and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
        .                  '"'* ,/                            ~                                      ,.,,,-*        /                                                                        Factory Mutual Engr. Assn.
Date )    J Jf        ,1rfL.!___. Signed ~                                                          7.          Lo-/.__                                      Commissions/i)fi,!)(C/{                        L/V/i                  ,A)\LJ J              7
{Inspector)                                                              {Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION ~OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by        Public Service Electric & Gas Co. - Nuclear Dept.                                                                                    CJP #PS93-073 (name)                                    (repair organization's P .0. no., job. no.,etc.)
Foot of Buttonwocxi Road,                                    Hancocks              Bridge,        NJ      08038 (address)
(name)
Foot of Buttonwocxi Road,                                    Hancocks              Bridge,        NJ      08038 (address)
: 3. Name, address and identification of nuclear power plant                                    Salem Nuclear Generating Station                                            Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038
: 4. system        Chemical & Volume Control system                                                                                                                          Nuclear Class I I
: 5. ~ Componentrepa~ed, modffiedorre~aced _~_r_1_'c_~_c_i_d_B_l_~                                      __er _________________________~
b: Name of manufacturer _ ____,_Wi=es~t=mg=*            =h=o_,,,us=e:....__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
c: Identifying nos. None                                            N/A                                      N/A                                    N/A                    _ _1=9~7~2~----
(mfr's. serial no.}                        (Nat'l.Bd.No.}                  Qurisdictional no.)                            (other)                                  (year built}
d: Construction Code ANSI B31. 7                            1969                        1970                                                None                                  II ANSI B31.1 1967                      (edition)                                    (addenda)                                          (Code Case(s)}                          (Code Class}
: 6. Section XI                            1983                                                        S1.nnmer      83                                                                          N/A (edition)                                                                  (addenda)                                                            (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                  1983            S83                  N_/_A_ __
(edition)      (addenda)          (Code Case(s)}
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                *1969              1970                N/A
                                                                                              *ANSI B31.7/ANSI B31.l 1967                                      (edition)          (addenda)          (Code Case(s))
: 9. Design responsibilities
                                  -PSE&G
: 10. Tests conducted: hydrostatic :f;!                    pneumatic              D design pressure O** pressure 170 psi                                          Code Case(s)_~N"""/~A~------
escription of work        Removal of boric acid blender no longer needed in chemical and (use of additional sheet(s) or sketch( es) is acceptable if properly identified) volume control syst:m and re-installation of piping.
: 12. Remarks: _ _,,Wi,_,,o=r=k,,____,,O=rd=e=r-..u.#~:-=9=3=0=61~8,...l,.,,_,3....,3..___ _ _ _ _ _ _ _ _De~f                    ......1~*c~i~*en~cy~~R~e"'fpo~rt~....,#~=~N;'f-/~A~-------
Design Change Package #: lEC-3254                                                          Rev. O See attached pages for Description of Replacement.                                                                              N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                      36                to use the "NR" stamp expires              Oct. 3 1                    , 193_4_ __
PSE&G Co. -Nuclear Dept.                                                  I /      fl                          Principal              Engr.
Date ( * (      l(    19,__l,i_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _
7 4,4&uL~                              *
(authorized representative)                          (title)
(repair organization)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of          New Jersey                            and employed by                        Arkwriqht Mutual Insurance Co of      MA            have inspected the repair, modification or replacement described in this report on                                                I/, 7            , 1gCO        and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
* n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
                    /          -. ;                      ~                                  -    /                                                        Factory Mutual Engr. Assn.
Date/.--),)            ,1~.Signed~JU-/?'. l~J_.____                                                                          CommissionsN/)""'t9l/                      '&#xa3;;J/t tJf?ZJ (Inspector)                                            (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB*B1 Rev 6
 
FORM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)                                                                                                                                                                          ill TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 rk performed by                  Public Service Electric &                                                                      Gas Co. - Nuclear Dept.                                                            CJP #PS93-074
*                                                                                                                                                        (name)                                          (repair organization's P .0. no., job. no.,etc.)
Foot of Buttonwocxi Road,                                                                    Hancocks                  Bridge, NJ 08038 (address)
(name)
Foot of Buttonwocxi Road,                                                                    Hancocks                  Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant                                                                          Salem Nuclear Generating Station                                                                      Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038
: 4. System          Chemical & Volune Control System                                                                                                                                                                                        Nuclear Class I I
: 5. a: Componentrepa~ed, modifiedorre~aced _1_~                                                                __        7_2_Co_n_tro_ _l_~_al_~_e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
b: Name of manufacturer                                      Copes Vulcan c: Identifying nos.                6910-95001-187-1 N/A                                                                                                N/A                                              N/A                                              1971 (mfr's. serial no.)                                              (Nat'l.Bd.No.)                        uurisdictional no.)                          (other)                                                                (year built) d: Construction Code                    ANSI B31. 7 1969                                                                      1970                                              N/A fl E-Spec 676270 (edition)                                                                                          (addenda)                                      (Code Case(s))                                                            (Code Class)
: 6. Section XI                                              1983                                                                  --~SUmmer~~-__...8""'3'-----------                                                                                              N/A (edition)                                                                                              (addenda)                                                                                        (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                                        1983                            S83          ~N~/~A-"'---
(edition)                          (addenda)      (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                              *1969                                        1970            None
                                                                                                                                  *ANSI B31.7/N E-Spec 676270 (edition)                                                                              (addenda)      (Code Case(s))
: 9. Design responsibilities __              PS_E_&G          _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic                            [JX pneumatic D                                                design pressure O *"'Pressure                    170 psi                          Code Case(s)_~N~/~A~-----
: 11. Description of work                      Replace existing lC'i/172 valve internals in accordance with ~ lEC-3254 (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
Packa: e      1        and            re lacernent of bolt'                                                                and    nuts            r  revision 1 of~ lEC-3254.
: 12. Remarks: _ _..W,,,,o,,,,,r,,_...k.._,,,O<<>rd,_,,,,,,,er,,,.,,__....J#w:.___.9""""3....,0....,6....1...8....l...3.._.3..___ _ _ _ _ _ _ ____.De,,,.__.f._i..,,c~i..,,e.....                            ...........rt.........._-..:iff~:.___.N m_..cy"-'l--.....R,,,.e.,..po                                ......n_...n__.,.e'"'-----------
Desiqn Change Package #:                                                                                lEC-3254                  Rev.      o See attached                                          pages                        for Description of Replacement.
                        **NA                                                                                                                              T
* 90&deg;F CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                                              36                    to use the "NR" stamp expires                          Oct.      3/        . 19_9_4_ _
                                  ,,;                                                    PSE&G Co. -Nuclear Dept.                                                        /    /    /          ~                                                      Principal            Engr.
Date j-~ /j'          19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _                                                                                                      dd~~,
(repair organization)                        v        (authorized representative)                                                            (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of                      New Jersey                                            and employed by                                Arkwright Mutual Insurance Co of        MA          have inspected the repair, modification or replacement described in this report on                                                                                  /    /                              , tf}
19                    and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, k                                                      /
sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date
                    /
J. .- Z-)    , 19 q_i_                . Signed
                                                                                                                            ~**
t** ~
tf Commissions N J F51ct01:y Mutual Engr. Assn.
IJ f1t./ /ttf/1                                      /!) ;/f 7}
I (Inspector)                                        (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION ~OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by _ _,Pub=-==-=l::.:1::..:'c=----=S::...;erv==-"-'1=-*ce=-=---=El=ectr=-=-=1=-*c=-&=--Gas=~CO"-"--.'------=Nu=c::.::l::..:e==!a=tr=----=De=p::..:t=-.=-----'CJP=:...._j#u..:PS=-=9::..:3=---'0=-7:....:5:o....__ _ __
(name)                                            (repair organization's P.0. no., job. no.,etc.)
Foot of Buttonwocxi Road,                                          Hancocks Bridge, ID                                    08038 (address) 2.owner _ _Pub      __l_i_c_S_erv __i_ce        __E_l_ectr        _ _i_c_and          _ _Gas    _ _co_._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
(name)
Foot of Buttonwocxi Road,                                          Hancocks Bridge, ID                                    08038 (address)
: 3. Name, address and identification of nuclear power plant                                              Salem Nuclear Generating Station                                                              Unit          #1 Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038
: 4. System          Main Steam                                                                                                                                                                        Nuclear Class I I
: 5. a: Component repaired, modified or replaced 1.MSE57, 1.MSE58, 1MSE59, 1.MSE60 COndensate Chambers
                                                                                ....,-----~---~----~----------------------
b: Name of manufacturer                  COnnex Pipe Systems c: Identifying nos.      See Attachment                                          N/A                                                N/A                                        N/A                                    1993 (mfr's. serial no.)                                (Nat'l.Bd.No.)                      Ourisdictional no.)                                    (other)                                              (year built) d: Construction Code          See Attachment                                                      N/A                                                            N/A                                                  II (edition)                                              (addenda)                                                    (Code Case(s))                                          (Code Class)
: 6. Section XI                          1983                                                                    Sl..nmner 83                                                                                                      N/A (edition)                                                                                  (addenda)                                                                          (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                          1983                S83                    ~N~/~A~--
(edition)            (addenda)              (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                        *1989                      1989                    N/A
                                                                  *ASME III/ANSI B31.7 1969 F.d. 1970 Add.                                                                        (edition)                  (addenda)                (Code Case(s))
: 9. Design responsibilities _PS  __ E_&G  _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic [JC pneumatic D                                              design pressure D *-J;:iressure                                1400psi                Code Case(s)_--=N'-"/'-'A=--------
escription of work        Installed new condensate chambers for #11 main steam header.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: _ __,_,W=o=r"""k~O=rd=er=-~#"""':,__,9"""'3~0,,__,8=1,,_,0""'0=9=9'-----------=De~f,_,,i.,,c,,..i.,,,en.....,,,cy~...,R.,.,e~po""'rt..._,.,_#..,_._:_.N;LI.J/O...OA....___ _ _ _ _ __
Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                            36                  to use the "NR" stamp expires                        Oct. 3, , 19_9_4_ __
PSE&G co.-Nuclear Dept.                                                              /      /      /              ....                  Principal Engr.
Date { -        a-c1    19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ ..,.~ -dd<~
(repair organization)                                                (authorized representative)                                            (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of          New Jersey                                    and employed by                              Arkwri t Mutual Insurance Co of          MA          have inspected the repair, modification or replacement described in this report on                                                                      -I                , 199 ' ( and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
C /                .I      __.                                                _ Facto:cy Mutual_.....~. Assn.
Date      /  * '{ , 19-5....!L._. S i g n e d . / t * ~                                                                                    Commissions ;J{)                f1'it        1AJ;1          /UJ J J      J (Inspector)                                                        (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
r  -
Page _2_ of _2_
FORM NR-1 ATTACHMENT Code Job Package No.: PS93075
* Work performed by:                      Public Service Electric & Gas co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 2.          Owner:                                  Public Service Electric & Gas Co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 3.            Location:                                Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4.            System: ~M=a=i=n=---=S~t=e=a=m==-------------~ Nuclear Class: --=I=I=----~
      ==============================================================================
ID of Component Replacement: 1MSE57 Condensate Chamber Name of Manufacturer: ___c~o=n=n=e=x=--P.......,i_p_e-=s_y~s~t~e_m______________________,
43471                          N/A                    N/A              N/A            1993                  =N=o~------~---=--
Serial No. Nat'l. Bd. Jurist No.                                        Other        Year Built              ASME Code stamp*d.?
Original Const. Code: ASME III 1989                                          Edition 1989 Addenda, Code Class z___
Code Cases: N/A                                    ANSI B31.7 1969 Ed. 1970 Add ID of Replacement:                              1MSE58 Condensate Chamber Name of Manufacturer: ___c=o=n=n=e=x=--P=-=ip~e-=s_y~s~t~e=m-........._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
434 72                          N/A                    N/A              N/A            ~1~9~9_3~___,.--      No*~--------~
Serial No. Nat'l. Bd. Jurist No.                                        Other         Year Built             ASME Code Stamp'd.?
Replacement Const. *code: ASME III 1989                                            Edition 1989 Addenda, Code Class L Code Cases:N/A                                          ANSI B31.7 1969 Ed. 1970 Add
      ==============================================================================
ID of Component Replaced: _:;.;N~A=------------------------~
Name of Manufacturer:
Name of Manufacturer:
Serial No. Cases: Nat'l. Bd. Jurist No. Const. Code: ---Other Year Built Edition ASME Code Stamp'd.?
                  'al No. Nat'l. Bd.                         Jurist No.       Other         Year Built             ASME Code Stamp'd.?
Addenda, Code Class _ * ==============================================================================
ginal Const. Code:                                                  Edition                    Addenda, Code Class Code Cases: - - -
FbRM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by Public Service Electric & Gas Co. -Nuclear Dept. GJP #PS93-012 (name) (repair organization's P.O. no., job. no.,etc.)
ID of Replacement:                             1MSE59 Condensate Chamber Name of Manufacturer: ~C=o=n=n=e=x=-P=-=i=p~e-=S~v~s~t=e=m=------------------
Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 (address)
4347 3                         N/A                   N/A             N/A           =1=9-=9~3~----=----- No S er i al No. Nat'l. Bd. Jurist No.                                     Other         Year Built             ASME Code Stci.mp'd.?
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocx:l Road, Hanccx:::ks Bridge, NJ 08038 4. System Control Air Nuclear Class II 5. a:
Replacement Const. Code: ASME III 1989                                            Edition 1989 Addenda, Code Class L Code Cases:N/A                                           ANSI B31.7 1969 Ed. 1970 Add
__
      ==============================================================================
b: Name of manufacturer
ID of Component Replaced: --=-'N~A=--------------,------------~
_ _,,Maso_.,,,,,=n....,,.e,,.i,,.l,,,an,,._._
_________________________________
_ c: Identifying nos. N-00133-1-1&2 N/A N/A N/A 1992 (mfr's. serial no.) (Nat'l.Bd.No.) (jurisdictional no.) (other) (year built) d: Construction Code ASME III 1971 S/1971 N/A ANSI B31. 7 1969 Add. (addenda) (Code Case(s)) (Code Class) 6. Section XI 1983 SUmrner 83 N/A (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
S83 (addenda)
S71 (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1971 N/A *ASME III/ANSI B31. 7 1969 Ed. 1970 Add. (edition) (addenda) (Code Case(s)) 9. Design responsibilities
_PS==E=-=&G:=..
______________________________________
_ 10. Tests conducted:
hydrostatic D pneumatic D design pressure D ** pressure NOP psi Code Case(s) _ _.N""/_.A""-------
Description of work Replaced stem assembly and bolting on Replace stem assembly (use of additional sheet(s) or sketch( es) is acceptable if properly identified) on Stem install to match new soft seats. 12. Remarks: _ _,Wi"-'o,,..r,,_,k"-'Ord"""'""er"""----l#r...i:L__o9,,,,.2"'0.c.4,..2..,1
...
________
_______ _ Design Change Package #: lEC-3170 Pkg. 1 See attached for Description of Replacement.
N/A ** stem Inservice T
* Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 1g3::......::4
__ _ PSE&G Co.-Nuclear Dept. Date i L. -:2.. c 19, '13 . Signed. _______________
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /I*-2 1< , 19 '?:I and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
1 C---'--., Facto:ry Mutual_ Engr. Assn. Date j 2 *-J f'J , 19 9J . Signed Commissions 4 2 oS' {::> /f/ l Jf',J I J /(./_r :/ J / (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*Bl Rev 6 
<1 _.-.--'/-FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S):g(
* TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS * .. ,. **, 0'.
* Page *1.* of 2 ork performed by --=Pub=-===1==1=*
_ (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (repair organization's P.O. no., job. no.,etc.) (address) 2.0wner __ Pub __ l_i_c_Serv
__ i_ce __ E_l_ectr __ i_c_and __ Gas __ Co_. ________________________ (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. system Generator Blowdown Nuclear Class II
__
____ s ___________
_ b: Name of manufacturer Masoneillian c: Identifying nos. See Attch. N/A (mfr's. serial no.) (Narl.Bd.No.)
d: Construction Code ANSI B31. 7 6. Section XI (edition) 1983 N/A Uurisdictional no.) 1969 (addenda)
Slllmner 83 (edition) (addenda) (other) None N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A *ANSI B31. 7 /ASME Sec. III 1971 -Slllmner 71 (edition) 1974 (year built) 2 (Code Class) N/A (Code Case(s)) S83
__ (addenda) 1969 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities
_PS __ E_&G ________________________________________
_ 10. Tests conducted:
hydrostatic O pneumatic O design pressure O pressure ** psi Code
: 11. Description of work Replace GB4 valve internals IAW DCP lEC-3226-01. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: __ Wi"'"""o=r=k=--Ord==er=-_#u...:....:
_,9""'3"""'0,,_,2,,_,0"""3'""1=2=3'---
________
Design Change Package #: lEC-3226 Rev. 01 See attached pages for Description of Replacement.
** NOP Temp. Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4 __ _ PSE&G Co. -Nuclear Dept. I .P iJ
-23 19,__2J::'Signed
______________
Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co . of MA have inspected the repair, modification or replacement described in* this report on 2 -Zh , 19zj q and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacemen.t described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date 2-"Jfr . 1{/_:J__. ,
* Commissionsl\/tJ)f7'{
..J.'1/1.:/
A.JcJJ7J * , I < / ,
Mutual Assn. . (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The Nation al Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 I Page _.L of _.L FORM NR-1 ATTACHMENT Code Job Package No.: PS93045 by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System: Generator Blowdown Nuclear Class: 2
'=============================================================================
i/ID of Component Replaced:
______________
_ JName of Manufacturer:
/:;; N2/N001301-l N/A N/A N/A -=1=9_,_7_.4'----
Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
Original Const. Code: ANSI B31.7 Edition 1969 Addenda, Code Code Cases: N/A ID of Replacement:
12GB4 Valve Internals Name of Manufacturer:
Masoneillan N2/N001301-2 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
original Const. Code: ANSI B31.7 Edition 1969_ Addenda, Code Code Cases: N/A ASME Sec. III 1971 -Summer 71 ==============================================================================
ID of Component Replaced:
______________
_ e of Manufacturer:
Masoneillan
-=-==-==-=====.::::.=
______________________
_ 001301-3 N/A =N_/=A'----
N/A 1974 al No. Nat'l. Bd. Jurist No. Other Year_B_u_i_l_t ASME Original Const. Code: ANSI B31.7 Edition 1969_ Addenda, Code Cases : _ N /A_
ID of Replacement:
12GB4 Valve Internals Code Stamp'd.?
Code Class Name of Manufacturer:
Masoneillan
-=-==="-=====-=-===-----------------------
N 2/N00130 l -4 N/A N/A *---Serial No. Nat'l. Bd. Jurist No. Original Const. Code: ANSI B31.7 Code Cases: N/A ASME Sec. III N/A 0ther Year Built ASME Code Stamp'd.?
Edition 1969_ Addenda, Code Class 1971 -Summer 71 ==============================================================================
ID of component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? . '''"'
Serial.No. Nat'l. Bd .. Jurist No.                                       Other         Year Built             ASME Code Stamp'd.?
Code: Edition Addenda, code class li'al No. Nat'l. Bd. Jurist No. Other Year Built ASME Code acement Const. Code: Edi ti on Addenda Code Class.?&sect;:.
Original Const. Code:                                                         Edition                     Addenda, Code Clas$
' :* * .. : > '( -:: .,r
Code Cases: _ _ _ _ _ _ _ __
* Cases : .. * ....... ,
      -------------------------------------------------~----------------------------
.... 't
ID of Replacement:                              1MSE60 Condensate Chamber Name of Manufacturer: ---~:=-===--=-===-=.....-=:-=~"------------------,-~~
______ ................................
Connex Pipe System 43474                          N/A                    N/A              N/A            =1=9=9=3~__,..~        No Serial No. Nat'l. Bd. Jurist No.                                         Other        Year Built              ASME Code Stamp'd.?
...
acement Const. Code: ASME III 1989                                  Edition 1989 Addenda, Code Class .6.._
FORM NR-1 REPORT OF REPAIR D MODIFICATION
Cases:N/A                             ANSI B31.7 1969 Ed. 1970 Add
_MOR INSTALLATION OF REPLACEMENT(S)
      ==============================================================================
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l
_ _ _ _ _ _ _ ..--&#xa3;.,, _ _ _ - -- -* - -- **- -- ---    --  -- -    - - ---    ~ - -- -----*          - "      *    *  * -~
...
 
__ (name) (repair organization's P.O. no., job. no.,etc.)
FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2
Foot of Buttonwocrl RoadJ Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwcxxl Road, Hancocks Bridge, NJ 08038 (address)
*~~~m~~-~~~=l=i=c~S~~~=i=~~=E=l=~==1=*c~&~~=~~~-~-~~=c=l~AA~r~~=~t~*--~~~~#~ffi~9~3~-~0~7~6~----                   (name)                                        (repair organization's P.0. no., job. no.,etc.)
: 3. Name, address and identification of nuclear power plant
Foot of Buttonwcxxi Road,                                        Hancocks Bridge, NJ                        08038 (address)
______ _ Foot of Buttonwood RoadJ Hancocks Bridge, NJ 08038 4. System Reactor Coolant Nuclear Class I b: Name of manufacturer ... o ....  
(name)
... l! ... 11,..c ....
Foot of Buttonwcxxi Road,                                        Hancocks Bridge, NJ                        08038 (address)
c: Identifying nos. 6910-95001-J 64-J N/A N/A (mfr's. serial no.) (Narl.Bd.No.)
: 3. Name, address and identification of nuclear power plant                                    Salem Nuclear Generating Station                                                            Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
ourisdictional no.) d: Construction Code W E-Spec E676270 ___ N...,,-F-/=A.__
: 4. System          Main Stearn                                                                                                                                                              Nuclear Class                    II 5.~ Componentrepa~ed,modffiedorre~aced~~~=E~6~1~,~~~=E~6~2~,~~~~E~63~,~~~=E~6~4~~~~~=~~~~~-~~~~~~-------
__ _ ANSI B31. 7 1969 Eticiitio!J..l970 Add. (addenda)
b: Name of manufacturer                        ~nnex Pipe Systems c: Identifying nos.       See Attachment                                    N/A                                    N/A                                          N/A                                        1993 (mfr's. serial no.)                           (Narl.Bd.No.)               Ourisdictional no.)                            (other)                                                    (year built) d: Construction Code            See Attachment                                          N/A                                                  N/A (edition)                              (addenda)                                          (Code Case(s))                                                  (Code Class)
: 6. Section XI ]983 SJ.nnmer 83 (edition) (addenda)
: 6. Section XI                                  1983                                                  SUrnmer        83                                                                                              ~/A (edition)                                                                (addenda)                                                                              (Code Case(s))
N/A (other) WA (Code Case(s)) 1969 (year built) I (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                          1983                      883                ~N~/~A~--
S83
(edition)                  (addenda)          (Code Case(s))
__ _ (addenda) 1970 (Code Case(s)) B. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A *ANSI B31. 7 ITfi E-Spec E-676270 (edition) (addenda) (Code Case(s)) 9: Design responsibilities
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                        *1989                            1989                N/A
: 10. Tests conducted:
                                                                    *ASME III/ANSI B31.7 1969 Ed. 1970 Add.                                                        (edition)                        (addenda)            (Code Case(s))
hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _
: 9. Design responsibilities --=ffi~=E:..:.&G:.=-._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Replaced.
: 10. Tests conducted: hydrostatic [){ pneumatic                                  D design pressure D **pressure                              1400psi                    Code Case(s) _ __,,N""/'-'A,_,,___ _ _ _ __
valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:
escription of work            Installed new cond~te chambers for #12 main steam header.
__
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
_________ ........
: 12. Remarks: _ __,_,W=o,.,r...,k'--"'O""'rd"""""'er""-..il#.....:-"""9_,,,3'"'"0""8'"""1""0""0'""9'""'9~--------_...~,_._f....        . . ,,_e..._.n~cyY'--....,B.,_eof,opo~rt......__..,j'-":----"'~'+/~A.___ _ _ _ _ __
______ -'----Design Change Package #: lEC-3219 Pkg. 1 See attached pages for Description of Replacement.
i .c,...j
N/A **SVstem Inservice Test Temo. Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4 __ _ Date ( 2 w PSE&G Co. -Nuclear Dept. 19,__'__L_.
                        ~iqn Change Package #: lEC-3256 Pkq. 1 See attached                              pages      for ~cription of Replacement.
Signed _______________
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by Arkwriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on f *-f I , 19 L/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Certificate of Authorization no.                                  36        to use the "NR" stamp expires              Oct. 3, , 19_9_.1_._ __
(/ &#xa3;: -Facto:i:Y Mutual Assn. Date /-/ 1 , 19 C/ &#xa3;/ . Signed YQ-pwV v* 1.,-J____
o                                         ffiE&G Co. -Nuclear Dept.                                                                                                    Principal                Engr.
CommissionstVtf)JJ'l'/
Date    1= "2---<(      19,_r__z:::_. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ __
J. /I/;-/ 1UJ J/ / / (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rsv.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION r&sect;' OR INSTALLATION OF REPLACEMENT($)
(repair organization)                                  (authorized representative)                                                 (title)
0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER Page l of l (name) (repair organization's P .0. no., job. no.,etc.)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of              New Jersey                            and employed by                    Arkwri t Mutual Insuran~ Co of        MA          have inspected the repair, modification or replacement described in this report on                                                  /-/       f              ,  191                  and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
a LI                                  ~                      /                                                                Factory Mutual                                    Engr. Assn.
: 3. Name, address and identification of nuclear power plant ___ S_al7""-_em
                                                                                          ~-
__ Nu_c_l_ear
1 Date      J-J_tf . 19-l.i_. Signed                                                {.                                        Commissions            NE ) (9'/ UA                                            fC.!V 1J (Inspector)                                           (Natl.Bd.No.(including endorsements)state or province and number)
___ Gen __ era __
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
__
NB-81 Rev.6
______ _ Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Reactor Coolant Nuclear Class I 5. a: Component repaired, modified or replaced 1PR2 Valve ------------------------------------
 
b: Name of manufacturer
Page __L of __L FORM NR-1 ATTACHMENT Code Job Package No.: PS93076 Work performed by:      Public Service Electric & Gas co., Nuclear Dept.
-------'C""o""pes==--VUl=-==can=-=--------------------------------------
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner:                  Public Service Electric & Gas co.
c: Identifying nos. 6910-95001-164-2 N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
aurisdictional no.) d: Construction Code W E-Spec E676270 __
: 3. Location:              Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
ANSI B31. 7 1969 E'$ditioa.J970 Add. (addenda)
: 4. System: Main Steam                                                                    Nuclear Class: -=I=I..___ __
: 6. Section XI 1983 Surrrrner 83 (edition) (addenda)
N/A (other) N/A (Code Case(s)) 1969 (year built) I (Code Class) NIA . (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 =Nr-=/A=------(edition)
*1969 (edition) (addenda) 1970 (Code Case(s)) N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E Spec E676270 (addenda) (Code Case(s)) 9. Design responsibilities
_PS_E_&_G
________________________________________
_ 10. Tests conducted:
hydrostatic O pneumatic O design pressure O **pressure NOP psi Code Case(s) __
_____ _ Replaced valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks:
_________
Desiqn Change Package #: lEC-3219 Pkg. 1 See attached pages for Description of Replacement.
N/A **Svstem Inservice Test NOP Temn. NOT CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires act. 3, , 19_9_4 __ _ Date rJ-I 2 f' PSE&G Co.-Nuclear Dept.
Signed _______________
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwrioht Mutual Insurance Co of lYIA have inspected the repair, modification or replacement described in this report on / -if , 19 q l/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date , 1g_jj__. Signed ( M?'\.Zt/
Commissions Mz '1'1 JN if JV J f7] 1-{ c 1* -/
Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION
[gl OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l *orkpertormedby
........
......
___
........
____ (name) (repair organization's P.O. no., job. no.,etc.)
Foot of ButtonwOCJd Road, Hancocks Bridge: NI 08038 (address) (name) Foot of Buttonwood Road, Hanccx::::ks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant ___
t=---'#'-=1=----------
Foot of Buttonwood Road: Hancocks Bridge, NJ 08038 4. System Reactor Coolant Nuclear Class II 5.
b: Name of manufacturer
---=--= ......
c: Identifying nos. __.N;-&#xa5;-/A=-----(mfr's. serial no.) (Nat'l.Bd.No.)
d: Construction Code J?S Spec 69-6445 SGS/M-FD-1
: 6. Section XI (edition) 1983 N/A aurisdictional no.) NIA J (addenda)
SJ l!JD1Jffr 83 (edition) (addenda)
N;/A 1976 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 (edition) (addenda)
N/A (Code Case(s)) *NIA N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *PS Spec S-C-MBJO-MIE-043 (edition) (addenda) (Code Case(s)) 9. Design responsibilities
: 10. Tests conducted:
hydrostatic D pneumatic D design pressure D **pressure WA psi Code Modified pressurizer piping supports. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ _ PSE&G co.-Nuclear Dept. Date i2 -8' 19, Cf-3 . Signed ________________
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION
_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on 2. O 06C. , 19 lf .3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ed or implied, concerning the repair, modification o e I cement described in this report. Furthermore, neither the Inspector nor his employer shall be -ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, any manner for any personal o e ge or a ss f any k" d arising from or connected with this inspection.
* Facto:ry Mutual Engr. Assn. Date zo Dec...' 19 Q 3. Signed Commissions N8 ll.2o :;i. r A) ,4 (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l rk performed by Pnblic Service El ec:tri c & Gas co -Nuclear Dept GIP #PS93-055 (name) (repair organization's P.O. no., job. no.,etc.)
M'oat of But+om,zoaj Raad, Hancacks Bridge, NT 08038 (address) (name) Foot of Buttonwood Road. Hancocks Bridge. NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant __ ..,S.,,a ...
Foat of Buttonwocx]
Road, Hancacks Bridge, NI 08038 4. System Reactor Cool ant Nuclear Class I 5. a: Component repaired, modified or replaced PR!' Pipe Spcxlls Sl-RC-3220 and Sl-RC-3222 b: Name of man.ufacturer
_
c: Identifying.nos. -N-+/ .. (mfr's. serial no.) N/A (Nat'l.Bd.No.)
d: Construction Code ANSI B31 7 1969 ANSI B31.1 1967 (edition)
: 6. Section XI 1983 (edition) 1970 (addenda)
N/A 1974 Uurisdictional no.) (other) (year built) N/A (Code Case(s)) (Code Class) simrrner 83 N/A (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 N._,,/c...:A-=----(edition)
*1969 (edition) (addenda) 1970 (Code Case(s)) N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/ANSI B31.l 1967 (addenda) (Code Case(s)) 9. Design responsibilities
: 10. Tests conducted:
hydrostatic D pneumatic D design pressure D** pressure NOP psi Code
: 11. Description of work Modi fj ed pressurizer relief tank small bore piping. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: _ _..w ..... o ...
...........
Ord ............
..... 3 ..... 0 .... l .... 2-..6 .... l .... 5 .... 0..,._ ________
e .... n .....
Desi gn Change Package j: JEC-3219 Pkg. 1 See attached.
pages for Description of Replacement.
N/A **SVstem Inservice Test Ti=>mn. NOT CERTIRCATEOFCOMPLIANCE Wffcertify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME *code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, ,
__ _ Date f-2 c; u PSE&G Co.-Nuclear Dept. d / / , 19,______L_,L..
Signed ____________
Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by Ark.wriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / *-// , 19.&-/ l/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, *d or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be ny manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date /.-1 I , 1g_j{_. Signed
* Commissions
,1.fF J8"1 Y J:iUIJ A.ff ?7 3
* e, q { ; Facto:cy Mutual EngJ::. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR*1 REPORT OF REPAIR 0 MODIFICATION-q]
OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l ork performed by _ _...Pub ........
... ice,,.,,.'-""'E
.... l.,.ectr""'""" ...... i""c"--"&.__,,Gas
...... .._,Co""""'
*
* .____ _
.... l..___ (name) (repair organization's P.O. no., job. no.,etc.)
Foot of Buttonwood Road. Hancocks Bridge. NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Control Air Nuclear Class II 5.a:
b: Name of manufacturer
__ Mu..tt. .....
.... l,.,,,e..__
__________________________________
_ c: Identifying nos. N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)
Qurisdictional no.) d: Construction Code B31.1 1967/B31.
7 1969 None 6. Section XI (edition) 1983 (edition) (addenda)
Summer 83 (addenda)
{other) None N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.l/B31.
7 1969 *1967 (edition) 1974 (year built) (Code Class) N/A (Code Case(s)) S83
{addenda)
N/A (addenda) (Code Case{s)) None {Code Case{s)) 9. Design responsibilities
--=PS=-=E=&G=-----------------------------------------
: 10. Tests conducted:
hydrostatic D pneumatic
[){ design pressure O **pressure 142 psi Code
: 11. Description of work Added break flanges to pipe spool piece 1CA2310. (use of additional sheet{s) or sketch( es) is acceptable if properly identified) 12.Remarks:
_
_________
Design Change Package #: lEC-3150-1 Rev. o See attached pages for Description of Replacement.
N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, ,
e'1 I/ PSE&G Co. -Nuclear Dept. Date ') -'"'2-L Signed _______________
_ Principal Engr. {repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance of MA have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication N B-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date ) J J f , 1rfL.!___.
Signed 7. Lo-/.__ Commissions/i)fi,!)(C/{
L/V/i ,A)\LJ 7 J . '"'* ,/ ,.,,,-* / Factory Mutual Engr. Assn. {Inspector)
{Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by Public Service Electric & Gas Co. -Nuclear Dept. (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address)
CJP #PS93-073 (repair organization's P .0. no., job. no.,etc.)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 4. system Chemical & Volume Control system Nuclear Class II 5.
__ er _________________________ b: Name of manufacturer
_
=h=o_,,,us=e:...._
_______________________________
_ c: Identifying nos. None N/A N/A N/A __ (mfr's. serial no.} (Nat'l.Bd.No.}
Qurisdictional no.) d: Construction Code ANSI B31. 7 1969 1970 ANSI B31.1 1967 (edition) (addenda)
: 6. Section XI 1983 S1.nnmer 83 (edition) (addenda) (other) None (Code Case(s)} (year built} II (Code Class} N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
S83 N_/_A __ _ (addenda) 1970 (Code Case(s)} *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/ANSI B31.l 1967 (edition) (addenda) (Code Case(s)) 9. Design responsibilities PSE&G ------------------------------------------
: 10. Tests conducted:
hydrostatic
:f;! pneumatic D design pressure O** pressure 170 psi Code escription of work Removal of boric acid blender no longer needed in chemical and (use of additional sheet(s) or sketch( es) is acceptable if properly identified) volume control syst:m and re-installation of piping. 12. Remarks: _
_________
......
Design Change Package #: lEC-3254 Rev. O See attached pages for Description of Replacement.
N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 1 , 193_4 __ _ Date ( * ( l( PSE&G Co. -Nuclear Dept. I / fl 19,__l,i_.
Signed _____________
* Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwriqht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I/, 7 , 1 gCO and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date/.--),)
CommissionsN/)""'t9l/
'&#xa3;;J/t tJf?ZJ / -. ; -/ Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rev 6 FORM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ill TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 *rk performed by Public Service Electric & Gas Co. -Nuclear Dept. CJP #PS93-074 (name) (repair organization's P .0. no., job. no.,etc.)
Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 4. System Chemical & Volune Control System Nuclear Class II 5. a:
__ 7_2_Co_n_tro
__
________________________
_ b: Name of manufacturer Copes Vulcan c: Identifying nos. 6910-95001-187-1 N/A N/A N/A 1971 (mfr's. serial no.) (Nat'l.Bd.No.)
uurisdictional no.) (other) d: Construction Code ANSI B31. 7 1969 1970 N/A fl E-Spec 676270 (edition) (addenda) (Code Case(s)) 6. Section XI 1983 (edition) (addenda) (year built) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 676270 (edition)
*1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) None (Code Case(s)) 9. Design responsibilities
__ PS_E_&G ________________________________________
_ 10. Tests conducted:
hydrostatic
[JX pneumatic D design pressure O *"'Pressure 170 psi Code
: 11. Description of work Replace existing lC'i/172 valve internals in accordance with lEC-3254 (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
Packa: e 1 and re lacernent of bolt' and nuts r revision 1 lEC-3254.
: 12. Remarks: _ _..W,,,,o,,,,,r,,_...k.._,,,O<<>rd,_,,,,,,,er,,,.,,__....J#w:.___.9""""3....,0....,6
.... 1 ... 8 .... l ... 3.._.3..__
________
..... m_..cy"-'l--
..... R,,,.e.,..po
...........
...... n_...n__.,.e'"'-----------
Desiqn Change Package #: lEC-3254 Rev. o See attached pages for Description of Replacement.
**NA T
* 90&deg;F CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 / . 19_9_4 __ Date /j' ,,; PSE&G Co. -Nuclear Dept. / / /
Signed ______________
Principal Engr. (repair organization) v (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / /-1-, 19 tf} and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date J ...-Z-) , 19 . Signed t** Commissions N IJ J f1t./ /ttf/1 /!) ;/f 7} I / q_i_ k / tf F51ct01:y Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 
-,# FORM NR-1 REPORT OF REPAIR 0 MODIFICATION INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by _ _,Pub=-==-=l::.:1::..:'
c=----=S::...;erv==-"-'1=-*
ce=-=---=El=ectr=-=-=1=-*
___ _ (name) (repair organization's P .0. no., job. no.,etc.)
Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 (address) 2.owner __ Pub __ l_i_c_S_erv
__ i_ce __ E_l_ectr __ i_c_and __ Gas __ co_. ________________________
_ (name) Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 (address)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 4. System Main Steam Nuclear Class II 5. a: Component repaired, modified or replaced 1.MSE57, 1.MSE58, 1MSE59, 1.MSE60 COndensate Chambers b: Name of manufacturer COnnex Pipe Systems c: Identifying nos. See Attachment N/A (mfr's. serial no.) (Nat'l.Bd.No.)
d: Construction Code See Attachment
: 6. Section XI (edition) 1983 N/A Ourisdictional no.) N/A (addenda)
Sl..nmner 83 (edition) (addenda) (other) N/A (Code Case(s)) N/A 1993 (year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 (edition) (addenda) 1989 (Code Case(s)) *1989 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 F.d. 1970 Add. (edition) (addenda) (Code Case(s)) 9. Design responsibilities
_PS __ E_&G ________________________________________
_ 10. Tests conducted:
hydrostatic
[JC pneumatic D design pressure D *-J;:iressure 1400psi Code Case(s)_--=N'-"/'-'A=--------
escription of work Installed new condensate chambers for #11 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: _
_.N;LI.J/O...OA....__
______ _ Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ _ Date { -a-c1 PSE&G co.-Nuclear Dept. / / / ....
Signed ____________
Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on -I , 199 '( and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication N B-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
C / .I __. _ Facto:cy Assn. Date / *-1-'{ , 19-5....!L._.
Signed./ t
* Commissions
;J{) f1'it 1AJ;1 /UJ J J J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 r -Page _2_ of _2_ FORM NR-1 ATTACHMENT Code Job Package No.: PS93075
* Work performed by: 2. Owner: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Public Service Electric & Gas Co. 3. Location:
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System:
Nuclear Class:  
==============================================================================
==============================================================================
ID of Component Replacement:
ID of Component Replacement: 1MSE61 Condensate Chamber Name of Manufacturer: ----=C=o=n=n=e=x:,::........,P::...=ip==e-=S~y=s~t=e=m..____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
1MSE57 Condensate Chamber Name of Manufacturer:
43471        N/A           N/A                               N/A                 1993                =N~o..______________
___
Se.rial No. Nat'l. Bd. Jurist No.                               Other             Year Built             ASME Code Stamp'd.?
___________________
Original Const. Code: ASME III 1989                                       Edition 1989 Addenda, Code Class ~
___, 43471 N/A N/A N/A 1993 Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code stamp*d.?
Code Cases: N/A         ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE62 Condensate Chamber Name of Manufacturer: ----=C~o~n=n=e=x""-'P~1=*p~e=-=s~y=s~t~e~m..____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class z___ Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ------------------------------------------------------------------------------
43472        N/A           N/A                               N/A                 =1~9~9~3..____,..__  No Serial No. Nat'l. Bd. Jurist No.                                 Other             Year Built             ASME Code Stamp'd.?
ID of Replacement:
Replacement Const. Code: ASME III 1989                                           Edition 1989 Addenda, Code Class ~-
1MSE58 Condensate Chamber Name of Manufacturer:
Code Cases:N/A                 ANSI B31.7 1969 Ed. 1970 Add
___
==============================================================================
________________
ID of Component Replaced: _,...N"'-""A"------------------------~
_ 434 72 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. *code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add ASME Code Stamp'd.?
Addenda, Code Class L ==============================================================================
ID of Component Replaced:
Name of Manufacturer:  
'al No. Nat'l. Bd. Jurist No. ginal Const. Code: Other Year Built ASME Code Stamp'd.?
Edition Addenda, Code Class Code Cases: ---ID of Replacement:
1MSE59 Condensate Chamber Name of Manufacturer: 4 3 4 7 3 N
/A N /A N /A S er i al No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stci.mp'd.?
Addenda, Code Class L ==============================================================================
ID of Component Replaced:
Name of Manufacturer:
Serial.No.
Nat'l. Bd .. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.?
Edition Addenda, Code Clas$ Code Cases: ________ _
ID of Replacement:
1MSE60 Condensate Chamber Name of Manufacturer:
Connex Pipe System 43474 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built No ASME Code Stamp'd.?
acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .6.._ Cases:N/A ANSI B31.7 1969 Ed. 1970 Add ============================================================================== . ' _______ ..--&#xa3;.,, ___ ----* ---**------------------------* -" * * * -: **
FORM NR-1 REPORT OF REPAIR D OR INSTALLATION OF REPLACEMENT(S)
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 (name) (repair organization's P .0. no., job. no.,etc.)
Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Stearn Nuclear Class II b: Name of manufacturer Pipe Systems c: Identifying nos. See Attachment N/A (mfr's. serial no.) (Narl.Bd.No.)
d: Construction Code See Attachment
: 6. Section XI (edition) 1983 (edition)
N/A Ourisdictional no.) N/A (addenda)
SUrnmer 83 (addenda)
N/A 1993 (other) (year built) N/A (Code Case(s)) (Code Class) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 Ed. 1970 Add. (edition)
*1989 (edition) (addenda) 1989 (Code Case(s)) N/A (addenda) (Code Case(s)) 9. Design responsibilities
_______________________________________
_ 10. Tests conducted:
hydrostatic
[){ pneumatic D design pressure D **pressure 1400psi Code Case(s) _ __,,N""/'-'A,_,,__
_____ _ escription of work Installed new chambers for #12 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: _ __,_,W=o,.,r...,k'--"'O""'rd"""""'er""-..il#
.....
.... i ...... c,...j
______ _
Change Package #: lEC-3256 Pkq. 1 See attached pages for of Replacement.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_.1_.
__ _ Date 1= "2---<( o ffiE&G Co. -Nuclear Dept. 19,_r__z:::_.
Signed ______________
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Co of MA have inspected the repair, modification or replacement described in this report on /-/ f , 191 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date J-J_tf . 19-l.i_. Signed {. Commissions NE ) (9'/ UA fC.!V 1J a LI / 1 Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Page __L of __L FORM NR-1 ATTACHMENT Code Job Package No.: PS93076 Work performed by: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 3. Location:
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Main Steam Nuclear Class: -=I=I..__
__ _ ==============================================================================
ID of Component Replacement:
1MSE61 Condensate Chamber Name of Manufacturer:
________________
_ 43471 N/A N/A N/A 1993
___________
_ Se.rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement:
1MSE62 Condensate Chamber Name of Manufacturer:
________________
_ 43472 N/A N/A N/A
__ Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.?
Addenda, Code Class ==============================================================================
ID of Component Replaced:
e of Manufacturer:
e of Manufacturer:
ial No. Nat'l. Bd. jurist No. Other Year Built ASME Code stamp'd.?
ial No. Nat'l. Bd. jurist No.                                 Other             Year Built             ASME Code stamp'd.?
Original Const. Code: Edition Addenda, Code Class Code Cases: _____ _ ID of Replacement:
Original Const. Code:                                                     Edition                   Addenda, Code Class Code Cases: _ _ _ _ __
1MSE63 Condensate Chamber Name of Manufacturer:
ID of Replacement: 1MSE63 Condensate Chamber Name of Manufacturer: ___,.=.C~o=n=n=e=x--..-P~1~*p~e=-s~y--=s~t~e~m,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~
________________ 43473 N/A N/A. N/A 1993. __ _ Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.?
43473       N/A           N/A.                             N/A                 1993._ __           No
Addenda, Code Class ==============================================================================
                                                                                                            *~--------~
ID of Component Replaced:
Serial No. Nat'l. Bd. Jurist No.                                 Other             Year Built             ASME  Code Stamp'd.?
Replacement Const. Code: ASME III 1989                                           Edition 1989 Addenda, Code Class ~
Code Cases:N/A                 ANSI B31.7 1969 Ed. 1970 Add
==============================================================================
ID of Component Replaced: _,...N~A"-------~--~--~--~--~--~-~
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code stamp'd.?
Serial No. Nat'l. Bd.       Jurist No.                           Other             Year Built             ASME Code stamp'd.?
Edition Addenda, Code Class Code Cases: ---
Original Const. Code:                                                    Edition                   Addenda, Code Class Code Cases:
ID of Replacement:
---------------~--------------------------------------------------------------
1MSE64 Condensate Chamber Name of Manufacturer:
ID of Replacement: 1MSE64 Condensate Chamber Name of Manufacturer: ----=C~o~n=n=e=x~P~i~*p~e=-=S~y=s~t=e=m..____ _ _ _ _ _ _ _ _ _ _ _ _~---
_____________ 43474 N/A N/A N/A ial No. Nat'l. Bd. Jurist No. Other Year Built lacement Const. Code: ASME III 1989 Edition 1989 e Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.?
43474       N/A           N/A                               N/A                 =1~9~9~3..____,.._  No ial No. Nat'l. Bd. Jurist No.                                 Other             Year Built             ASME Code Stamp'd.?
Addenda, Code Class a_ ==============================================================================
lacement Const. Code: ASME III 1989                                           Edition 1989 Addenda, Code Class a_
-:-.. FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 8 OR INSTALLATION OF REPLACEMENT(S)
e Cases:N/A               ANSI B31.7 1969 Ed. 1970 Add
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by Public SeJ::vice Electric & Gas Co. -Nuclear Dept. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
==============================================================================
Public Sei:vice Electric and Gas Co. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
 
CJP #PS93-077 (repair organization's P.O. no., job. no.,etc.)
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 8 OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Steam Nuclear Class II 5.a: __
ork performed by     Public SeJ::vice Electric & Gas                             Co. - Nuclear Dept.                               CJP #PS93-077 (name)                               (repair organization's P.O. no., job. no.,etc.)
__ E_6_6 ....
Foot of Buttonwood Road,                     Hancocks Bridge, NJ                         08038 (address)
__
Public Sei:vice Electric                     and Gas Co.
__ __ ___________
(name)
_ b: Name of manufacturer Connex Pipe Systems c: Identifying nos. See Attachment N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)
Foot of Buttonwood Road,                       Hancocks Bridge, NJ                         08038 (address)
Qurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda)
: 3. Name, address and identification of nuclear power plant                 Salem Nuclear Generating Station                                       Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
SUrnmer 83 (edition) (addenda) (other) N/A N/A {Code Case(s)) 1993 (year built) II (Code Class) NIA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
: 4. System         Main Steam                                                                                                                     Nuclear Class I I 5.a: Componentrepa~ed,modffiedorre~aced _~              __E_6_5~,-~      __ E_6_6....,~~--E_6_7~,-~      __E_6_8_C_o_~_ensa    _ _~    __   ~ _ _ _ _ _ _ _ _ _ _ __
S83
b: Name of manufacturer             Connex Pipe Systems c: Identifying nos. See Attachment                     N/A                                    N/A                               N/A                         1993 (mfr's. serial no.)         (Nat'l.Bd.No.)               Qurisdictional no.)                    (other)                                  (year built) d: Construction Code       See Attachment                             N/A                                             N/A                                    II (edition)                     (addenda)                                     {Code Case(s))                           (Code Class)
__ (addenda) 1989 (Code Case(s)) *1989 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 Ed. 1970 Add. (edition) (addenda) (Code Case(s)) 9. Design responsibilities  
: 6. Section XI                        1983                                          SUrnmer 83                                                                          NIA (edition)                                                  (addenda)                                                    (Code Case(s))
--=PS=-=E=-=-&G'-=-------------------------------------------
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983                                     S83                N~/'--=A_,,____ _
: 10. Tests conducted:
(edition)       (addenda)         (Code Case(s))
hydrostatic pneumatic D design pressure D** pressure 1400 psi Code  
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                         *1989                1989              N/A
....
                                                  *ASME III/ANSI B31.7 1969 Ed. 1970 Add.                                             (edition)           (addenda)         (Code Case(s))
escription of work Installed new condensate chambers for #13 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 9. Design responsibilities - - = P S = - = E = - = - & G ' - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
: 12. Remarks:
: 10. Tests conducted: hydrostatic ~                pneumatic     D     design pressure D** pressure                   1400 psi           Code Case(s)_~N..../~A~------
_________
escription of work     Installed new condensate chambers for #13 main steam header.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: -~W~o=r~k~O=rd=er~~#~:~9~3~0~8~1=0~0=9~9_ _ _ _ _ _ _ _ _~De~f~i=c~i~en~cy.'1--~R=e""'po~rt~~#~:~N:..,.,.....IA~--------
Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 1 , 1!9_4 __ _ Date 1 --i--<-( PSE&G Co.-Nuclear Dept. 19,___f_L.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Signed _______________
Certificate of Authorization no.                 36       to use the "NR" stamp expires Oct. 3 1                         , 1!9_4 Date     1- -i--<-(
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /-I and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
PSE&G Co.-Nuclear Dept.
Date /-2-j , Signed lArvl--Commissions NB fr1{ J:ttJ/.} 1UJ ]7 J . / , Facto:ry Mutual EfBr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Work performed by: 2. Owner: 3. Location:
19,___f_L. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 4. System: Main Steam FORM Page _L of __,L *:
Principal             Engr.
Package No.: PS93077 ;;.  
(repair organization)                               (authorized representative)                           (title)
.< :._: .. -Public service Nuclear Dept. Foot of Buttonwood Road-Hancbcks 1 Bridge, NJ 08038 Public Service Electric'&;
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of       New Jersey               and employed by                   Arkwri t Mutual Insurance Co of       MA             have inspected the repair, modification or replacement described in this report on                       /-I                           and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Gas>;co. Foot of Buttonwood Road',.-:Hanccicks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Nuclear Class:  
                                .                ~                    /      ,                                                Facto:ry Mutual                EfBr.        Assn.
Date     /-2-j         , 1~.          Signed       ~z:. lArvl--                                           Commissions       NB fr1{             J:ttJ/.} 1UJ ]7J (Inspector)                                       (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
FORM  NR3J:~~~;;;~;~,,*-                                          Page _L of __,L
                                              *: ;.'.ff:~:.;.;.:,;:~ca*d~~'rrt>b Package No.: PS93077
                                                ;;. ::;:~;:/:!::~\*~ .~'/ih{?* .< :._: .. -
Work performed by:    Public service Elec:itric~:&-:..Gas'.-co. 1 Nuclear Dept.
Foot of Buttonwood Road- Hancbcks Bridge, NJ 08038
: 2. Owner:                Public Service Electric'&; Gas>;co.
Foot of Buttonwood Road',.- :Hanccicks Bridge, NJ 08038
: 3. Location:            Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. System: Main Steam                                                Nuclear Class: --=I=I"----~
==============================================================================
==============================================================================
ID of Component Replacement:
ID of Component Replacement: 1MSE65 Condensate Chamber Name of Manufacturer: Connex Pipe System 43471       N/A      ~7.N~/~A~~~-~N~/7-A~=----1-9_9_3_____                          N_o-------~
1MSE65 Condensate Chamber Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No.         Other             Year Built                   ASME Code Stamp'd.?
Connex Pipe System 43471 N/A
Original Const. Code: ASME III 1989         Edition 1989 Addenda, Code Class ~
_____
Code Cases: N/A       ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE66 condensate Chamber Name of Manufacturer: ......,;:C=o=n=n=e=x=--=P~i~p~e;_::S~y~s=t==e=m=--~~~~~~~~~~~~~~~~~-
Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
43472       N/A         N/A           N/A                 =1=9=9~3~----=-~          No Serial No. Nat'l. Bd. Jurist No.         Other             Year Built                   ASME Code Stamp'd.?
Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement:
Replacement Const. Code: ASME III 1989                 Edition 1989 Addenda, Code Class .2._
1MSE66 condensate Chamber Name of Manufacturer:
Code Cases:N/A             ANSI B31.7 1969 Ed. 1970 Add
43472 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.?
========================================~=====================================
Addenda, Code Class .2._
ID of Component Replaced:   _l::!Lb~~~~~~~~~~~~~~~~~~~~~~~~
ID of Component Replaced:
e of Manufacturer:
e of Manufacturer:
ial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
ial No. Nat'l. Bd. Jurist No.       Other             Year Built                   ASME Code Stamp'd.?
Original Const. Code: Edition Addenda, Code Class Code Cases: ---ID of Replacement:
Original Const. Code:                       Edition                           Addenda, Code Class Code Cases: - - -
1MSE67 Condensate Chamber Name of Manufacturer:
ID of Replacement: 1MSE67 Condensate Chamber Name of Manufacturer: Connex Pipe System
Connex Pipe System 43473 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.?
                      ~~~==-=-=--~-=-"-=-~-=-'....~~~~~~~~~~~~~~~~~~
Addenda, Code Class ==============================================================================
43473       N/A         N/A           N/A                 _1_9_9_3~-~                No    *~~~~~~~~~~~
ID of Component Replaced:
Serial No. Nat'l. Bd. Jurist No.         Other             Year Built                     ASME Code Stamp'd.?
Replacement Const. Code: ASME III 1989                 Edition 1989 Addenda, Code Class ~-
Code Cases:N/A             ANSI B31.7 1969 Ed. 1970 Add
==============================================================================
ID of Component Replaced:   -FN~A=--~~~~~~~~~~~~~~~~~~~~~~~~
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No.     Other             Year Built                     ASME Code Stamp'd.?
Edition Addenda, Code Class Code Cases: ---ID of Replacement:
Original Const. Code:                        Edition                           Addenda, Code Class Code Cases: - - -
1MSE68 Condensate Chamber Name of Manufacturer:
ID of Replacement: 1MSE68 Condensate Chamber Name of Manufacturer: ~C~o=n=n=e=x=--~P=i=p~e:;__:s~y~s~t~e~m~~~~~~~~~~~~~~~~~~-
43474 N/A N/A N/A ial No. Nat'l. Bd. Jurist No. Other Year Built No AS ME Code Stamp'd.?
43474        N/A        N/A            N/A                 =1=9=9=3~-~                No   *~~~~~--:~~-:--::--=:-
acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .2._ e Cases:N/A ANSI B31.7 1969 Ed. 1970 Add ==============================================================================
ial No. Nat'l. Bd. Jurist No.        Other              Year Built                    AS ME Code Stamp'd.?
I rn .. -nwwrnrrT -or rw :; I r .... FORM NR-1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by Public SeJ:Vice Electric & Gas Co. -Nuclear Dept. CJP #PS93-078
acement Const. Code: ASME III 1989                 Edition 1989 Addenda, Code Class .2._
{name) {repair organization's P.O. no., job. no.,etc.)
e Cases:N/A             ANSI B31.7 1969 Ed. 1970 Add
Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 {address)
==============================================================================
{name) Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 {address)
 
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 4. System Main Steam Nuclear Class II b: Name of manufacturer Connex Pipe Systems c: Identifying nos. See Attachment N/A N/A {mfr's. serial no.) {Narl.Bd.No.)
I rn .. -nwwrnrrT -or                             rw :; I   r FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2
Uurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 {addenda)
ork performed by       Public SeJ:Vice Electric &                               Gas Co. - Nuclear Dept.                                               CJP #PS93-078
SUrrnner 83 {edition)
{name)                                     {repair organization's P.O. no., job. no.,etc.)
{addenda)
Foot of Buttonwood Road,                           Hancocks Bridge, N.J                       08038
{other) N/A N/A {Code Case{s)) 1993 (year built) II (Code Class) N/A {Code Case{s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 {edition)
{address)
S83
{name)
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31. 7 1969 F.d. 1970 Add. *1989 (addenda) 1989 {Code Case{s)) N/A (edition)
Foot of Buttonwood Road,                           Hancocks Bridge, N.J                       08038
{addenda)
{address)
{Code Case{s)) 9. Design responsibilities
: 3. Name, address and identification of nuclear power plant                       Salem Nuclear Generating Station                                                       Unit #1 Foot of Buttonwood Road, Hancocks Bridge, N.J 08038
_PS_E_&G _________________________________________
: 4. System           Main Steam                                                                                                                                           Nuclear Class I I 5.~ Componentrepa~ed,modffiedorre~~ed~~~=E~6~94,~~~~~~~0~,~~~~~~1~,~~~~~~2~Co~~~=~~~~~~~~~~~~-------
_ 10. Tests conducted:
b: Name of manufacturer              Connex Pipe Systems c: Identifying nos. See Attachment                       N/A                                    N/A                                      N/A                                           1993
hydrostatic (8: pneumatic D design pressure D **pressure 1400 psi Code scription of work Installed new condensate chambers for #14 rnain steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
{mfr's. serial no.)               {Narl.Bd.No.)               Uurisdictional no.)                         {other)                                                     (year built) d: Construction Code        See Attachment                                  N/A                                             N/A                                                           II (edition)                          {addenda)                                    {Code Case{s))                                                   (Code Class)
: 12. Remarks:
: 6. Section XI                          1983                                            SUrrnner      83                                                                                            N/A
_________
{edition)                                                      {addenda)                                                                              {Code Case{s))
De..,,,.,_f..._1...,'
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                         1983                         S83                  =Nl--'/A~--
c,,..1...,'
{edition)                       (addenda)        {Code Case{s))
..... A...__ ______ _ Design Change Package #: lEC-3256 Pkg. 1 See attached pages for Description of Replacement.
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                     *1989                              1989                N/A
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ _ PSE&G Co. -Nuclear Dept. # p-/ -.... Date /-'2---Lr Signed ________________
                                                    *ASME III/ANSI B31. 7 1969 F.d. 1970 Add.                                                     (edition)                          {addenda)           {Code Case{s))
_,, Principal Engr. {repair organization)
: 9. Design responsibilities _PS_E_&G     _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
{authorized representative)
: 10. Tests conducted: hydrostatic (8:              pneumatic D              design pressure D **pressure                    1400 psi                    Code Case(s)_-=N~/-=A-=-------
{title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of :MA. have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ,c; / Facto:ry Mutual Assn. Date r-J. 'i ' 1 M_. Signed L twL-Commissions
scription of work      Installed new condensate chambers for #14 rnain steam header.
;Jp f"f<ft/ f .UJtf 4Il 1J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.s FORM NR-1 ATTACHMENT Code Job Package No.: PS93078 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 3. Location:
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
Salem Nuclear Generating station .,,; .. Foot of Buttonwood Road, Hancocks Bridge, NJ' 08038. 4. System: Main Steam Nuclear Class: II ==============================================================================*
: 12. Remarks: -~W~o=r=k~O=rd=e=r'--"#__,,_:-=9=3-"'0=8_...l,,,_0,,,.09=9<<--_ _ _ _ _ _ _ _ _De.., ,.,_f.. _1.. ,c,,..1...,'
ID of Component Replacement:
                                                                                                                        ' en~cy_~_...R_,,,,e"'1'po'&deg;"""rt_,,.___,:/t,_.:'---'-N;&#xa5;-/.....A...___ _ _ _ _ __
1MSE69 Condensate Chamber Name of Manufacturer:
Design Change Package #: lEC-3256 Pkg. 1 See attached pages for Description of Replacement.
________________
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
_ 43471 N/A N/A N/A 1993 Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
Certificate of Authorization no.                  36          to use the "NR" stamp expires            Oct. 3,              , 19_9_4_ __
Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class 2,___ Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement:
Date    /-'2---Lr PSE&G Co. -Nuclear Dept.
1MSE70 Condensate Chamber Name of Manufacturer:
19,~ Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,, ~ ~
________________
                                                                                                                          # p- /                          -....                     Principal                Engr.
_ 43472 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.?
{repair organization)                                {authorized representative)                                                 {title)
Addenda, Code Class .a_ ==============================================================================
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of          New Jersey                  and employed by                    Arkwri ht Mutual Insurance Co of        :MA.           have inspected the repair, modification or replacement described in this report on                                                                                    and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
ID of Component Replaced:
                                                                        ,c; /                                                            Facto:ry Mutual ~. Assn.
Date      r- J. 'i ' M_. 1            Signed                          L      twL-(Inspector)
Commissions      ;Jp f"f<ft/ f .UJtf 4Il 1J (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.s
 
Page~ of~
FORM NR-1 ATTACHMENT Code Job Package No.: PS93078 Work performed by:    Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner:               Public Service Electric & Gas Co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 3. Location:             Salem Nuclear Generating station                                    .,,;..
Foot of Buttonwood Road, Hancocks Bridge, NJ' 08038.
: 4. System: Main Steam                                                    Nuclear Class: I I
==============================================================================*
ID of Component Replacement: 1MSE69 Condensate Chamber Name of Manufacturer: --C~o=n=n=e=x""'-'P=-=i_p~e-=s_y~s~t~e=m..__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
43471        N/A          N/A                        N/A              1993        _N~o~---------
Serial No. Nat'l. Bd. Jurist No.                        Other          Year Built    ASME Code Stamp'd.?
Original Const. Code: ASME III 1989                            Edition 1989 Addenda, Code Class 2,___
Code Cases: N/A        ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE70 Condensate Chamber Name of Manufacturer: ---=C=o=n=n=e=x"'-'P=-=ip==e-=S-v~s~t=e=m,.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
43472        N/A          N/A                        N/A            =1~9~9~3~-  No Serial No. Nat'l. Bd. Jurist No.                        Other        Year Built    ASME Code Stamp'd.?
Replacement Const. Code: ASME III 1989                              Edition 1989  Addenda,  Code Class .a_
Code Cases:N/A              ANSI B31.7 1969 Ed. 1970 Add
==============================================================================
ID of Component Replaced: _;=...N----=-A=-----------------------~
e of Manufacturer:
e of Manufacturer:
ial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code stamp'd.?
ial No. Nat'l. Bd.     Jurist No.                   Other         Year Built     ASME Code stamp'd.?
Original Const. Code: Edition Addenda, Code Class Code Cases: ---ID of Replacement:
Original Const. Code:                                         Edition           Addenda, Code Class Code Cases: - - -
1MSE71 Condensate Chamber Name of Manufacturer:
ID of Replacement: 1MSE71 Condensate Chamber Name of Manufacturer: ---=C~o=n=n=e=x""'-'P=-=i_p=e--=s_y~s~t=e=m,.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
________________
43473       N/A           N/A                       N/A             =1~9~9~3~-  No*------,,---,-------
_ 43473 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No *------,,---,-------
Serial No. Nat'l. Bd. Jurist No.                       Other         Year Built     AS ME Code Stamp'd.?
AS ME Code Stamp'd.?
Replacement Const. Code: ASME III 1989                             Edition 1989 Addenda, Code Class .a_
Addenda, Code Class .a_ ==============================================================================
Code Cases:N/A               ANSI B31.7 1969 Ed. 1970 Add
ID of Component Replaced:
==============================================================================
ID of Component Replaced: ----=N~A"------------------------~
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd.     Jurist No.                   Other         Year Built     ASME Code Stamp'd.?
Editibn Addenda, Code Class Code Cases: ---ID of Replacement:
Original Const. Code:                                          Editibn         Addenda, Code Class Code Cases: - - -
1MSE72 Condensate Chamber Name of Manufacturer:
ID of Replacement: 1MSE72 Condensate Chamber Name of Manufacturer: _-C~o=n=n=e=x"'-'P=-=ip_.=e--=s_y~s~t=e=m~------------------
43474 N/A N/A N/A  
43474       N/A           N/A                       N/A             =1=9=9=3~--  No
' al No. Nat'l. Bd. Jurist No. Other Year Built No ASME Code Stamp'd.?
  ' al No. Nat'l. Bd. Jurist No.                       Other         Year Built     ASME Code Stamp'd.?
acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .a_ Cases:N/A ANSI B31.7 1969 Ed. 1970 Add ==============================================================================
acement Const. Code: ASME III 1989                             Edition 1989 Addenda, Code Class .a_
FORM NR-1 REPORT OF REPAIR D OR INSTALLATION OF REPLACEMENT(S)
Cases:N/A             ANSI B31.7 1969 Ed. 1970 Add
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by Public Sei:vice Electric & Gas Co. -Nuclear Dept. CJP #PS93-079 (name) (repair organization's P .0. no., job. no.,etc.)
==============================================================================
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
 
: 3. Name. address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Steam Nuclear Class II 5. a: Component repaired, modified or replaced 1C-MSG-2532A&B, 1C-MSG-2533A&B SUpports b: Name of manufacturer c: Identifying nos. N/A N/A N/A N/A ---=1=-9=-93=--------(mfr's. serial no.) (Nat'l.Bd.No.)
FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2
Uurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda) summer 83 (edition) (addenda) (other) N/A (Code Case(s)) (year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
rk performed by     Public Sei:vice Electric & Gas Co. - Nuclear Dept.                                                             CJP     #PS93-079 (name)                               (repair organization's P .0. no., job. no.,etc.)
S83
Foot of Buttonwood Road,                       Hancocks           Bridge,         NJ       08038 (address)
__ _ 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B3l.7/PS Spec S-C-MBCX:>-MLB-043, 1985 *1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities
(name)
_PS __ E_&G _________________________________________
Foot of Buttonwood Road,                     Hancocks           Bridge,         NJ       08038 (address)
_ 10. Tests conducted:
: 3. Name. address and identification of nuclear power plant                 Salem Nuclear Generating Station                                       Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
hydrostatic D pneumatic D design pressure D ** pressure N/A psi Code
: 4. System       Main Steam                                                                                                                       Nuclear Class II
: 11. Description of work Installed supports for condensate pots on #11 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 5. a: Component repaired, modified or replaced 1C-MSG-2532A&B, 1C-MSG-2533A&B SUpports b: Name of manufacturer -~PS~E=&G~~-------------------------------------
: 12. Remarks:  
c: Identifying nos. N/A                               N/A                                     N/A                             N/A                     ---=1=-9=-93=--------
....
(mfr's. serial no.)         (Nat'l.Bd.No.)               Uurisdictional no.)                    (other)                                  (year built) d: Construction Code       See Attachment                             N/A                                            N/A                                     II (edition)                       (addenda)                                     (Code Case(s))                           (Code Class)
c=1='  
: 6. Section XI                        1983                                        summer        83                                                                      N/A (edition)                                                  (addenda)                                                      (Code Case(s))
......
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                         1983           S83                N~/_A_ __
(edition)        (addenda)        (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                         *1969              1970                N/A
                                          *ANSI B3l.7/PS Spec S-C-MBCX:>-MLB-043, 1985                                               (edition)           (addenda)         (Code Case(s))
: 9. Design responsibilities _PS__E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 10. Tests conducted: hydrostatic D               pneumatic D         design pressure D** pressure N/A psi                               Code Case(s)_~N'-"-/~A~------
: 11. Description of work       Installed supports for condensate pots on #11 main steam header.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: -~W=o=r~k~O=rd=er~....         #~:_9=3=0=8=1=0=0=9~1~--------~De=f~i=*c=1='en=-=cy~~R=e""'po=rt~......                           #~=~N:,_/A~-------
Desiqn Change Package #: lEC-3256 Pkg. 1 See attached pages for Description of Replacement.
Desiqn Change Package #: lEC-3256 Pkg. 1 See attached pages for Description of Replacement.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, . 199_4 __ _ Date /-3 9 PSE&G Co. -Nuclear Dept.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Signed _______________
Certificate of Authorization no.                 36     to use the "NR" stamp expires             Oct. 3,             . 199_4 9 ~ Signed_ _PSE&G                   Co. -Nuclear Dept.                                                                       Principal Engr.
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on //-// , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore.
Date    /-3            19,~.                          _ _ _ _ _ _ _ _ _ _ _ _ __
neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
(repair organization)                               (authorized representative)                           (title)
Date /-J'.-'J , 1M. Signed*tvnui.
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of       New Jersey               and employed by                   Arkwri ht Mutual Insurance Co of       MA           have inspected the repair, modification or replacement described in this report on                     //-//             , 19           and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty,
__
                                                                    -/
Commissions&#xb5;/Jfl1t/MJA t</J)J} 9 -/ /1 Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 ATTACHMENT Page _L of _L Code Job Package No.: PS93079 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:
sed or implied, concerning the repair, modification or replacement described in this report. Furthermore. neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Salem Nuclear Generating Station Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 System: Main Stearn Nuclear Class: II of Manufacturer:
Factory Mutual Engr. Assn.
Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Starnp'd.?
Date     /-J'.-'J ,   1 M . Signed*tvnui.__
original Const. Code: Edition Addenda, Code Class  
9          ,,.,f-~-
.. 'o of Replacement:
(Inspector)
lC-MSG-2532 A&B Supports ''ame of Manufacturer:
                                                                              /1 Commissions&#xb5;/Jfl1t/MJA t</J)J}
PSE&G A N/A N/A N/A erial No. Nat'l. Bd. Jurist No. Other Year Built . eplacernent Const. Code: ANSI B31. 7 1969 Edition 1970 ;/Code Cases :N/A PS Spec S-C-MBOO-MDS-043 1985 No *-----------
(Natl.Bd.No.(including endorsements)state or province and number)
AS ME Code Starnp'd.?
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
Addenda, Code Class II
NB-81 Rev.6
;Yfif ID of Component Replaced:
 
1(\> e of Manufacturer:
Page _L of _L FORM NR-1 ATTACHMENT Code Job Package No.: PS93079 Work performed by:   Public Service Electric & Gas Co., Nuclear Dept.
,-,,_.,, f*:/ rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Starnp'd.?
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 owner:               Public Service Electric & Gas Co.
Original Const. Code: Edition Addenda, Code Class Code Cases: ----ID of Replacement:
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:           Salem Nuclear Generating Station Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 System: Main Stearn                             Nuclear Class: II ID~~~;=~~:;~~=~~=;:;~=~=~7==;=~================================================
lC-MSG-2533 A&B Supports Name of Manufacturer:
            **'~hne  of Manufacturer:
PSE&G --='-=-'===-------------------------'----,-
Serial No. Nat'l. Bd.         Jurist No. Other   Year Built       ASME Code Starnp'd.?
N /A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code PS Spec S-C-MBOO-MDS-043 1985 No , ...
original Const. Code:                           Edition           Addenda, Code Class
,,.*. Serial No. Nat'l. Bd. Original Const. Code: Jurist No. Other Year Built ASME Edition Addenda,<C9.g:
          "-";.~~=-:::::~-------------------------------------------------------------------------
Code Cases: ----.  
            'o of Replacement: lC-MSG-2532 A&B Supports
------------....... J., ..
          ''ame of Manufacturer: PSE&G
                                      ---~~=---------------------------
A           N/A         N/A         N/A     =1=9=9=3~--,-~  No erial No. Nat'l. Bd. Jurist No.         Other   Year Built       AS*-----------
ME Code Starnp'd.?
          . eplacernent Const. Code: ANSI B31. 7 1969       Edition 1970 Addenda, Code Class II
        ;/Code Cases :N/A                 PS Spec S-C-MBOO-MDS-043 1985
~,~;i:{***==============================================================================
;Yfif ID of Component Replaced: ~N~A=-------------------------
(\>
-,,_.,,         e of Manufacturer:
*:/
rial No. Nat'l. Bd.       Jurist No. Other   Year Built       ASME Code Starnp'd.?
Original Const. Code:                           Edition         Addenda, Code Class Code Cases: ----
ID of Replacement: lC-MSG-2533 A&B Supports Name of Manufacturer: PSE&G N/A              N/A
                                      --='-=-'===-------------------------'----,-
N/A         N/A     =1=9=9=3~~~    No                        , ...**:~.- ,,.*.
Serial No. Nat'l. Bd. Jurist No.             Other   Year Built Replacement Const. Code: ANSI B31.7 1969           Edition 1970 Code Cases:N/A~-                PS Spec S-C-MBOO-MDS-043 1985 Serial No. Nat'l. Bd.         Jurist No. Other   Year Built       ASME 9Q.~r*.;.
Original Const. Code:                          Edition         Addenda,<C9.g:
Code Cases: - - - -                                                     ~ ~ . _:;:~~,*:~~:~~}~
                                                        ---- ---- ----             .......J., .. ,,,~
          ~~-~;-;~~~~~~~~~~~--------------------------------------~-~~*~~~'.
Name of Manufacturer:
Name of Manufacturer:
ial No. Nat'l. Bd. Jurist No. lacernent Const. Code: e Cases: ----Other 
ial No. Nat'l. Bd. Jurist No.         Other lacernent Const. Code:
-' FGRM NR-1 REPORT OF REPAIR 0 MODIFICATION
e Cases: - - - -
[l OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by
 
__ (name) (repair organization's P .0. no., job. no.,etc.)
            -   ' FGRM NR-1 REPORT OF REPAIR 0 MODIFICATION [l OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2
Foot of Buttonwood Road, Hancocks Bridge, ID 08038 (address) 2.owner __ Pub __ l_1_'c_S_erv
rk performed by   _.....:Pub::...=.::..:l=i=c=--=S:....:erv=-::...:i=-::ce:::.=......::E==l=-::ectr=.:=i:.=c=--=&_Gas==--...:Co=*=-----___!:Nu=c==l:.::e:::::e~ir:_!:::De=p~t:..!.._ ___:CJP~!:........:#11.:PS~9~3~-~0~8~0~----
__ 1_'ce __ E_l_ectr_--'-1='c_.....:and=--_Gas.c:__:_:_Co-=--*-------------------------(name) Foot of Buttonwood Road, Hancocks Bridge, ID 08038 (address)
(name)                                                 (repair organization's P .0. no., job. no.,etc.)
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, ID 08038 4. System Main Steam Nuclear Class II 5.a:
Foot of Buttonwood                             Road, Hancocks                                 Bridge,                 ID           08038 (address) 2.owner _ _Pub    __l_1_'c_S_erv     __1_'ce     __E_l_ectr_--'-1='c_.....:and=--_Gas.c:__:_:_Co-=--*-------------------------
___
(name)
b: Name of manufacturer
Foot of Buttonwood Road, Hancocks Bridge, ID 08038 (address)
___ PS_E_&G _____________________________________
: 3. Name, address and identification of nuclear power plant                                                   Salem Nuclear Generating Station                                                               Unit #1 Foot of Buttonwood Road, Hancocks Bridge, ID 08038
_ c: Identifying nos.
: 4. System         Main       Steam                                                                                                                                                                         Nuclear Class I I 5.a: Componentrepa~ed,modifredorre~~ed _l_C_-_~                                        ___2_5_3_~_&_B~,_l_C_-_~_~_2_5_3_3_A_&_B_~~-~~~---------------
____ _ N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)
b: Name of manufacturer ___PS_E_&G                     _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Qurisdictional no.) (other) d: Construction Code See Attachment N/A N/A (edition) 1983 (addenda) (Code Case(s)) 6. Section XI SUrmner 83 (edition) (addenda)
c: Identifying nos. _N~/A        _ _ _ __                                      N/A                                                       N/A                                             N/A                           1993 (mfr's. serial no.)                           (Nat'l.Bd.No.)                             Qurisdictional no.)                                         (other)                                    (year built) d: Construction Code             See Attachment                                                       N/A                                                                   N/A                                         II (edition)                                         (addenda)                                                             (Code Case(s))                                 (Code Class)
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: 1983 (edition)
: 6. Section XI                                 1983                                                                  SUrmner               83                                                                                     NIA (edition)                                                                                   (addenda)                                                                        (Code Case(s))
*1969 *ANSI B31. 7 /PS Spec S-C-MB'.JO-Mffi-043 1 1985 (edition) 1993 (year built) II (Code Class) NIA (Code Case(s)) S83 .....:N=-:../,_,,A=---(addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                                                                    1983            S83              .....:N=-:../,_,,A=---
__ PS_E_&G ______________________________________
(edition)        (addenda)          (Code Case(s))
_ 10. Tests conducted:
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                                                                   *1969               1970                N/A
hydrostatic D pneumatic D design pressure O *"'Pressure N/A psi Code Case(s) __
                                                      *ANSI B31. 7 /PS Spec S-C-MB'.JO-Mffi-043 1 1985 (edition)                                                                                                 (addenda)           (Code Case(s))
_____ _ 11. Description of work Installed for condensate pots on #12 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 9. Design responsibilities __       PS_E_&G   _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
: 12. Remarks: __
: 10. Tests conducted: hydrostatic D                         pneumatic                 D design pressure O *"'Pressure                                                     N/A psi                 Code Case(s) _ _N~/_A        _ _ _ _ __
Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
: 11. Description of work               Installed suppo~ for condensate pots on #12 main steam header.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19 94 ----Date j-3 PSE&G Co.-Nuclear Dept. t1 pt ;;; .
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
Signed ___________
: 12. Remarks: _ _      W_o_r_k_O_rd_er_~#~=-9~3~0~8=1~0~09~7~--------=De~f=i=c=ien=cy=.<-~R=e"""'po=rt~~#~:~N,_,,/~A~------
Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on //-I/ , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or*connected with this inspection.  
Design Change Package #: lEC-3256 Pkq. 1 See attached                         pages               for Description of Replacement.
/ Factory Mutual Engr. Assn. Date /-,l LJ , 19 'f V . Signed. {. Commissions It/ /J5t1t/ZJVA fiA1)J J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH __ 43229. NB-81 Rev.6
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
' FORM NR-1 ATTACHMENT Page _A_ of _A_ Code Job Package No.! PS93080 Work performed by: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 2. Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 3. Location:
Certificate of Authorization no.                             36             to use the "NR" stamp expires                                   Oct. 3, , 19-94                         ---
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Main Steam Nuclear Class: II ==============================================================================
PSE&G Co.-Nuclear Dept.                                                                       t1 pt ;;;                 .                  Principal                Engr.
ID of Component Replaced:
Date    j-3            19,~. Signed _ _ _ _ _ _ _ _ _ _ _ .?~L;,.4...,
(repair organization)                                                         (authorized representative)                                   (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of             New Jersey and employed by                                                                   Arkwri ht Mutual Insurance Co of         MA         have inspected the repair, modification or replacement described in this report on                                                                                   //-I/ , 19                   and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or*connected with this inspection.
                                                                                                /                                                                                     Factory Mutual Engr. Assn.
Date     /-   ,l LJ , 19 'f   V.         Signed.                                 {.       U~                                                      Commissions It/               /J5t1t/ZJVA fiA1)J                       J (Inspector)                                                               (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH _ 43229.
NB-81 Rev.6
 
        ' ~
Page _A_ of _A_
FORM NR-1 ATTACHMENT Code Job Package No.! PS93080 Work performed by:   Public Service Electric & Gas co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 2. Owner:               Public Service Electric & Gas Co.
Foot of Buttonwood Road, Han cocks Bridge, NJ 08038
: 3. Location:           Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. System: Main Steam                               Nuclear Class: II
==============================================================================
ID of Component Replaced: __;;..N~A=-------------------------
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code stamp'd.?
Serial No. Nat'l. Bd. Jurist No. Other   Year Built         ASME Code stamp'd.?
Edition Addenda, Code Class Code Cases: ---ID of Replacement:
Original Const. Code:                      Edition           Addenda, Code Class Code Cases: - - -
lC-MSG-2534 A&B Supports Name of Manufacturer:
ID of Replacement: lC-MSG-2534 A&B Supports Name of Manufacturer: _,:.P~S=E=&=G=--------------------------
N/A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code stamp 'd. ?* Addenda, Code Class II ==============================================================================
N/A         N/A         N/A         N/A     =1=9=9=3~---,.-  No Serial No. Nat'l. Bd. Jurist No.       Other   Year Built         ASME Code stamp 'd. ?*
of Component Replaced:
Replacement Const. Code: ANSI B31.7 1969     Edition 1970 Addenda, Code Class II Code Cases:N/A             PS Spec S-C-MBOO-MDS-043 1985
==============================================================================
of Component Replaced: __;;..N..._.,.A=--------------------------
of Manufacturer:
of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No. Other   Year Built         ASME Code Stamp'd.?
Edition Addenda, Code Class Code Cases: ---ID of Replacement:
Original Const. Code:                      Edition           Addenda, Code Class Code Cases: - - -
lC-MSG-2535 A&B Supports Name of Manufacturer:
ID of Replacement: lC-MSG-2535 A&B Supports Name of Manufacturer: --=P~S=E~&=G=--------------------------
N/A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code Stamp'd.?
N/A         N/A         N/A         N/A     =1=9=9~3~_,... No Serial No. Nat'l. Bd. Jurist No.       Other   Year Built         ASME Code Stamp'd.?
Addenda, Code Class II ==============================================================================
Replacement Const. Code: ANSI B31.7 1969     Edition 1970 Addenda, Code Class II Code Cases:N/A             PS Spec S-C-MBOO-MDS-043 1985
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of* Replacement:
Serial No. Nat'l. Bd. Jurist No. Other  Year Built        ASME Code Stamp'd.?
Name of Manufacturer:  
Original Const. Code:                     Edition            Addenda, Code Class Code Cases: - - -
'al No. Nat'l. Bd. Jurist No. acement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?
ID of* Replacement:
Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?
Name of Manufacturer:
Addenda, Code Class FORM NR-1 REPORT OF REPAIR D OR INSTALLATION OF REPLACEMENT(S)
    'al No. Nat'l. Bd. Jurist No.       Other   Year Built         ASME Code Stamp'd.?
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by Public Sel::vice Electric & Gas Co. -Nuclear Dept. CJP #PS93-081 (name) (repair organization's P .0. no., job. no.,etc.)
acement Const. Code:                    Edition           Addenda, Code Class Code Cases: - - -
Foot of Buttonwood Road, Hanccx::ks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hanccx::ks Bridge, NJ 08038 (address)
=========================================================================~====
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Steam Nuclear Class II 5. a: Component repaired, modified or replaced 1C-MSG-2562A&B, 1C-MSG-2563A&B supports b: Name of manufacturer
 
_
FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by     Public Sel::vice Electric & Gas Co. - Nuclear Dept.                                                                                   CJP #PS93-081 (name)                                     (repair organization's P.0. no., job. no.,etc.)
c: Identifying nos. N/A N/A N/A N/A __ 1=9=9=:;,,,;3=-------(mfr's. serial no.) (Nat'l.Bd.No.)
Foot of Buttonwood Road, Hanccx::ks Bridge, NJ                                                           08038 (address)
Ourisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda)
(name)
SUrnmer 83 (edition) (addenda) (other) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
Foot of Buttonwood Road, Hanccx::ks Bridge, NJ                                                           08038 (address)
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/PS Spec S-C-MBJO-MD3-043, 1985 *1969 (edition) (year built) II (Code Class) N/A (Code Case(s)) S83 N_,,/_A __ _ (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities
: 3. Name, address and identification of nuclear power plant                             Salem Nuclear Generating Station                                                   Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
_PS=-=.::E:..:&G-=------------------------------------,----------
: 4. System       Main Steam                                                                                                                                               Nuclear Class II
: 10. Tests conducted:
: 5. a: Component repaired, modified or replaced 1C-MSG-2562A&B, 1C-MSG-2563A&B supports b: Name of manufacturer _ _ _ , , P S E & G ' - = = : = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
hydrostatic D pneumatic D design pressure D ** pressure N/A psi Code Case(s)_--'N'""/'-'A=-=-------
c: Identifying nos. N/A                                         N/A                                           N/A                                   N/A                         __1=9=9=:;,,,;3=-------
escription of work Installed supports for condensate pots on #13 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
(mfr's. serial no.)                 (Nat'l.Bd.No.)                     Ourisdictional no.)                            (other)                                      (year built) d: Construction Code       See Attachment                                       N/A                                                     N/A                                          II (edition)                               (addenda)                                            (Code Case(s))                                  (Code Class)
: 12. Remarks:
: 6. Section XI                        1983                                                    SUrnmer 83                                                                                       N/A (edition)                                                                 (addenda)                                                                 (Code Case(s))
______ _ Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                               1983               S83              N_,,/_A_ __
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires act. 3, , 1994 ----.... Principal Engr. Date /-)' PSE&G Co.-Nuclear Dept. 19,--2:,L.
(edition)            (addenda)      (Code Case(s))
Signed ______ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on -/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. . _ Factory Mutual Engr. Assn. Date /-2-i.J , 1rfl!:/..-.
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                               *1969                    1970              N/A
Signed CommissionsltJ/JSff'/fJUA AlfTJJ (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Page J_ of J_ FORM NR-1 ATTACHMENT Code Job Package No.: PS93081 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 3. Location:
                                              *ANSI B31.7/PS                       Spec       S-C-MBJO-MD3-043, 1985                                     (edition)               (addenda)       (Code Case(s))
Salem Nuclear Generating Station Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 4. System: Main Steam Nuclear Class: II ==============================================================================
: 9. Design responsibilities _PS=-=.::E:..:&G-=------------------------------------,----------
ID of Component Replaced:
: 10. Tests conducted: hydrostatic D                   pneumatic D                 design pressure D             **   pressure         N/A psi               Code Case(s)_--'N'""/'-'A=-=-------
escription of work       Installed supports for condensate pots on #13 main steam header.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: _...!:Wc:::o::r_,,_..k,__O=rd=er=-_.#'-':'---"9'"""3,_,,0'""'8""1""0""'0""--99""------------"'De=f""i=c""ien""'-"'cy=-__.,R=e:;i:;po=rt'-"'--..ll.#_._:~N._,,/.....,A.....___ _ _ _ _ __
Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                   36             to use the "NR" stamp expires act. 3,                                   , 1994 PSE&G Co.-Nuclear Dept.                                                                                                 Principal Engr.
Date /- )'             19,--2:,L. Signed_ _ _ _ _ _~--------- ....
(repair organization)                                         (authorized representative)                               (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of         New Jersey                     and employed by                           Arkwri ht Mutual Insurance Co of       MA             have inspected the repair, modification or replacement described in this report on                                               - /                               and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
                                  .                                       _                                                                         Factory Mutual Engr. Assn.
Date     /-2-i.J       , 1rfl!:/..-. Signed     ~t[.,_, ~                                                                CommissionsltJ/JSff'/fJUA                                 AlfTJJ (Inspector)                                               (Natl.Bd.No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB-81 Rev.6
 
Page J _ of J _
FORM NR-1 ATTACHMENT Code Job Package No.: PS93081 Work performed by:   Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner:               Public Service Electric & Gas Co.
Foot of Buttonwood Road, Han cocks Bridge, NJ 08038
: 3. Location:             Salem Nuclear Generating Station Foot of Buttonwood Road, Han cocks Bridge, NJ 08038
: 4. System: Main Steam                               Nuclear Class: I I
==============================================================================
ID of Component Replaced:   -""'N_,__,_A=--~~~~~~~~~~~~~~~~~~~~~~~
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No. Other   Year Built       ASME Code Stamp'd.?
Edition Addenda, Code Class Code Cases: ---ID of Replacement:
Original Const. Code:                      Edition           Addenda, Code Class Code Cases: - - -
lC-MSG-2562 A&B Supports Name of Manufacturer:
ID of Replacement:   lC-MSG-2562 A&B Supports Name of Manufacturer: PSE&G
PSE&G N /A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code Stamp'd.?
__,=~~=-~~~~~~~~~~~~~~~~~~~~~~~~-
Addenda, Code Class II ==============================================================================
N/A         N/A         N/A         N/A     =1=9=9=3~-      No Serial No. Nat'l. Bd. Jurist No.       Other   Year Built       ASME Code Stamp'd.?
ID of Component Replaced: of Manufacturer: Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.?
Replacement Const. Code: ANSI B31.7 1969     Edition 1970 Addenda, Code Class II Code Cases:N/A             PS Spec S-C-MBOO-MDS-043 1985
Edition Addenda, Code Class Code Cases: ---ID of Replacement:
==============================================================================
lC-MSG-2563 A&B Supports Name of Manufacturer:
ID of Component Replaced:   _.:.;N"'-"A=--~~~~~~~~~~~~~~~~~~~~~~~~
PSE&G N /A N/A N/A N/A__
~ of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No AS ME Code Stamp'd.?
~            Nat'l. Bd. Jurist No. Other   Year Built       ASME Code Stamp'd.?
Addenda, Code Class II ==============================================================================
Original Const. Code:                      Edition           Addenda, Code Class Code Cases: - - -
ID of Replacement: lC-MSG-2563 A&B Supports Name of Manufacturer: PSE&G
                        .~~~-~~~~~~~~~~~~~~~~~~~~~~~~~-
N/A         N/A         N/A         N/A__ =1=-99""""3=--___,- No*~~~~~~~~~~-
Serial No. Nat'l. Bd. Jurist No.       Other   Year Built       AS ME Code Stamp'd.?
Replacement Const. Code: ANSI B31.7 1969     Edition 1970 Addenda, Code Class II Code Cases:N/A             PS Spec S-C-MBOO-MDS-043 1985
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:
Serial No. Nat'l. Bd. Jurist No. Other  Year Built        ASME Code Stamp'd.?
Original Const. Code:                     Edition          Addenda, Code Class Code Cases: - - -
ID of Replacement:
Name of Manufacturer:
Name of Manufacturer:
1 No. Nat'l. Bd. Jurist No. cement Const. Code: Other Year Built ASME Code Stamp'd.?
1 No. Nat'l. Bd. Jurist No.       Other   Year Built       ASME Code Stamp'd.?
Edition Addenda, Code Class Other Year Built ASME Code Stamp'd.?
cement Const. Code:  ~~~~~~~~~-
Edition Addenda, Code Class _ Cases: ---==============================================================================
Edition           Addenda, Code Class _
*-t ; b :::: FORM NR-1 REPORT OF REPAIR D OR INSTALLATION OF REPLACEMENT(S)
Cases: - - -
D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by Public Service Electric & Gas Co. -Nuclear Dept. CJP #PS93-082 (name) (repair organization's P.O. no., job. no.,etc.)
==============================================================================
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)
 
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Stearn Nuclear Class II 5. a: Component repaired, modified or replaced 1C-MSG-2564A&B, 1C-MSG-2565A&B SUpports b: Name of manufacturer
                                                                                            *- t                                                                                 ; b ~ ::::
_ __.PS--=E=&G""'----------------------------------------
FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2
c: Identifying nos. N/A N/A N/A N/A
rk performed by     Public Service Electric &                               Gas Co. - Nuclear Dept.                                   CJP #PS93-082 (name)                               (repair organization's P.O. no., job. no.,etc.)
___ _ (mfr's. serial no.) (Nat'l.Bd.No.)
Foot of Buttonwood Road,                       Hancocks Bridge, NJ                           08038 (address)
Uurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda)
(name)
SUrnrner 83 (edition) (addenda) (other) N/A (Code Case(s)) (year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
Foot of Buttonwood Road,                       Hancocks Bridge, NJ                           08038 (address)
S83 =NL-'/A=-=-----
: 3. Name, address and identification of nuclear power plant                     Salem Nuclear Generating Station                                       Unit #1 Foot of Buttonwood Road,                       Hancocks Bridge, NJ                           08038
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/PS Spec S-C-MB'.X>-MI:S-043, 1985 *1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities  
: 4. System       Main Stearn                                                                                                                           Nuclear Class I I
-=PS==E=-=&G=-=-----------------------------------------
: 5. a: Component repaired, modified or replaced 1C-MSG-2564A&B, 1C-MSG-2565A&B                                             SUpports b: Name of manufacturer _ _ _ . P S - - = E = & G " " ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
: 10. Tests conducted:
c: Identifying nos. N/A                             N/A                                       N/A                               N/A                   -~1=9~9~3_ _ __
hydrostatic D pneumatic D design pressure O **pressure N/A psi Code Case(s)_--'N=--"-/-=-A=--------
(mfr's. serial no.)         (Nat'l.Bd.No.)                 Uurisdictional no.)                      (other)                                  (year built) d: Construction Code       See Attachment                               N/A                                             N/A                                    II (edition)                       (addenda)                                     (Code Case(s))                           (Code Class)
escription of work Installed supports for condensate pots on #14 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 6. Section XI                          1983                                          SUrnrner      83                                                                    N/A (edition)                                                    (addenda)                                                      (Code Case(s))
: 12. Remarks:
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                             1983           S83               =NL-'/A=-=-----
c""1""''
(edition)      (addenda)          (Code Case(s))
______ _ Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                             *1969              1970                N/A
**No Presei:vice Reauired Temn. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ _ Date I -;J PSE&G Co.-Nuclear Dept. 19,__f_l._.
                                            *ANSI B31.7/PS Spec S-C-MB'.X>-MI:S-043, 1985                                                 (edition)           (addenda)         (Code Case(s))
Signed ______________
: 9. Design responsibilities - = P S = = E = - = & G = - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on , 19'J} and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. . / / " Factory Mutual Engr. Assn. Date I -2 if ' 19q '-/ . Signed rt.4./ '2--Commissions N8 sr ft-/ f&deg;N ;4 rv:JJ?.J (Inspector) (Natl.Bd .No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1 ATTACHMENT Page __L of __L Code Job Package No.: PS93082 performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 2. Owner: Public Service Electric & Gas co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 3. Location:
: 10. Tests conducted: hydrostatic D               pneumatic     D design pressure O**pressure N/A psi                                     Code Case(s)_--'N=--"-/-=-A=--------
Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Main Steam Nuclear Class: II ==============================================================================
escription of work       Installed supports for condensate pots on #14 main steam header.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
: 12. Remarks: -~Wi~o=r=k~O=rd=e=r~#~:~9=3=0=8=1=6=1=00~--------~De=f=1=*c""1""''en,,,,._..,cy~_,,R,_,,,e""'po~rt....=.._,_#'"""':~N&#xa5;-/~A.___ _ _ _ _ __
Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement.
                        **No Presei:vice Reauired                                                  Temn.      N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                  36      to use the "NR" stamp expires              Oct. 3,             , 19_9_4_ __
PSE&G Co.-Nuclear Dept.                                                                              Principal              Engr.
Date    I - ;J        19,__f_l._. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ __
(repair organization)                                (authorized representative)                          (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of        New Jersey              and employed by                      Arkwriaht Mutual Insurance Co of        MA            have inspected the repair, modification or replacement described in this report on                          //~/I           , 19'J}        and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
* n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date      I - 2 if ' 19q'-/
                                      . Signed    rt.4./        /
                                                                  '2--    ~
                                                                            /
(Inspector)
Commissions N8 Factory Mutual Engr. Assn.
sr    ft-/ f&deg;N;4        rv:JJ?.J (Natl.Bd .No.(including endorsements)state or province and number)
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB*81 Rev.6
 
Page __L of __L FORM NR-1 ATTACHMENT Code Job Package No.: PS93082 performed by:  Public Service Electric & Gas Co., Nuclear Dept.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 2. Owner:              Public Service Electric & Gas co.
Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 3. Location:            Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
: 4. System: Main Steam                                Nuclear Class: II
==============================================================================
ID of Component Replaced: __N""-""A=-----------------,-----------
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Other  Year Built        ASME Code Stamp'd.?
Original Const. Code:                      Edition            Addenda, Code Class Code Cases:
----------------------------------------------------------------------------~-
ID of Replacement: lC-MSG-2564 A&B Supports Name of Manufacturer: PSE&G
                        ~~~----------------------------
N/A          N/A          N/A          N/A      ~1~9~9~3~--,..--  No Serial No. Nat'l. Bd. Jurist No.        Other  Year Built        ASME Code Stamp'd.?
Replacement Const. Code: ANSI B31.7 1969      Edition 1970 Addenda, Code Class II Code Cases:N/A            PS Spec S-C-MBOO-MDS-043 1985
==============================================================================
rial No. Nat'l. Bd. Jurist No. Other  Year Built        ASME Code Stamp'd.?
Original Const~ Code:                      Edition            Addenda, Code Class Code Cases: - - -
ID of Replacement: lC-MSG-2565 A&B Supports Name of Manufacturer: PSE&G
                        --""'~~=---------------------...;...._              ____
N/A          N/A          N/A          N/A      =1=9=9=3~-~      No
                                                                    *---~-----~-
Serial No. Nat'l. Bd. Jurist No.        Other  Year Built        AS ME Code Stamp'd.?
Replacement Const. Code: ANSI B31.7 1969      Edition 1970 Addenda, Code Class II Code Cases:N/A            PS Spec S-C-MBOO-MDS-043 1985
==============================================================================
ID of Component Replaced:
ID of Component Replaced:
__
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.?
Serial No. Nat'l. Bd. Jurist No. Other   Year Built         ASME Code Stamp'd.?
Edition Addenda, Code Class Code Cases: ---
Original Const. Code!                      Edition           Addenda, Code Class Code Cases: - - -
ID of Replacement:
ID of Replacement:
lC-MSG-2564 A&B Supports Name of Manufacturer:
PSE&G N /A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code Stamp'd.?
Addenda, Code Class II ==============================================================================
rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?
Original Code: Edition Addenda, Code Class Code Cases: ---ID of Replacement:
lC-MSG-2565 A&B Supports Name of Manufacturer:
PSE&G
___ _ N/A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No AS ME Code Stamp'd.?
Addenda, Code Class II ==============================================================================
ID of Component Replaced:
Name of Manufacturer:
Name of Manufacturer:
Serial No. Nat'l. Bd. Jurist No. Original Const. Code! Code Cases: ---ID of Replacement:
Nat'l. Bd. Jurist No.     Other   Year Built         ASME Code Stamp'd.?
Name of Manufacturer:
Const. Code:                    Edition           Addenda, Code Class _
Nat'l. Bd. Jurist No. Const. Code: Other Year Built ASME Code Stamp'd.?
==============================================================================
Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?
 
Addenda, Code Class _ ==============================================================================  
FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS                                                                                           f Pa e 1 o 1 ark performed by           Public Service Electric                               &   Gas Co. -           Nuclear         Dept.               CJP     #PS93-083 Rev.O (name)                             (repair organization's P.O. no .. job. no.,etc.)
---
Foot of             Buttonwocd                   Road. Hancocks           Bridge, NJ               08038 (address)
..............
: 2. Owner             Public Service Electric                           an:l Gas Co.
----
              --=-======--===-=-==-==----=====:..====--==-==--===--=~=------------------------------
FORM NR-1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS f Pa e 1 o 1 ark performed by Public Service Electric & Gas Co. -Nuclear Dept. CJP #PS93-083 Rev.O (name) (repair organization's P.O. no .. job. no.,etc.)
(name)
Foot of Buttonwocd Road. Hancocks Bridge, NJ 08038 (address)
Foot of             Buttonwocd                  Road,    Hancocks            Bridge, NJ              08038 (address)
: 2. Owner Public Service Electric an:l Gas Co. (name) Foot of Buttonwocd Road, Hancocks Bridge, NJ 08038 (address)
: 3. Name, address and identification of nuclear power plant                              Salem Nuclear Generating Station                                    Unit #1 Foot of            Buttonwocd Road, Hancocks                                Bridge, NJ 08038
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocd Road, Hancocks Bridge, NJ 08038 4. System Pressurizer Relief Tank Line SUpport Nuclear Class II b: Name of manufacturer In..c:;t.al 1 ed by J?SE&G c: Identifying nos. N/A N/A N/A Iruat,al led 1975 (mfr's. serial no.) (Nat'l.Bd.No.)
: 4. System              Pressurizer Relief Tank Line                                  SUpport                                                                Nuclear Class                  II 5.~ Componentrepa~ed,modffiedorre~aced~P~i~~~~~~~~~rt~~#~C~--~~~--5~----------------------~
Ourisdictional no.) (other) (year built) d: Construction Code Specification 69-6445-1974 None 6. Section XI (edition) 1983 (addenda)
b: Name of manufacturer                      In..c:;t.al 1 ed by J?SE&G c: Identifying nos.        N/A                                   N/A                                      ~/A                            N/A                Iruat,al      led 1975 (mfr's. serial no.)                 (Nat'l.Bd.No.)               Ourisdictional no.)                    (other)                                  (year built) d: Construction Code            Specification                    69-6445-1974                                                      None (edition)                        (addenda)                                   (Code Case(s))                           (Code Class)
SUnuner 83 (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (Code Class) N/A (Code Case(s)) S83 (edition) (addenda) (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *Spec 696445 1974 *See BelOW'._,_,_
: 6. Section XI                                  1983                                            SUnuner        83                                                                    N/A (edition)                                                         (addenda)                                                   (Code Case(s))
___ None (edition) (addenda) (Code Case(s)) 9. Design responsibilities
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                      1983            S83                N'--+/~A~--
________________________________________
(edition)      (addenda)          (Code Case(s))
_ 10. Tests conducted:
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                   *See BelOW'._,_,__ _ _None
hydrostatic D pneumatic D design pressure D** pressure N/A psi Code escription of work M.o:lify pipe support C-RWS-5 (use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks:
                                                                                    *Spec 696445 1974                                            (edition)          (addenda)          (Code Case(s))
_________
: 9. Design responsibilities        ~PS"-""E,,,.,,,&G,=._ _________________________________________
_______ _ Design Change Package #: lEC-3054-2 Rev. O See attached pages for Description of Replacement.
: 10. Tests conducted: hydrostatic                  D        pneumatic      D      design pressure        D** pressure          N/A       psi      Code Case(s)_~N~o=n=e~------
N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , H9-:;...4-=----
escription of work            M.o:lify            pipe support C-RWS-5 (use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: _JW~o~rLk..,__~Ordi.w...~e~r~#~*~9L3..l...Ll~O~Ou7~1~4L7L__ _ _ _ _ _ _ _ __._ne=...f~i~c~iue~ncycn....&#xa5;-~R~e+po.11..1.1rt:_,__~#1t-o-:-N"""'a~n~e:.___ _ _ _ _ _ __
: c. PSE&G Co. -Nuclear Dept. / / / :. Date ]' -;+.&#xa3; 19, ?"'&#xa5;. Signed. _________________ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be ,n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.  
Design Change Package #: lEC-3054-2 Rev. O See  attached pages for Description of Replacement.                                                          N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
') ,..,.... Date J ,. 2) , 1rflL_. Signed * '7 ..,,,L--Commissions;\J,55%-i'f
Certificate of Authorization no.                            36      to use the "NR" stamp expires              Oct. 3,         , H9-:;...4-=----
&#xa3;v ;l ,if) 5 73 / (,_ Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including or province and This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
: c.                             PSE&G Co. -Nuclear Dept.                                       /    / /      :.                 Principal              Engr.
FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l r
            -;+.&#xa3; Date ]'                      19, ?"'&#xa5;. Signed. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
*ork performed by Public service Electric & Gas Co. -Nuclear Dept. (name)
(repair organization) 2 ~~    (authorized representative)                          (title)
* Foot of Buttonwood Road, Hancocks Bridge, NT 08038 CJP #PS93-088 Rev.a (repair organization's P.O. no., job. no.,etc.) (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NT 08038 (address)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of              New Jersey                    and employed by                    Arkwri          t Mutual Insurance Co of      MA                  have inspected the repair, modification or replacement described in this report on                                                      J      and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
: 3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NT 08038 4. System Control Air Nuclear Class II b: Name of manufacturer
        ,n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
_____________________________________
                ,..,....                                    ~                /      (,_                                                  Factory Mutual Engr. Assn.
_ c: Identifying nos. N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)
                                                                ~ '7 ..,,,L--
Uurisdictional no.) d: Construction Code 69-6445/SG-SMFD-1 WA 6. Section XI (edition) 1983 (addenda)
        ')
SUrnmer 83 (edition) (addenda) (other) None (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)
Date J ,. 2)             , 1rflL_. Signed
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *NIA *S-C--MB:X>-MCS-043 (edition) 1974 (year built) II (Code Class) :t{/A (Code Case(s)) S83 (addenda)
* Commissions;\J,55%-i'f            &#xa3;v ;l ,if) 573
N/A (addenda) (Code Case(s)) None (Code Case(s)) 9. Design responsibilities
                                                              ~                (Inspector)                                       (Natl.Bd.No.(including  endorsements)s~te or province and n~rnber:
: 10. Tests conducted:
This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
hydrostatic D pneumatic D design pressure D **pressure N/A psi Code Case(s) __
 
: 11. Description of work Replace 2 nuts on pipe support #P-CrAG-660.
FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) ~
* (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l r  ~;======================================================================================.::=_==============
__
ork performed by      Public service Electric & Gas Co. -                                                Nuclear          Dept.                CJP    #PS93-088          Rev.a (name)                                (repair organization's P.O. no., job. no.,etc.)
_________
* Foot of      Buttonwood                Road,        Hancocks Bridge, NT                            08038 (address)
Design Change Package #: lEC-3150-1 Rev. O See attached pages for Description of Replacement.
(name)
N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19-=-9-=4=-----
Foot of       Buttonwood                Road,        Hancocks              Bridge,        NT      08038 (address)
Date '2 -19,-2&#xa3;_. Signed. __ PS_E_&G __ eo_._-Nu_c_l_ear
: 3. Name, address and identification of nuclear power plant                            Salem Nuclear Generating Station                                        Unit      #1 Foot of Buttonwood Road, Hancocks Bridge, NT 08038
__ De_p_t_. __ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual ce Co of MA have inspected the repair, modification or repla.cement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1 any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
: 4. System        Control Air                                                                                                                                  Nuclear Class I I 5.~ Componentrepa~ed,modffiedorre~aced~P~i~pe~~~~~~rt~~~~~~~6~6~0~---------------------~
Date J -2 ) , 1 sh_. Signed "l,. l-c_J.__-
b: Name of manufacturer      -~.,_,,,,,.,E.,&G.,,,.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
'/ J._,4/ A 11153 7 l . c,, 1 9 c.* / .. Fc:cto:ry Mutual Assn. 1 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rev.6}}
c: Identifying nos. N/A                                      N/A                                        N/A                                                          1974 (mfr's. serial no.)                (Nat'l.Bd.No.)                  Uurisdictional no.)                      (other)                                  (year built) d: Construction Code       69-6445/SG-SMFD-1                                    WA                                            None                                    II (edition)                                (addenda)                                      (Code Case(s))                          (Code Class)
: 6. Section XI                        1983                                                  SUrnmer      83                                                                      :t{/A (edition)                                                            (addenda)                                                      (Code Case(s))
: 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made:                                      1983            S83                =N~/=A'----
(edition)        (addenda)        (Code Case(s))
: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:                                    *NIA                N/A                None
                                                                                      *S-C--MB:X>-MCS-043                                          (edition)          (addenda)          (Code Case(s))
: 9. Design responsibilities ----"PS~E=&G"'-'-""-----------------------------------------
: 10. Tests conducted: hydrostatic D                  pneumatic D                  design pressure D **pressure                    N/A psi            Code Case(s) __N~o~n~e~------
: 11. Description of work        Replace 2 nuts on pipe support #P-CrAG-660.
(use of additional sheet(s) or sketch( es) is acceptable if properly identified)
            ~~~~~~~~~
12.Remarks: __Wuo~r~ka.__,.,Ord"'""'~e~r-----i#~:'---'9~3~0~6~1*5..u.1~3~5_ _ _ _ _ _ _ _ ____JDeL.&:O.f~jcl.i..Ljecnu~cy~~R~e~poa..urt._.__~#~:._,N~ounu.ce~-------
Design Change Package #: lEC-3150-1 Rev. O See attached pages for Description of Replacement.                                                                  N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.
Certificate of Authorization no.                    36          to use the "NR" stamp expires                Oct.      3,        , 19-=-9-=4=-----
Date '2 -    ~~      19,-2&#xa3;_. Signed._ _PS_E_&G                  __  eo_._-Nu_c_l_ear    _ _De_p_t_.__
Principal              Engr.
(repair organization)                                  (authorized representative)                          (title)
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of        New Jersey                    and employed by                        Arkwri t Mutual                                      ce Co of        MA          have inspected the repair, modification or repla.cement described in this report on                                                                  and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, 9
sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1 any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
          .                  c,, 1                                          c.* /                    .                                      Fc:cto:ry        Mutual ~.                  Assn.
Date    J -2 ) ,1sh_.                Signed        ~'?My"                "l,. l-c_J.__-                        Commissions/J~Jtz '/              J._,4/A 11153 7l (Inspector)                                         (Natl.Bd.No.(including endorsements)state or province and number) 1 This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.
NB*B1 Rev.6}}

Latest revision as of 10:19, 23 February 2020

ISI Activities - 90 Day Rept Eleventh Refueling Outage Salem Generating Station Unit 1
ML18100B034
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/31/1994
From: Lake L
Public Service Enterprise Group
To:
Shared Package
ML18100B033 List:
References
NUDOCS 9404260399
Download: ML18100B034 (180)
v • d • e


Text

FORM NIS-1 OWNER 1 S DATA REPORT . . FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. Owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77..
6. National Board Number for Unit: N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
8. This report covers the examinations that were conducted during the 11th Refueling Outage.
9. Components Inspected.

MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO. NUMBER BOARD NO.

  1. 1 Reactor Combustion 66201 Head Vessel Engineering 66101 Vessel N/A 20757
  1. 11 Steam Westinghouse 1003 N/A 68-10 Generator Tampa Div.

P.O. Box 19218 Tampa, FL 33616

  1. 12 Steam Generator II II 1022 N/A 68-08
  1. 13 Steam Generator II II 1023 N/A 68-09
  1. 14 Steam Generator II II 1203 N/A 68-51
  1. 1 Regen. Sentry Equip. 4195-A4 N/A 385, 386, Ht. Exch. Corp. 7, 8, 9 387 Oconomowoc, WI
  1. 1 Rx. Commercial 101238 N/A 1193 Coolant Filters, Corp.

Filter Lebanon, IN

--- - -9404260399' 940420~ -- ---,

PDR ADOCK.05000272 G . PDR

, Page 1 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

i. owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. Owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
9. Components Inspected (cont'd):

MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO. NUMBER BOARD NO.

  1. 1 Pressur- Delta Southern 1011 N/A 68-8 izer Chemical United Engineers Volume & & Constructors Control (UE&C) 30 South N/A N/A N/A Piping 17th st., Phila.

System PA 19101 Component UE&C N/A N/A N/A Cooling Sys.

Containment UE&C N/A N/A N/A Spray Piping System Mains team UE&C N/A N/A N/A Piping sys.

  1. 11 RHR Heat Engineers & Sl5860-C N/A 122 Exchanger Fabricators, Inc.

Page 2 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L Owner: Public Service Electric & Gas Co., 80 Park Plaza

  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
9. Components Inspected (cont'd):

MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO. NUMBER BOARD NO.

Pressurizer UE&C N/A N/A N/A Relief Piping Sys.

Pressurizer UE&C N/A N/A N/A Spray Sys.

Reactor UE&C N/A N/A N/A Coolant Piping Sys Residual UE&C N/A N/A N/A Heat Removal System Service Water UE&C N/A N/A N/A System Steam Gen. UE&C N/A N/A N/A Feed Piping System Safety UE&C N/A N/A N/A Injection Piping Sys.

Page 3 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

i. Owner: Public Service Electric & Gas Co., 80 Park Plaza
  • Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. Owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
10. Abstracts of Examinations:

1.0 This report also contains augmented examinations required by the Salem Technical Specification, Regulatory Guides, Circu-lars and Bulletins issued by the United States Nuclear Regulatory Commission.

Examinations were conducted by PSE&G as well as companies under contract to PSE&G. The following is a brief summary with further details found in the attached report and on file at the Salem Generating Station.

Since nearly all inservice examination requirements can be found in Salem's Technical Specifications, this summary lists these requirements first arranged by Technical Speci-fication paragraph number followed by applicable NRC Circu-lars and Bulletins .

Page 4 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES I

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza
  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant:

Plant Unit 1 07101 Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary 11.1 Technical Specification 4.0.5 - ASME XI (1983 Edition)

During the Fall 1993 refueling outage, PSE&G, MQS and SwRI personnel performed nondestructive examinations (NDE) of selected Class 1, Class 2 and Class 3 compo-nents at the Salem Unit 1 Generating Station. These examinations constituted the fourth inservice examina-tion (ISI) of the second inspection interval of com-mercial operation.

11.1.1 ISI Examination Southwest Research Institute (SwRI) under the direction of the Salem ISI Group conducted seventy-six (76) manual ultrasonic, one hun-dred and four (104) liquid penetrant, and fourteen (14) magnetic particle examinations.

Examinations were conducted on the following systems:

Class .l Vessels Pressurizer RPV Steam Generator #11 through #14 Piping Chemical and Volume Control Reactor Coolant System Pressurizer Relief System Pressurizer Spray System Residual Heat Removal System Safety Injection System Pumps Reactor Coolant Pumps #12 and #14 Page 5 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

i. Owner: Public Service Electric & Gas Co., 80 Park Plaza
  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required} N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (Cont'd}

Integrally Welded Attachments Reactor Coolant Pumps #12 and #14 Safety Injection Class .6.

Vessels Head Tank #11 Reactor Coolant Filter Regenerative Heat Exchanger Piping Main Steam System Steam Generator Feed System Containment Spray system Residual Heat Removal System Pressurizer Relief System Chemical Volume Control system Safety Injection System Integrally Welded Attachments Residual Heat Removal System Safety Injection System Main Steam System The following nonconformance was reported by SWRI:

A PT examination on weld 4-SJ-1172-5 (Summary No. 131200}, revealed six (6) linear record-able indications. CNF 1-1 was issued by SWRI and dispositioned by PSE&G as follows:

After cosmetically blending these indica-tions, a PT re-exam was performed with no linear indications identified.

There were no other*unacceptable indications identified .

Page 6 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

i. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

11.1.2 Visual Examination on Valves and Bolting The Salem ISI Group conducted twenty-nine (29)

Class 1 bolting exams and one (1) Class 1 valve internal exam.

There were several Class 1 Bolting exam anoma-lies noted, including boric acid accumulation, nuts seized on the stud or bolt, etc .. Work orders and/or deficiency reports were generat-ed to document and correct all anomalies.

NOTE: No additional exams were required.

Examinations were conducted on the following systems:

Valves Pressurizer Relief System Safety Injection System Residual Heat Removal System Chemical Volume and Control System Pressurizer Spray System There were no unacceptable indications identi-fied.

11.1.3 Visual Examination of Supports The Salem !SI Group conducted and/or coordi-nated visual examinations on seventeen (17)

Class I, five (5) Class II and one hundred forty eight (148) Class III supports .

Page 7 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77. *
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

Examinations were conducted on the following systems:

Auxiliary Feedwater Main Steam Chemical & Volume Control Pressurizer Relief Component Cooling Pressurizing Containment Spray Safety Injection Residual Heat Removal Service Water There were no unacceptable indications identi-fied.

11.1.4 System Pressure Tests System leakage exams were performed in accord-ance with ASME Section XI on all Class I systems.

A system leakage test was performed with the Reactor Coolant System in mode 3 (normal operating temperature and pressure) with the insulation installed. No pressure boundary leakage was detected. Minor mechanical leak-age was identified and work requests were initiated for repairs.

Thirty two (32) System Pressure Tests (SPT) were completed during a System Functional or Inservice Test on Nuclear Class 1, 2 and 3 components in accordance with ASME Section XI.

No pressure boundary leakage was detected.

Work requests were initiated to correct minor mechanical leakage that was identified .

Page 8 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

i. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. Owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

11.2* Preservice Examinations were performed on the #11 through #14 SJ17 valve replacement welds per DCP 1E0-2309.

The welds that were replaced to facilitate the valve replacement are listed below:

!SIC !SIC PSE&G

SUMMARY

  1. COMPONENT ID WELD #

174900 1~-SJ-1142-49R RH-3282-77F-A 175001 1~-SJ-1142-50R RH-3282-76F-A 175101 1~-SJ-1142-51R RH-3282-75F-A 175500 1~-SJ-1132-39R RH-3295-111F-A 179601 1~-SJ-1132-40R RH-3295-110F-A 179701 1~-SJ-1132-41R RH-3295-109F-A 184600 1~-SJ-1122-41R RH-3269-43F-A 184700 1~-SJ-1122-42R RH-3269-42F-A 184801 1~-SJ-1122-43R RH-3268-41F-A 190100 1~-SJ-1112-49R RH-3256-4F-A 190201 1~-SJ-1112-50R RH-3256-3F-A 190301 1~-SJ-1112-351 RH-3256-2F-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted.

Preservice Examination was performed on Safety Injec-tion System piping weids, due to the replacement of two (2) orifices per DCP lEC-3260.

The welds that were replaced to facilitate the re-placement of the orifices are listed below:

!SIC !SIC PSE&G

SUMMARY

  1. COMPONENT ID WELD #

386600 2-SJ-2126-6R SI-5-256B-A 386620 2-SJ-2126-7R SI-5-257B-A 387100 2-SJ-2123-6R SI-1-211C-B 387120 2-SJ-2123-7R SI-1-212C-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted.

Page 9 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

11.3 Technical Specification 4.4.6.0 - Steam Generator Tube Eddy Current Inspection.

11. 3. 1 Overview The original scope of Salem lRll outage was comprised of 20% bobbin and 20% top of hot leg tubesheet in all four Steam Generators. In addition, a twelve hour* window was allotted for RPC testing of dented hot leg tube support plate ~ntersections.
11. 3. 2 Top of Tubesheet RPC Inspection The tube expansion in the Steam Generators at Salem Unit 1 were made using the WEXTEX proc-ess (explosive expansions). History of Wextex units has shown some cracking in the expansion transition. Cracking of the WEXTEX region can be axial, circumferential or oblique in orien-tation as detected by RPC. The extent of circumferential cracking and the extent to which an axial indication extends into the transition zone are critical measurements.

Due to indications found, the initial scope was expanded by a total of 612 tubes in Steam Generator #11. One circumferential and seven axial indications were detected in this Steam Generator. None of these indications exceeded the structural integrity limits. Three of these indications were OD initiated. These indications are believed to have been caused by ODSCC rather than residual stress from the WEXTEX expansion process.

There were no expansions of Top of Tubesheet RPC inspections in #12 Steam Generator. 708 tubes were inspected which represents 20.9% of the Steam Generator .

Page 10 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1' . Owner: Public Service Electric & Gas Co., 80 Park Plaza

  • 2.

3.

4.

5.

Newark, N.J.

Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

Steam Generator #13 1 s scope was expanded to 100% due to an indication found in tube R14C39. This tube had a 0.448 11 axial indica-tion. The entire length of this indication was contained within the WEXTEX transition, therefore the structural integrity limit of 0.41" was exceeded, prompting the 100% expan-sion of this Steam Generator. This tube also contained two circumferential indications at the top of the tubesheet. Evaluation by Westinghouse determined that this tube re-quired stabilization. One additional tube in this Steam Generator was evaluated for stabi-lization and determined that no stabilization was required.

Steam Generator #14 had no expansions of the Top of Tubesheet RPC inspection. A total of 708 tubes were inspected which represents 20.9% of the Steam Generator.

11.3.3 Bobbin Inspection There were five different types of degradation detected during the bobbin inspection. Four of these mechanisms were previously identified to some degree in Unit 1. They are:

AVB WEAR All four Steam Generators have had some wear at the anti-vibration bars . . Steam Generator

  1. 11 had two tubes plugged because of this wear.

COLD LEG THINNING All four Steam Generators have had thinning at peripheral tube cold leg support plate intersections. Steam Generator #14 had one tube plugged because of this mechanism.

Page 11 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1' . owner: Public Service Electric & Gas Co., 80 Park Plaza

  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

OD INDICATIONS AT NON-DENTED SUPPORT PLATES These indications are usually distorted on bobbin and require further clarification by RPC testing. Typically, there is a deposit present, which adds to the distortion. This deposit is usually responsible for the corrosion occurring at these intersections.

When these indications confirm, the RPC testing reveals a oval-shaped, pit-like signal. Steam Generators #11 and #12 plugged one tube each for this mechanism.

Steam Generator #13 had four tubes plugged for this mechanism.

OD INDICATIONS AT THE TOP OF TUBESHEET These indications are similar to the support plate indications mentioned above, in that the signals are usually distorted by the presence of a deposit. Again, this deposit is most likely responsible for the corrosion occurring. As mentioned, three of these signals were deemed pluggable during the RPC inspection. In addition, several signals in both Steam Generators #11 and #13 were called INR (Indication not Recordable),

during the RPC inspection. INR was used since these signals did not fit any of the allowable RPC indications (SAI, MAI, SCI, MCI, SOI and MOI). These INR signals were also bobbin tested. In most cases, these signals were found to be less than a 20%

through wall dimension, however, two more tubes in Steam Generator #11 were plugged for this mechanism as well as two tubes in Steam Generator #13.

Page 12 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. owner: Public Service Electric & Gas Co., 80 Park Plaza
  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

One new degradation mechanism was identified during lRll. This was ID INITIATED INDICA-TIONS AT DENTED SUPPORT PLATE INTERSECTIONS.

These indications can be detected by bobbin when they extend greater than 0.2 11 beyond the edge of the support plate. These indications can be attributed to residual stress from the dent. The shape rather than the size of the dent appears to be more of a factor in causing these indications. The sizes of the dents associated with these indications are rela-tively small when*compared to the population of dents present in Unit 1 Steam Generators.

The first indication of this type was found in Steam Generator #12 tube R33C43 at lH (1st

  • support plate hot leg side) . RPC of this indication revealed that it was 1.59 11 long, extending from 0.91 11 above the support plate to 0.68 11 below. This indication prompted 100%

bobbin.testing in Steam Generator #12 from 7H to TEH (tube end hot). This expansion re-vealed two more indications tube R8C4 at lH and tube R28C85 at 2H. RPC of tube R8C4 showed an MAI (multiple axial indications).

One of the axials was 1. 102 11 in length start-ing* at 0.74 11 above the support plate. The other axial was 1. 050" in length starting at 0.66 11 above the support plate. RPC of tube R28C85 showed and SAI 0.432 11 long starting at 0.68" .above the support plate.

These indications in Steam Generator #12 prompted 100% bobbin testing in the other three Steam Generators from 7H to TEH. No more indications of this type were found in Steam Generators #11 and #14. However, two indications.were flagged in Steam Generator

  1. 13 for RPC testing. RPC of tube R30C42 at 3H revealed an SAI 1. 032 11 long starting at O. 26 11 above the support plate and ending at 1.292 11 below the support plate.

Page 13 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY TH~ PROVISIONS OF THE ASME CODE RULES 1' . owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1 *
4. owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

RPC of tube R3C59 at lH revealed an MAI. One of the axials was 1.742" long starting at 0.87" above the support plate. The other axial was o. 591'.' long, starting at o. 74" above the support plate. Both of these indications were determined to be OD indications rather than ID.

RPC OF DENTED SUPPORT PLATE INTERSECTIONS Twelve hours were allocated for sample testing of dented support plate intersec-tions in each Steam Generator. The 300 largest dents in each Steam Generator were selected for testing. The aim of this testing is to detect the presence of circum-ferential indications. Circumferential oriented indications can not be seen by bobbin probes. Due to time constraints and restrictions encountered within the tubes, none of the Steam Generators completed the 300 tube program. The number of intersec-tions inspected, ranged from 122 to 170. No indications were detected in this inspec-tion.

11.4 Current Status of the Steam Generators At this time the total number of tubes plugged in the Salem Unit 1 Steam Generators are as follows:

Generator # 11 12 13 14 Tubes previously plugged 104 121 112 143 New tubes plugged this outage 12 4 10 2 Tubes Plugged 116 125 122 145 Page 14 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

i. owner: Public Service Electric & Gas Co., 80 Park Plaza
  • Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. Owner's Certificate of Authorization (if required) N/A.
5. commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

NOTE: The first five and the last five tubes of Row 1 in each of the Steam Generators were mechan-ically plugged due to a vibration in the tube lane blocking device. The remaining Row 1 tubes were preventively plugged due to a wear problem on the tubes caused by a vibration in the tube lane blocking device. The remaining Row 1 tubes were preventively plugged due to the onset of stress corrosion cracking in the U-bend region as evidenced in two of the four Steam Generators.

11.5 Technical Specification 4.6.1.2d, Containment Type "B" (Penetrations) and Type "C" (Valves) Leak Rate Testing .

11.5.1 summary The PSE&G Research Corp. under the field supervision of the Salem ISI Group, conducted local leak rate tests on sixty three (63) Type "B" Electrical Penetrations, seven (7) Type "B" Mechanical Penetrations and fifty five (55)

Type "C" Mechanical Penetrations (113 valves).

11. 5. 2 Results A. Several Type "C" valves exceeded the recommended leak rate acceptable criteria.

These valves were worked to an acceptable condition and retested satisfactorily.

B. A total As-Found leakage (min path) of

. 15,338.5 SCCM was measured through all Type "B" and "C" containment penetrations.

After corrective maintenance, a total As-Left (max path) of 26,372.0 SCCM was meas-ured through all Type "B" and "C" penetra-tions.

Page 15 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1' . Owner: Public Service Electric & Gas Co., 80 Park Plaza

  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant:

Plant Unit 1 07101 Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

11.6 Technical Specification 4.6.1.3b Elevation 100 1 and 130' Airlock Leak Rate Tests 11.6.1 Summary PSE&G Research Corporation under the field supervision of the Salem ISI Group conducted leak rate tests on the 100' and 130' contain-ment personnel airlocks.

11.6.2 Results The combined As-Found leakage for these air-locks was 4,925.0 SCCM. After maintenance, the combined As-Left leakage for the airlocks was 5,860.0 SCCM. Both of these measured combined leakage rates satisfies the Technical Specif i-cation acceptance criteria of ~ 0.05 La (10,812 SCCM) .

11.7 Technical Specification 4.7.9. (a) "Visual Inspection of Hydraulic and Mechanical Snubbers"

11. 7. 1 Summary The Salem ISI Group conducted visual examina-tions on twenty four (24) hydraulic and one hundred and eleven {111) mechanical snubbers.

11.7.2 Results A. There were no discrepancies noted which would affect snubber operability. There were some minor items noted including missing washers, loose spherical bearings and binding around the bearings and some light corrosion. These conditions were all noted and corrected.

B. All snubbers which were removed and rein-stalled received a satisfactory "As-Left" visual examination.

Page 16 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED' BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza
  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination summary (cont'd):

11.8 Technical Specification 4.7.9 (c) "Functional Testing of Selected Hydraulic and Mechanical Snubbers" 11.8.1 summary - Hydraulic Snubbers A. Per Technical Specifications, 10% of the installed hydraulic snubbers as well as all previous outage functional test failures are required to be tested. The 10% sample included one 200 KIP Main Steam snubber and two 1000 KIP Steam Generator snubbers.

There were no previous outage test fail-ures.

B. The 10% sample of hydraulic snubber (small size) included one (1) Lisega 3018 .

There were no noted discrepancies in the Technical Specification sample.

11.8.2 Summary - Mechanical snubbers Per Technical Specifications, 10% of the total installed mechanical snubbers as well as previ-ous outage functional test failures were tested utilizing the WYLE Model 150 Snubber Testing machine. The 10% sample is broken down by

  • snubber category size (small, medium and large) with 10% from each size selected each outage.

All selected snubbers are detailed below:

A. The 10% sample of the medium size snubbers included two (2) PSA-l's and nine (9) PSA-3 's.

B. The 10% sample of the large size snubbers included one (1) PSA-35.

C. Due to previous outage failures, 100% of the small size snubbers (PSA-1/4 1 s, PSA-1/2) are tested each outage. This result-ed in tests being performed on.one Model 1/4 and three Model 1/2.

Page 17 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's _Bridge, N.J. 08038
3. Plant Unit 1
4. owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

11.8.3 Results - Mechanical Snubbers A. One medium size Technical Specification sample snubber failed the functional test resulting in a sample expansion of eleven (11) additional tests.

B. All the small size snubbers were tested satisfactory.

11.9 Technical Specification 4.4.11.1 Reactor Coolant Pump Flywheel-Examination 11.9.1 Summary Southwest Research Institute {SwRI) under the direction of the ISI Group performed an in-place ultrasonic examination (UT) on Reactor Coolant Pump {RCP) Flywheels SN 3S-76P917 and SN 2S-76P917. Flywheel examinations are tracked by the RCP Motor serial number and original pump location.

There were no unacceptable indications identi-fied.

11.10 NRC Bulletin 82-02 "Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of Power Plants".

11.10.1 Summary Visual (VT) and Magnetic Particle {MT) exams were performed on the #11 through #14 Steam Generator (inlet & outlet) and Pressurizer Primary Manway Bolts. Also #11 through #14 Reactor Coolant Pumps main flange bolting was visually inspected.

Page 18 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES l

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza
  • 2.

3.

4.

5.

6.

Newark, N.J.

Plant Unit 1 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 owner's Certificate of Authorization (if required) N/A.

Commercial Service Date 7/1/77.

National Board Number for Unit N/A.

7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

There were several S/G (inlet & outlet) Pri-mary Manway washers replaced, due to deep galling. These washers were replaced in kind.

A VT revealed wastage on the shank of one bolt on #14 S/G Outlet manway. This bolt was replaced. There were several PZR Primary Manway bolts replaced, due to non service induced anomalies found during the VT.

NOTE: 100% of all the S/G and PZR manway bolts were examined during this refuel-ing outage.

There were no other unacceptable indications identified .

11.11.1 Summary Southwest Research Institute {SwRI), and MQS under the direction of the Salem ISI Group, performed augmented ultrasonic and dye pene-trant examinations on nine (9) 1. 5 11 Safety Injections welds, two (2) 2 11 Chemical Volume Control welds and two (2) 3 11 Chemical Volume Control welds.

NOTE: Seven (7) components had the 88-08 exams waived, due to the replacement of the 11 through 14 SJ17 valves (DCP lE0-2309) . The associated replacement welds were not ultrasonically examined as required by NRC Bulletin 88-08. NRC Bulletin 88-08 is concerned with a service induced condition, which would not exist with these new welds.

There were no unacceptable indications identi-fied.

Page 19 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

11.12 NRC Bulletin 88-11 "Pressurizer Surge Line Thermal stratifi.cation".

11.12.1 Summary The Salem ISI group performed visual examina-tions on all existing surge line pipe supports

/ HEBA restraints and their associated insula-tion. A total of ten (10) supports were examined.

There were no unacceptable indications identi-fied.

11.13 NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants".

11.13.1 Summary Measurements were taken at one hundred and sixty four (164) locations to identify possible pipe erosion/corrosion. Of the 164 locations, 147 were from the original scope and 17 were the result of significant wall thinning found in 15*components. Fifteen (15) components were cut out and replaced and one (1) compo-nent received external weld "build-up". Other than the aforementioned areas, no other condi-tions were observed.

11.14 Field Directive, S-C-R700-MFD-288, "Leak Rate Test Program for the Steam Generator Blowdown Isolation Valve (GB4) 11.14.1 PSE&G Research and Testing Lab under the field supervision of the Salem ISI Group, conducted leak rate tests on all four Steam Generator Blowdown Valves (GB-4's) in accordance with procedure SC.SS-IS.GB-0004(Q).

Page 20 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 3
  • Plant Unit 1
4. owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

11.14.2 Results All four valves had an acceptable leak rates below the test acceptance criteria of ~ 30,000 SCCM. No discrepancies were noted.

11.15 Summary NuReg 0578 - TMI Lessons Learned -

A. Twenty-seven (27) System Pressure Tests were com-pleted per NUREG 0578 commitments.

Completed System Pressure Tests on the following systems:

Chemical Volume and Control Safety Injection Containment Spray Sampling Liquid Radwaste Waste Gas Residual Heat Removal B. The PSE&G Research Corp., under the direction of the Salem ISI Group conducted the Waste Gas System Leak Test in accordance with procedure SC.SS-IS.WG-0003(R).

11.15 .1 Results A. The leakage on systems defined by NUREG 0578 were identified as minor mechanical leakage and would not have any adverse impact on the Auxiliary building access during an accident. Work requests were initiated for repairs.

B. The Waste Gas System Leak Rate Test showed no adverse findings relative to this Bulletin.

Page 21 of 22

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101
2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
3. Plant Unit 1
4. Owner's Certificate of Authorization (if required) N/A.
5. Commercial Service Date 7/1/77.
6. National Board Number for Unit N/A.
7. Examination Dates: 08-17-92 through 02-02-94.
11. Examination Summary (cont'd):

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Date ~ 30 , 19 tl signed PSE&G owner By~. JI-~

Certificate of Authorization No. (if applicable) N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the state or Province of New Jersey and employed by Arkwright Mutual Insurance Company, Norwood, Massachusetts, have inspected the components described.in this Owner's Data Report during the period 08-17-92 to 02-02-94 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owner's Data Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employ-er makes any warranty, e~pressed or implied, concerning the examinations and corrective measures described in this Owner's Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date - -J-l/

, 19~v Commissions National Board, State, Province and No.

Page 22 of 22

PUBLIC SERVICE ELECTRIC & GAS CO.

SALEH NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.O)

SECTION XI COMPLETE COXPORERTS SECORD INTERVAL, SECORD PERIOD, SECORD OUTAGE (93RF)

Karch 4, 1994 REVISION 0 Date i3ld.1'1.

I Date Date

-of<ifaL/'

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE:

' REVISIO'H: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND* INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS EACTOR PRESSURE VESSEL N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

CIRCUMFERENTIAL WELDS CREF. DWG. NO. A*1) 002001 1*RPV-7042 B-A UT1.5 VS1SSISRCE0094Q X * - PERFORM MANUAL UT FROM THE SURFACE OF VESSEL TO FLANGE B1.30 UT5.7 X THE VESSEL FLANGE ON 100~ VESSEL TO UT12.5 X FLANGE WELD (#1 THRU 54, STUD HOLES).

W.0.#931121035 TO PERFORM NOE.

    • 53-SAM/109-SAM**

THREADS IN FLANGE (REF. DWG. NO. A*2) 003700 1*RPV*LIG 1 THRU 54 B-G-1 UTO VS1SSISRCE0009Q X - - EXAMINE LIGAMENTS #18 THRU #54.

B6.4D W.0.#931121035 TO PERFORM NOE.

    • 7-1.25-8-CS-60-SAM**

REACTOR VESSEL SUPPORT CREF. DWG. NO. A-1>

003751 1-RPV-11CLSUPPORT F-A VT-3 S1SSISZZ0020Q X - - THIS EXAM IS TO BE COORDINATED WITH THE SLIDING SUPPORT F2.10 SAFE END WELD EXAMINATIONS ON THE #11 COLD LEG. W.O. # 931121035, TO PERFORM NOE.

003752 1-RPV-12HLSUPPORT F-A VT-3 S1SSISZZ0020Q X - - THIS EXAM IS TO BE COORDINATED WITH THE SLIDING SUPPORT F2.10 SAFE END WELD EXAMINATIONS OF THE #12 HOT LEG. W.0.# 931121035, TO PERFORM NOE.

INTERIOR (REF. 1?WG-. NO. *A-1) 004310 RPV INTERNAL SURFACE B-N-1 VT-3 VS1SSISZZ002QQ X - - SWRI TO PERFORM VT-3 INSPECTION.

B13.10 W.0.#931121035 TO PERFORM NOE *. FOR SMD TO SUPPORT THE RPV VT, SEE W.0.#

930601189.

CONTROL ROD DRIVE HOUSINGS (REF. DWG. NO. A-2B>

006050 1-CRDH B-0 PT (#72) VS1SSISZZ0003Q X - - EXAMINED #72 & 73 CRDH, NEAR #50 STUD CRD HOUSING BODY-TO-ADAPTER 814.10 PT (#73) X HOLE. W.O. #931121035 TO PERFORM NOE.

WELDS

, DATE: ,03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 2 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS

.PRESSURIZER N 0 ASHE 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM *No METHOD PROCEDURE C M R **CALIBRATION BLOCK**

BOLTING CREF. DWG. NO. A-3) 007820 PZR BOLTING-HANWAY B-G-2 VT-1 (ISi) SCSSISZZ0010Q - - X A FLORESCENT MT EXAM TO BE PERFORMED ?ER B7.21 VT-1 (PSI) X - - NRC BULLETIN 82-02. MQS TO PERFORM THE MT VSHSSSPZZ0202Q X - - MT AND PSE&G TO PERFORM THE VT. W.O.

  1. 920401058 & 931121035 TO PERFORM NOE.

SEVERAL BOLTS WERE REPLACED PER CJP

  1. S-93-254 & w.o. #930401183
  • DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 3
  • REVISION: 0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS TEAM GENERATOR 11 N 0 ASME O G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

BOLTING CREF. DWG. NO. A*4) 008790 11*STG*OMB B-G-2 VT-1 SCSSISZZ0010Q x A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS*OUTLET MANWAY B7.30 MT VSHSSSPZZ0202Q x 82-02. MQS TO PERFORM T~E MT AND PSE&G TO PERFORM THE VT. W.O. # 931105020 AND 931121035 TO PERFORM ND.

008795 11*STG-IMB B-G-2 VT-1 SCSSISZZ0010Q x A FLORESCENT MT EXAM TO.BE PERFORMED PER BOLTS-INLET MANWAY B7.30 MT VSHSSSPZZ0202Q x 82-02.' MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931105020 AND 931121035 TO PERFORM NOE *

, DATE: ,03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 4 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS STEAM GENERATOR 12 N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

BOLTING (REF. DWG. NO. A-5) 009650 12-STG-OMB B-G-2 VT-1 SCSSISZZ0010Q X - - A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-OUTLET MANWAY B7.30 MT VSHSSSPZZ0202Q X 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931121035 &

931105031 TO PERFORM NOE.

009675 12-STG-IMB B-G-2 VT-1 SCSSISZZ0010Q X A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-INLET MANWAY B7.30 MT VSHSSSPZZ0202Q X - - 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931121035 &

931105031 TO PERFORM NOE

  • DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 5
REVISION: 0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS TEAM GENERATOR 13 N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

BOLTING (REF. DWG. NO. A-6) 010550 13-STG-OMB B-G-2 VT-1 SCSSISZZ0010Q x A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-OUTLET MANWAY B7.30 MT VSHSSSPZZ0202Q x 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931105032 AND 931121035 TO PERFORM NOE.

010575 13-STG-IMB B-G-2 VT-1 SCSSISZZ0010Q x A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-INLET MANWAY B7.30 MT VSHSSSPZZ0202Q x 82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. # 931105032 AND 931121035 TO PERFORM THE NOE.

, DATE: ,03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 6 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI CCJIPLETE COMPONENTS

.STEAM GENERATOR 14 N O ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

BOLTING (REF. DWG. NO. A-7) 011450 14-STG-OMB B-G-2 VT-1 SCSSISZZ0010Q X A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-OUTLET MANWAY B7.30 MT VSHSSSPZZ0202Q x 82-02. MQS TO PERFORM MT & PSE&G TO PERFORM VT. W.O. #931121035 & 931105033 TO PERFORM NOE. #14CL BOLT #16 WAS FOUND TO HAVE WASTAGE ON BOLT SHANK.

CJP # S-93-262 REPLACED BOLT W/

SATISFACTORY PSI VT.

011475 14-STG-IMB B-G-2 VT-1 SCSSISZZ0010Q X A FLORESCENT MT EXAM TO BE PERFORMED PER BOLTS-INLET MANWAY B7.30 MT VSHSSSPZZ0202Q X - 02. MQS TO PERFORM THE.MT & PSE&G TO PERFORM VT. w;o. #931105033 & 931121035 TO PERFORM NOE.

"'C.* **

DATE: 03/04/94 SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 7

' REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS CHEMICAL AND VOLUME CONTROL SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! FI CATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK**

12*CV*1143 ~REF. DWG. NO. A*82 011700 12-CV-1143*3 B*J PT VS1SSISZZ0003Q x . - W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO ELBO\I B9.11 UT45 VS1SSISZZ0014Q - x - INDICATIONS ARE GEOMETRIC REFLECTORS UT45T x FROM THE WELD ROOT AND COUNTERBORE.

UT45TAN x

    • 12*SS-160-1.283.*21 *SAM**

3-CV-1141 ~REF. DWG. NO. A-92 016701 3-CV-1141*14 A*E PT VS1SSJSZZ0003Q x EXAMINED PER NRC BULLETIN 88*08.

VALVE TO ELBOW NB88-08 UT45 VS1SSISZZ0014Q x - - W.0.#931121035 TO PERFORM NOE.

UT45T x - -

UT45TAN x

    • 3-SS-160*.451-30-SAM**

016801 3*CV*1141-15 A*E PT VS1SSJSZZ0003Q x - - EXAMINED PER NRC BULLETIN 88-08.

ELBOW TO BRANCH CONNECTION NB88-08 UT45 VS1SSISZZ0014Q . x - W.0.#931121035 TO PERFORM NOE. THE UT45 UT45T x - - INDICATION JS A GEOMETRIC REFLECTOR FROM UT45TAN x THE WELD ROOT.

    • 3-SS-160-.451-30*SAM**

2-CV-1175 ~REF. DWG. NO. A-11, A*122 022001 2*CV*1175-35 A-E PT VS1SSISZZ0003Q x EXAMINED PER NRC BULLETIN 88-08.

VALVE TO PIPE NB88*08 UT45 VS1SSJSZZ0016Q x W.0.#931121035 TO PERFORM NDE.

UT45T x . -

UT70 x - -

.,.,. **1.5-SS-COUP-111-SAM**

022101 2*CV*1175*36 A-E PT* VS1SSISZZ0003Q x EXAMINED.PER NRC BULLETIN 88*08.

PIPE TO TEE NB88*08 UT45 VS1SSISZZ0016Q x - - W.0.#931121035 TO PERFORM NOE.

UT45T x UT70 x

    • 1.5-SS-COUP-111-SAM**

, DATE: p3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 8 REVISION: 0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS PRESSURE RELIEF SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK**

4-PR-1100 {REF. DWG. NO. A-162 026600 4-PR-1100-8 B-J PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE.

PIPE TO TEE B9.11 UT45 VS1SSISZZ0014Q x UT45T x - -

UT45TAN x

    • 4-SS-160-.533-28-SAM-Rl"*

3-PR-1107 {REF. DWG. NO. A-162 027400 3-PR-1107-6 B-J PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NDE.

PIPE TO ELBOW B9.21 027600 3-PR-1107-8 B-J PT VS1SSISZZ0003Q X - - W.O. 931121035 TO PERFORM NOE.

PIPE TO ELBOW B9.21 3-PR-1106 CREF. DWG. NO. A-17) 028500 3-PR-1106-3 B-J PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NDE.

ELBOW TO PIPE B9.21

' DATE: , 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 10 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

~REACTOR SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS COOLANT SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! FI CATION ITEM NO METHOD PROCEDURE c MR **CALIBRATION BLOCK**

29-RC-1140 (REF. DWG. NO. A-27l 047301 29-RC-1140-1 B-F PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE. FOR SMD NOZZLE TO SAFE-END B5.130 TO REMOVE THE SANDBOX COVERS, SEE W.0.#

930601187.

    • 37-SAM/76-SAM**

047401 29-RC-1140-2 B-J PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO PIPE B9.11 TO REMOVE THE SANDBOX COVERS, SEE W.0.#

930601187.

    • 2.312-SS-37-SAM**

29-RC-1120 (REF. DWG. NO. A-29l 050901 29-RC-1120-1 B-F PT VS1SSISZZ0003Q *x - - w.o.#931121035 TO PERFORM NOE. FOR SMD NOZZLE TO SAFE-END B5.130 TO REMOVE THE SANDBOX COVERS, SEE W.0.#

930601187.

    • 37-SAM/76-SAM**

051001 29-RC-1120-2 B-J PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO PIPE B9.11 TO REMOVE THE SAND~OX COVERS, SEE W.0.#

930601187.

  • .*2.312-SS-37-SAM**

27.5-RC-1130 (REF. DWG. NO. A-32l 057201 27.5-RC-1130-4. B-J PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE. FOR SMD ELBOW TO SAFE-END~* B9.11 TO REMOVE THE SANDBOX COVERS, SEE W.0.#

930601187.

    • 2.312-SS-37-SAM**

057301 27.5-RC-1130-5 B-F PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO NOZZLE B5.130 TO REMOVE THE SANDBOX COVERS, SEE W.0.#

930601187.

    • 37-SAM/76-SAM**

27.5-RC-1110 (REF. DWG. NO. A-34l 059901 27.5-RC-1110-4 B-J PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE. FOR SMD ELBOW*TO SAFE-END B9.11 TO REMOVE THE SANDBOX COVERS, SEE W.0.#

930601187.

    • 2.312-SS-37-SAM**

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 11

'REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~EACTOR. COOLANT SYSTEM CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOO PROCEDURE C M R **CALIBRATION BLOCK**

27.5-RC-1110 CREF. DWG. NO. A-34) 060001 27.5-RC-1110-5 B-F PT VS1SSISZZ0003CI X - - W.0.#931121035 TO PERFORM NOE. FOR SMD SAFE-END TO NOZZLE 85.130 TO REMOVE THE SANDBOX COVERS, SEE W.0.#

930601187.

    • 37-SAM/76-SAM**

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 12 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK**

12*SJ*1151 CREF. DWG. NO. A-53) 094700 12-SJ-1151*3 B*J PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NOE. THIS ELBOW TO PIPE - B9.11 UT45 VS1SSISZZ0014Q - x - WELD REPLACES

SUMMARY

  1. 094600, DUE TO A UT45T x HANGER OBSTRUCTION. THE UT45 UT45TAN x INDICATIONS ARE GEOMETRIC REFLECTORS UTO VS1SSISZZ0018Q x - - FROM THE WELD ROOT.
    • 12-SS-160-1.283-21-SAM**

10-SJ-1141 (REF. DWG. NO. A-54) 096700 10-SJ-1141-14 B*J PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE.

VALVE TO TEE B9.11 UT45 VS1SSISZZ0014Q - - x LIMITATION: THE EXAM IS LIMITED TO 0%

UT45T - - x COVERAGE, DUE TO VALVE \ TEE CONFIGURATION.

    • 10-SS-160-1.119-22-SAM**

8-SJ-1162 {REF. DWG. NO. A-58, A-592 105000 8-SJ-1162*5 B*J .PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO PIPE B9.11 UT45 VS1SSISZZ0014Q - x - INDICATIONS ARE GEOMETRIC REFLECTORS UT45T x FROM THE WELD ROOT.

UT45TAN x

    • 8-SS*XX*.860-23-SAM**

8-SJ-1152 CREF. DWG. NO. A-60, A-61>

109600 8*SJ*1152*4PS*2 B*K-1 PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE.

PENETRATION TO ?IRE B10.10 109900 8-SJ-1152*6 8-J PT VS1SSISZZ0003Q

  • x W.0.#931121035 TO PERFORM NOE *. THE UT45 PIPE TO ELBOW 89.11 UT45 VS1SSISZZ0014Q - x - INDICATIONS ARE GEOMETRIC INDICATIONS UT45T x FROM THE WELD ROOT AND COUNTERBORE.

UT45TAN . x

    • 8-SS*XX*.860*23-SAM**

4-SJ-1182 {REF. DWG. NO. A-74) 129000 4-SJ-1182-14 B*J PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. THE UT45 PIPE TO ELBOW B9.11 UT45 VS1SSISZZ0014Q - x - INDICATIONS ARE GEOMETRIC REFLECTORS UT45T x FROM THE WELD ROOT.

UT45TAN x

    • 4*SS*160*.533*28*SAM-R**

DATE: 03/04/94 SALEM NUCLEAR PO\IER STATION UNIT* 1 PAGE: 13 REVISION: 0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK**

4*SJ-1172 {REF. DWG. NO. A*75l 131200 4-SJ-1172-5 B-J PT VS1SSISZZ0003Q x W.0.#931121035 CNDE). THE PT EXAM ELBO\I TO PIPE B9.11 PT x - - REVEALED 6 LINEAR RECORDABLE UT45 VS1SSISZZ0014Q - x - INDICATIONS. DURING THE RELEVANCY UT45T x DETERMINATION PROCESS, SURFACE UT45TAN x CONDITIONING PROCEEDED A.RE-EXAM WITH NO LINEAR INDICATIONS IDENTIFIED. UT45 GEOMETRIC, DUE TO WELD COUNTERBORE.

    • 4-SS-160-.533-28-SAM-R**

133800 4-SJ-1172-28 B-J PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. THE UT45 TEE TO REDUCER B9.11 UTOL VS1SSISZZ0018Q x INDICATION IS A GEOMETRIC REFLECTOR FROM UT45 VS1SSISZZ0014Q - x - THE WELD ROOT.

UT45T x - -

UT45TAN x - - **4-SS-160-.533-28-SAM-R**

3-SJ-1192 {REF. DWG. NO. A-722 134700 3-SJ-1192-BA B-J PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE.

PIPE TO PIPE B9.21 2-SJ-1147 CREF. DWG. NO. A-78) 141500 2-SJ-1147-8FB B-G-2 VT-1 SCSSISZZ0010Q X - - W.O.# 920810139 & 931121035.

FLANGE BOLTING B7.50 2-SJ-1137 CREF. DWG. NO. A-802 147900 2-SJ-1137-10FB B-G-2 VT-1 SCSSISZZ0010Q X - - W.0.# 920810145 &931121035.

FLANGE BOLTING 87.50 2-SJ-1128 CREF. DWG. NO. A-83.84,852 155500 2-SJ-1128-2FB B-G-2 VT-1 SCSSISZZ0010Q X - - W.0.# 920810149 & 931121035.

FLANGE BOLTING B7.50

, DATE: , 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 14 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N O ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION_ ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

2-SJ-1128 CREF. DWG. NO. A-83.84.85) 158200 2-SJ-1128-29 B-J PT VS1SSISZZ0003Q X - - W.O. #931121035 TO PERFORM NOE. THIS ELBOW TO PIPE B9.40 WELD REPLACES

SUMMARY

  1. 157900, DUE TO HANGER INTERFERENCE *.

158600 2-SJ-1128-32 B-J PT VS1SSISZZ0003Q X - - W.O. #931121035 TO PERFORM NOE. THIS PIPE TO COUPLING B9.40 EXAM REPLACES

SUMMARY

  1. 159100, DUE TO ALARA CONCERNS.

SUMMARY

  1. 159100 WAS LOCATED IN THE DECAY TUNNEL.

2-SJ-1118 CREF. DWG. NO. A-87. A-88) 165800 2-SJ-1118-4FB B-G-2 VT-1 SCSSISZZ0010Q X - - W.0.# 920810151 & 931121035.

FLA.NGE BOL Tl NG B7.50 1.5-SJ-1142 ~REF. DWG. NO. A-89,90,91}

174300 1 1/2-SJ-1142-43 ELBOW TO PIPE B-J PT VS1SSISZZ0003Q x - - W.O. #931121035 TO PERFORM NOE. THIS B9.40 WELD REPLACED

SUMMARY

  1. 174100, DUE TO A HANGER OBSTRUCTION.

174900 1 1/2-SJ-1142-49R PIPE TO VALVE B-J B9.40 PT VHSSSSPZZ0206Q x - - PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-184 & W.0#

920508129.

175001 1/2-SJ-1142-50R VALVE TO PIPE A-E NB88-08 UT PT VHSSSSPZZ0206Q x - - 88-08 EXAMS WAIVED, REPLACEMENT.

W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-184 &W.0#

920508129.

    • 1.5-SS-COUP-111-SAM**

175101 1 1/2-SJ-1142-51R A-E PT VHSSSSPZZ0206Q x - - 88-08 EXAMS WAIVED, REPLACEMENT.

PIPE TO ELBOW NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PE~FORMED, DUE TO THE REPLACEMENT OF THIS IJELO PER DCP 1E0-2309, CJP# S-93-184 & W.0#

920508129.

    • 1.5-SS-COUP-111-SAM**

,DATE: 0,3/04/94 SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 15 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~AFETY INJECTION SYSTEM CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION . ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

1.5-SJ-1142 CREF. DWG. NO. A-89.90.91) 179500 1 1/2-SJ-1132-39R B-J PT VHSSSSPZZ0206Q X - - PSI BASELINE EXAMINATION.WAS PERFORMED, PIPE TO VALVE B9.40 DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0#

921117149.

179601 1 1/2-SJ-1132-40R A-E PT VHSSSSPZZ0206Q X - - 88-08 EXAMS WAIVED, REPLACEMENT.

VALVE TO PIPE NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & .W.0#

921117149.

    • 1. 5-SS-COUP-*111-SAM**

179701 1/2~SJ-1132-41R A-E PT VHSSSSPZZ0206Q X - - 88-08 EXAMS WAIVED, REPLACEMENT.

PIPE TO ELBOW NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0#

921117149.

    • 1.5-SS-COUP-111-SAM**

179801 1 1/2-SJ-1132-42 A-E PT VHSSSSPZZ0206Q x EXAMINED PER NRC BULLETIN 88-08. W.O.

ELBOW TO PIPE NB88-08 UT45 VS1SSISZZ0016Q x #931121035 TO PERFORM NOE.

UT45T x UT70 x

    • 1.5-SS-COUP-111-SAM**

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 16

' REVISIClN: 0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK**

1.5-SJ*1132 {REF. OWG. NO. A*92, A*93l 179901 1 1/2*SJ*1132*43 A*E PT VS1SSISZZ0003Q x EXAMINED PER NRC BULLETIN 88-08.

PIPE TO BRANCH CONNECTION NB88*08 UT45 VS1SSISZZ0016Q x - . W.0.#931121035 TO PERFORM NOE.

UT45T x UT70 x

':')

    • 1.5-SS-COUP-111*SAM**

1.5*SJ*1122 {REF. DWG. NO. A*94, A-952 184600 1 1/2*SJ-1122-41R 'B*J PT VHSSSSPZZ0206Q x - - PSI BASELINE EXAMINATION WAS PERFORMED.

TEE TO PIPE B9.40 DUE TO THE REPLACEMENT OF ~HIS WELD PER DCP 1E0-2309; CJP# S-93-181 &W.0.3 930709175.

184700 1 1/2-SJ*1122*42R B*J PT VHSSSSPZZ0206Q x - . PSI BASELINE EXAMINATION WAS PERFORMED, PIPE TO VALVE B9.40 DUE TO THE REPLACEMENT OF THIS WELD PER OCP 1E0-2309, CJP# S-93-181 & W.0#

930709175.

184801 1 1/2-SJ*1122-43R A-E PT VHSSSSPZZ0206Q x . . 88-08 EXAMS WAIVED, REPLACEMENT.

VALVE TO PIPE NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-181 & W.0#

930709175.

    • 1.5-SS-COUP-111-SAM**

184901 1/2-SJ-1122-44 A-E PT VHSSSSPZZ0206Q x EXAMINED PER NRC BULLETIN 88-08. w.o.

PIPE TO ELBOW NB88*08 UT45 VS1SSISZZ0016Q x #931121035 TO PERFORM NOE.

UT45T x UT70 x

    • 1.5-SS-COUP-111*SAM**

185001 1/2-SJ-1122-45 A-E PT VHSSSSPZZ0204Q x EXAMINED PER NRC BULLETIN 88-08. '.1.0.

ELBOW TO PIPE NB88-08 UT45 VS1SSISZZ0016Q x #931121035 TO PERFORM NOE.

UT45T x UT70 x

    • 1.5-SS-COUP-111-SAM**

185101 1 1/2-SJ-1122-46 A-E PT VS1SSISZZ0003Q x EXAMINED PER NRC BULLETIN 88-08.

PIPE TO BRANCH CONNECTION NB88-08 UT45 VS1SSISZZ0016Q x - - W.0.#931121035 TO PERFORM NOE.

UT45T x UT70 x

    • 1.5-SS-COUP-111-SAM**

DATE: 93/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 17

' REVISION:*

0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~AFETY INJECTION SYSTEM CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTI Fl CATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK**

1'.5*SJ-1112 CREF. DWG. NO. A-96. A-97>

190100 1 1/2-SJ-1112-49R B-J PT VHSSSSPZZ0206Q x - - PSI BASELINE EXAMINATION WAS PERFORMED, PIPE TO VALVE B9.40 DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 & W.0#

921117147.

190201 1 1/2-SJ-1112-50R A-E PT VHSSSSPZZ0206Q x - - 88-08 EXAMS WAIVED, REPLACEMENT.

VALVE TO PIPE NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS* PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 & W.0#

921117147.

    • 1.5-SS-COUP-111-SAM**

190301 1/2-SJ-1112-51R A-E PT VHSSSSPZZ0206Q

  • x - - 88-08 EXAMS WAIVED, REPLACEMENT.

PIPE TO ELBOW NB88-08 UT W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-182 &W.0#

921117147.

    • 1.5-SS-COUP-111-SAM**

190401 1 1/2-SJ-1112-52 A-E PT VHSSSSPZZ0206Q x EXAMINED PER NRC BULLETIN 88-08. w.o.

ELBOW TO PIPE NB88-08 UT45 VS1SSISZZ0016Q x #931121035 TO PERFORM NOE.

UT45T x UT70 x

    • 1.5-SS-COUP-111-SAM**

190501 1/2-SJ-1112-53 A-E PT VS1SSISZZ0003Q x - - EXAMINED PER NRC BULLETIN 88-08.

PIPE TO BRANCH CONNECTION NB88-08 UT45 VS1SSISZZ0016Q x - - w.o.#931121035 TO PERFORM NOE.

UT45T x - -

UT70 x

    • 1.5-SS-COUP-111-SAM**

, DATE: ~3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 18 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~EACTOR COOLANT PUMP 12 CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 191800 12*PMP*1LG B-K-1 PT VS1SSISZZ0003Q X *

  • W.0.#931121035 TO PERFORM NOE.

LUG B10.20 LIMITATION: THE EXAM IS LIMITED TO 72%

COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.

191850 12-PMP-2LG B-K-1 PT VS1SSISZZ0003Q X -

  • W.0.#931121035 TO PERFORM NOE.

LUG B10.20 LIMITATION: THE EXAM IS LIMITED TO 72%

COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.

191900 12*PMP*3LG B*K-1 PT VS1SSISZZ0003Q X *

  • W.0.#931121035 TO PERFORM NOE.

LUG B10.20 LIMITATION: THE EXAM IS LIMITED TO 76%

COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.

PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 192101 12-PMP*FLW A-E UTOL VS1SSISZZ0001Q x PERFORM IN-PLACE UT EXAMINATION PER PER PUMP MOTOR FLYWHEEL (IN-PLACE) RG1.14 UT45 x NRC REGULATORY GUIDE 1.14 & W.O.

  1. 931121035 ON RCP MOTOR FLYWHEEL S/N 3S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO THE BORE AND BOLT HOLES.
    • 42-SAM**

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 19 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~EACTOR COOLANT PUMP 14 CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME O G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 193400 14-PMP-1LG B-K-1 PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

LUG B10.20 LIMITATION: THE EXAM IS LIMITED TO 77%

COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.

193450 14-PMP-2LG B-K-1 .PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

LUG B10.20 LIMITATION: THE EXAM IS LIMITED TO 74%

COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.

193500 14-PMP-3LG B-K-1 PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

LUG B10.20 LIMITATION: THE EXAM IS LIMITED TO 76%,

DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG.

PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 193701 14-PMP-FLW A-E UTOL VS1SSISZZ0001Q X PERFORM IN-PLACE UT EXAMINATION PER NRC

. PUMP MOTOR FLYWHEEL (IN-PLACE) RG1.14 UT45 X - - REGULATORY GUIDE 1.14 &W.O. #931121035 ON THE RCP MOTOR FLYWHEEL S/N 2S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO BORE AND BOLT HOLES.

    • 42-SAM**

, DATE: ,03/04/94 SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 20 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

  • ~

CLASS 1 SECTION xr COMPLETE COMPONENTS N O ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

VALVE BODIES 193870 12 SJ 55 VB B-M-2 VT-3 S1SSISZZ0010Q X - - W.O. 931121035 TO PERFORM NDE.

ON LINE 10-SJ-1121 B12.50 BOLTING CREF. DWG. NO. A-10>

194100 1 CV 78 B-G-2 VT-1 SCSSISZZ0010Q - - x W.0.# 920810209 AND 931121035 TO PERFORM ON LINE 3-CV-1133 B7.70 NDE. ONE (1) STUD WAS FOUND WITH INADEQUATE THREAD ENGAGEMENT. A DR WAS ISSUED TO SYSTEM ENGINEERING. w.o.

  1. 93100204 CORRECTED THE THREAD ENGAGEMENT PROBLEM. A SA Tl SFACTORY RE-EXAM WAS PERFORMED.

BOLTING 194700 1 PR 1 B-G-2 VT-1 SCSSISZZ0010Q x - - PSI BASELINE EXAMINATION WAS PERFORMED, ON LINE *3-PR-1106 B7.70 DUE TO DCP 1EC-3219-1, CJP# PS-93-053 &

W.0.# 930126150. NEW STUDS AND NUTS WERE INSTALLED.

194800 1 PR 2 B-G-2 VT-1 SCSSISZZ0010Q x - - PSI BASELINE 'EXAMINATION WAS PERFORMED, ON LINE 3-PR-1107 B7.70 DUE TO DCP 1EC-3219-1, CJP# PS-93-054 &

W.0.# 930126150. NEW STUDS AND NUTS WERE INSTALLED.

~*

195400 1 PS 1 B-G-2 VT-1 SCSSISZZo010Q x - - THE BOLTING WAS REPLACED PER ON.LINE 4-PS-1111 B7.70 1EC-3249-1/PS-93-056/930708108 &

931121035.

195500 1 PS 3 B-G-2 VT-1 SCSSISZZ0010Q x - - THE BOLTING WAS REPLACED PER ON LINE 4-PS-1131 B7.70 1EC-3249-1/PS-93-057/930708111 &

931121035.

197000 11 SJ 43 B-G-2 VT-1 SCSSISZZ0010Q x - - W.0.# 920810155 AND 931121035 TO PERFORM ON LINE 6-SJ-1112 B7.70 NDE.

, DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 21 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS N O ASHE 0 G T SEC. -XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

BOLTING CREF. DWG. NO. A-68) 197900 12 SJ 43 B-G-2 VT-1 SCSSISZZ001QQ X - - W.0.# 920810158 AND 931121035 TO PERFORM ON LINE 6-SJ-1122 B7.70 NOE.

BOLTING CREF. DWG. NO. A-56) 198200 12 SJ 55 B~G-2 VT-1 SCSSISZZ0010Q - - x W.0.# 920810195 & 931121035 TO PERFORM ON LINE 10-SJ-1121 B7.70 NOE. THE VT-1 EXAM REVEALED BORON RESIDUE BETWEEN THE VALVE BODY TO BONNET. THE VALVE WAS DISASSEMBLED &

INSPECTED & BOLTING MATERIAL WAS REPLACED UNDER W.O. # 931002074 & CJP

  1. S-93-250.

198300 12 SJ 56 B-G-2 VT-1 SCSSISZZ0010Q x - - -W.0.# 920810203 ON LINE 10-SJ-1121 B7.70 BOLTING CREF. DWG. NO. A-66) 198800 13 SJ 43 B-G-2 VT-1 SCSSISZZ0010Q - - x W.0.# 920810161 & 931121035 TO PERFORM ON LINE 6-SJ-1132 B7.70 NOE. BORON RESIDUE WAS FOUND ON SEVERAL STUDS. W.O. #931026136 REMOVED THE BORON AND A SATISFACTORY VT RE-EXAM WAS PERFORMED.

BOLTING CREF. DWG. NO. A-67) 199200 13 SJ 156 B-G-2 VT-1 SCSSISZZ0010Q x - - W.0.# 920810173-ON LINE 6-SJ-1131 B7.70 BOLTING 199500 14 RH 27 B-G-2 VT*1 SCSSISZZ0010Q x - - THE BOLTING MATERIAL WAS REPLACED IH ON LINE 8-SJ-1145 B7.70 ACCORDANCE WITH CJP #S-93-249 & W.O.

  1. 940326008.

199600 14 SJ 43 B-G-2 VT-1 SCSSISZZ0010Q x - - W.0.# 920810162 AND 931121035 TO PERFORM ON LINE 6-SJ-1142 B7.70 NOE.

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 22

'REVIS1014: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E. REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

BOLTING (REF. DWG. NO. A-54) 199700 14 SJ 54 B-G-2 VT-1 SCSSISZZ0010Q - - X W.0.# 920810207 & 931121035 TO PERFORM ON LINE 10-SJ-1141 B7.70 NOE. THE VT REVEALED BORON RESIDUE ON THE STUDS. W.O. #931013197 WAS INITIATED TO CLEAN OFF THE BORON. AFTER THE BORON WAS REMOVED A SATISFACTORY VT-1 EXAM WAS PERFORMED.

199800 14 SJ 55 B-G-2 VT-1 SCSSISZZ0010Q X - - W.0.# 920810201*

ON LINE 10-SJ-1141 B7.70 199900 14 SJ 56 B-G-2 VT-1 SCSSISZZ0010Q - - X W.0.# 920810206 &931121035 TO PERFORM ON LINE 10-SJ-1141 87.70 NOE. THE VISUAL EXAMINATION REVEALED SEVERAL STUDS WITH A LACK OF THREAD ENGAGEMENT. W.O. #930730004 DISSASSEMBLED & INSPECTED THIS VALVE.

DURING RE-ASSEMBLY THE LACK OF THREAD ENGAGEMENT WAS CORRECTED.

, DATE: p3/04/94 SALEM NUCLEAR PO\JER STATION UNIT 1 PAGE: 23 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~HEAD TANKS, VESSEL 11 CLASS 2 SECTION XI COMPLETE COMPONENTS N 0 ASHE 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-4) 204900 11-HT-1 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE.

UPPER HEAD TO SHELL C1.20 UTOW - - x LIMITATION: EXAM LIMITED TO 38%, DUE TO UT45 VS1SSISZZ0012Q x WELD CONFIGURATION. UT ON THE WELD NOT UT45T x PERFORMED, DUE TO THE WELD UT45TAN x CONFIGURATION.

    • 6-SS-10-.140-45-SAM**

, DATE: ,03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 24 REVISION: 0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

CLASS 2 SECTION XI CC>>4PLETE CC>>4PONENTS

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-6) 205020 1-RCF-1 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE.

UPPER HEAD TO FLANGE C1.20 UTOW x LIMITATION: EXAM LIMITED TO 74%, DUE TO UT45 VS1SSISZZ0012Q x - - CONFIGURATION.

UT45T x UT45TAN x **14-SS-10-.250-96-SAM**

205030 1-RCF-2 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE.

FLANGE TO SHELL C1.10 UTOW x LIMITATION: EXAM LIMITED TO 86%, DUE TO UT45 VS1SSISZZ0012Q x CONFIGURATION AND WELDED SUPPORT.

UT45T x UT45TAN x **14-SS-10-.250-96-SAM**

, DATE: ,03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 25 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~REGENERATIVE HEAT EXCHANGER CLASS 2 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

CIRCUMFERENTIAL WELDS (REF. DWG. NO. B-7) 205105 1-RHE-5 CAP TO SHELL C-A UTOL VS1SSISZZ0018Q x - - W.0.#931121035 TO PERFORM NDE. THE UT45 C1 .10 UTOW x INDICATION IS A GEOMETRIC REFLECTOR FROM UT45 VS1 SS! SZZ0013Q - x - THE INSIDE SURFACE.

UT45T x - -

UT60 x - - **9.5-SS-X-.750-86-SAM**

UT60T x 205120 1-RHE-8 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE. THE UT45 SHELL TO CAP C1 .10 UTOW x AND UT60 INDICATIONS ARE G~OMETRIC UT45 VS1SSISZZ0013Q - x - REFLECTORS FROM THE WELD ROOT.

UT45T x UT60 - x - **9.5-SS-X-.750-86-SAM**

UT60T x

PAGE: 26 ASME SEC. XI

SUMMARY

EXAMINATION AREA CATGY EXAM REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE **CALIBRATION BLOCK**

INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. B-8) 205170 11-RHRHEX-1VS c-c PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

VESSEL SUPPORT C3.10 205180 11-RHRHEX-2VS c-c PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

VESSEL SUPPORT C3.10

  • ~*

, DATE: P3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 27 REVISION: 0 OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS FEEDWATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! Fl CATION ITEM NO METHOD PROCEDURE c MR **CALIBRATION BLOCK**

16-BF-2141 (REF. DWG. NO. B-102 210601 16*BF*2141*1R A*E RT VSHSSSPZZ0210Q x - - PERFORM NOE UNDER W.O. # 9304216193. 45 REDUCER TO NOZZLE ATS UT45 VS1SSISZZ0017Q - x - AND 60 DEGREE INDICATIONS ARE GEOMETRIC UT45T x - - REFLECTORS FROM THE INSIDE SURFACE.

UT60 - x -

UT60T x **116-SAM**

16-BF-2131 (REF. DWG. NO. B-112 213401 16*BF*2131 *,1R A*E RT VSHSSSPZZ0210Q x PERFORM NOE UNDER W.O. 930426192. THE ELBOW TO NOZZLE ATS UT45 VS1SSISZZ0017Q x 60 DEGREE INDICATION IS A GEOMETRIC UT45T x REFLECTOR FROM THE WELD ROOT.

UT60 - x -

UT60T x **35-SAM/36-SAM**

16-BF-2121 (REF. DWG. NO. e-122 217791 16*BF*2121*1R A*E RT VSHSSSPZZ0210Q x PERFORM NOE UNDER W.O. # 930426190. THE REDUCER TO NOZZLE ATS UT45 VS1SSISZZ0017Q - x - 45 AND 60 DEGREE INDICATIONS ARE UT45T x GEOMETRIC REFLECTORS FROM THE WELD ROOT.

UT60 - x -

UT60T x **116-SAM**

16-BF-2111 (REF. DWG. NO. B-132 220573 16*BF*2111*1R A*E RT VSHSSSPZZ0210Q x PERFORM NOE UNDER- W.O. 930426188. THE REDUCER TO NOZZLE ATS UT45 VS1SSISZZ0017Q - x - 45 AND 60 DEGREE INDICATIONS ARE UT45T x GEOMETRIC REFLECTORS FROM THE WELD ROOT.

UT60 - x -

UT60T x - - **116-SAM**

DATE: 03/04/94 SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 28

' REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERia>, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS MAIN STEAM SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO- METHOD PROCEDURE _ C M R **CALIBRATION BLOCK**

32-MS-2141 CREF. DWG. NO. B-25) 227600 32-MS-2141-1 C-F-2 MT VS1SSISZZ0002Q X W.0.#931121035 TO PERFORM NOE.

NOZZLE TO REDUCER C5.51 UT45 VS1SSISZZ0017Q *X UT45T x - -

    • 32*CS-XX-1.618-47-SAM**

32-MS-2121 CREF. DWG. NO. B-27>

229900 32-MS-2121-2PS-1 c-c MT VS1SSISZZ0002Q X - - W.0.#931121035 TO PERFORM NOE.

PIPE SUPPORT C3.20 30-MS-2141 {REF. DWG. NO. B-25) 232000 30-MS-2141-1 C-F-2 MT VS1SSISZZ0002Q x - - W.0.#931121035 TO PERFORM NOE. THE UT45 REDUCER TO ELBOW C5.51 UT45 VS1SSISZZ0017Q - x - INDICATIONS ARE GEOMETRIC REFLECTORS UT45T x FROM THE WELD ROOT.

    • PL-1.5-CS-65-SAM**

232040 30-MS-2141-1LD-I C-F*2 MT VS1SSISZZ0002Q x - - W.0.#931121035 TO PERFORM NOE. EXAMINE LONGITUDINAL C5.52 UT45 VS1SSISZZ0017Q x 2.5T OF WELD LENGTH.

UT45T x

    • PL-1.5-CS-65-SAM**

232080 30-MS-2141-1LD-O C-F-2 MT VS1SSISZZ0002Q x - - W.0.#931121035 TO PERFORM NOE. - EXAMINE LONGITUDINAL C5.52 UT45 VS1SSISZZ0017Q x 2.5T OF WELD LENGTH.

UT45T x

    • PL-1.5-CS-65-SAM**

, DATE: .03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 29 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS PRESSURE RELIEF SYSTEM N O ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

12-PR-2101 CREF. DWG. NO. B-37, B-38) 254900 12-PR-2101-2 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NOE. THIS PIPE TOPiPE C5.11 . UT45 VS1SSISZZ0014Q x WELD REPLACED

SUMMARY

  1. 254400, DUE TO UT45T x HANGER INTERFERENCE. EXAMINED 2.5T OF UT45TAN x THE INTERSECTING LONGITUDINAL SEAM ON THE UP STREAM AND DOWN STREAM SIDE.
    • 31-SAM/66-SAM**

' DATE: P3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 30 REliISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS ESIDUAL HEAT REMOVAL SYSTEM N 0 ASME 0 G T SEC. XI R. E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOO PROCEDURE C M R **CALIBRATION BLOCK**

263294 14-RH-2114-16PS-2 c-c PT VS1SSI.SZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

PIPE SUPPORT C3.20 263296 14-RH-2114-16PS-3 c-c PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE.

.,..,.. PIPE SUPPORT 14-RH-2114-16PS-4 PIPE SUPPORT C3.20 c-c C3.20 PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE.

263304 14-RH-2114-18 C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE.

FLANGE TO PUMP CS.11 UT45T VS1SSISZZ0014Q x LIMITATION: THE UT EXAM WAS LIMITED TO

"'" SOX COVERAGE. THE TRANVERSE SCAN WAS THE ONLY UT PERFORMED, DUE TO THE FLANGE AND PUMP CONFIGURATION.

    • 14-SS-40-.438-79-SAM**

14-RH-2112 CREP. DWG. NO. B-46>

263384 14-RH-2112-29 C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE.

TEE TO PIPE CS.11 UT45 VS1SSISZZ0014Q x EXAMINATION INCLUDES 2.ST OF THE UT45T x INTERSECTING LONGITUDINAL SEAM ON THE UT45TAN x DOWN STREAM SIDE.

    • 14-SS-40-.438*79-SAM**

~1/.1 DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 31

' REVISIO!i: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

' SECOND INTERVAL, SECOND PERIOD,* SECOND OUTAGE (93RF)

CLASS 2 SECTION XI CC>>4PLETE COMPONENTS INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER !DENT! Fl CATION ITEM NO METHOD PROCEDURE c MR **CALIBRATION BLOCK**

14-SJ-2124 ~REF. DWG. NO. B-52) 263716 14-SJ-2124-1 C-F-1 PT VS1SSISZZ0003Q . x W.0.#931121035 TO PERFORM NOE.

VALVE TO ELBOW C5.11 UT45 VS1SSISZZ0014Q x LIMITATION: EXAM LIMITED TO 95X, DUE TO UT45T x CONFIGURATION OF VALVE.

UT45TAN x

    • 14-SS-40-.438-79-SAM**

263718 14-SJ-2124-HD-I C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. EXAMINE LONGITUDINAL C5.12 UT45 VS1SSISZZ0014Q x 2.5T OF WELD LENGTH.

UT45T x UT45TAN x

    • 14-SS-40-.438-79-SAM**

263no 14-SJ-2124-1LD-O .C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. EXAMINE LONGITUDINAL C5.12 UT45 VS1SSISZZ0014Q x 2.5T OF WELD LENGTH.

UT45T x UT45TAN x

    • 14-SS-40-.438-79-SAM**

l2-SJ-2152 ~REF. DWG. NO. B-54) 263830 12-SJ-2152-5 C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE.

ELBOW TO PIPE C5.11 UT45 VS1SSISZZ0014Q x - .;.

EXAMINATION INCLUDED 2.5T OF THE UT45T x INTERSECTING LONGITUDINAL SEAM DOWN UT45TAN x STREAM.

    • 12-SS-40-.377-31-SAM**

263896 12-sJ-2152-36 C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. EXAM PIPE TO PIPE C5.11 UT45 VS1SSISZZ0014Q - x - 2.5T OF LONG SEAM ON BOTH SIDES. THE UT45T x UT45 INDICATIONS ARE GEOMETRIC UT45TAN x REFLECTORS FROM THE INSIDE .SURFACE.

    • 12-SS-40-.377-31-SAM**

263898 12-SJ-2152-36PS-1 c-c PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE.

PIPE SUPPORT C3.20 263900 12-SJ-2152-36PS-2 c-c PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

PIPE SUPPORT C3.20

  • DATE: 03/04/94 SALEM NUCLEAR PO'JER STATION UNIT 1 PAGE: 32 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS

.SAFETY INJECTION SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOO PROCEDURE C M R **CALIBRATION BLOCK**

12-SJ-2152 CREF. DWG. NO. B-54) 263904 12-SJ-2152-36PS-4 c-c PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFOR~ NOE.

PENETRATION TO PIPE C3.20

, DATE: !>3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 33 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS CONTAINMENT SPRAY N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOO PROCEDURE C M R **CALIBRATION BLOCK**

8-CS-2114 (REF. DWG. NO. B-66) 355480 8-CS-2114-4 C-F-1 PT VS1SSISZZ0003Q x W.0.# 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW c5.11 UT45 VS1SSISZZ0014Q x EXAM REPLACES

SUMMARY

  1. 355400, DUE TO A UT45T x SUPPORT INTERFERENCE.

UTO VS1SSISZZ0018Q x - -

    • 8-SS .140-24-SAM** 0 355500 8-CS-2114-5 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NOE. THIS ELBOW TO PIPE c5.11 UT45 VS1SSISZZ0014Q x - - EXAM REPLACES

SUMMARY

  1. 355420, DUE TO A UT45T x SUPPORT INTERFERENCE.

UT45TAN x - -

UTO VS1SSISZZ0018Q x **8-SS-10-.140-24-SAM**

, DATE: ~3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 34 RE.VISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

CLASS 2 SECTION XI COMPLETE CC>>4PONENTS CHEMICAL & VOLUME CONTROL N 0 ASHE 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD *PROCEDURE c M R **CALIBRATION BLOCK**

3*CV-2163 ~REF. DWG. NO. B-702 358300 3-CV-2163-6 C-F-1 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q x WELD REPLACES

SUMMARY

  1. 365500, DUE TO UT45T x ALARA CONCERNS. THE WELD WAS LOCATED IN UT45TAN x - - THE SEAL WATER INJECTION FILTER ROC>>4.

UTOL VS1SSISZZ0018Q x **3-SS-160-.451-30-SAM**

358320 3-CV-2163-7 C-F-1 PT VS1SSISZZ0003Q x - - W.0 *. 931121035 TO PERFORM NOE. THIS ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q - x - WELD REPLACES

SUMMARY

  1. 365520, DUE TO UT45T x ALARA CONCERNS. THE WELD !'AS LOCATED IN UT45TAN x - - THE SEAL WATER INJECTION FILTER ROC>>4.

UTOL VS1SSISZZ0018Q x - - THE UT45 INDICATION IS A GEOMETRIC REFLECTOR FROM THE WELD ROOT.

    • 3-SS-160-.451-30-SAM**

358340 3-CV-2163-8 C-F-1 PT V.S1 SSI SZZ0003Q x - - W.O. 931121035 TO PERFORM NDE* THIS PIPE TO ELBOW C5.21 UT45

  • VS1SSISZZ0014Q x WELD REPLACES

SUMMARY

  1. 368720, DUE TO UT45T x ALARA CONCERNS. THE WELD WAS LOCATED IN UT45TAN x - - THE SEAL WATER INJECTION FILTER ROC>>4.

UTOL VS1SSISZZ0018Q x **3-SS-160-.451-30-SAM**

3-CV-2160 ~REF. DWG. NO. B-712 359100 3-CV-2160-5 C-F-1 PT VS1SSISZZ0003Q x W~0.#931121035 TO PERFORM NOE. THE UT45 ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q - x - AND UT60 INDICATIONS ARE GEOMETRIC UT45T x REFLECTORS FROM THE WELD ROOT.

~ .. "'"'.., UT45TAN x UT60 x **3-SS-160-.451-30-SAM**

UTOL VS1SSISZZ0018Q x 359120 3-CV-2160-6 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NDE. THIS

-PIPE TO PIPE C5.21 UT45 VS1SSISZZ0014Q - x - EXAM REPLACED

SUMMARY

  1. 359000, DUE TO A
  • ..]--.~. UT45T x HIGH NUMBER OF EXAM LIMITATIONS PRESENT.

UT45TAN x THE UT45 AND UT60 INDICATIONS ARE UT60 - x - GEOMETRIC REFLECTORS FROM THE WELD ROOT.

UTOL VS1SSISZZ0018Q x **3-SS-160-.451-30-SAM**

359140 3-CV-2160-7 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NDE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q x - - EXAM REPLACED SuMMARY #359080, DUE TO A UT45T x SUPPORT INTERFERENCE.

UT45TAN x UT60 x **3-SS-160-.451-30-SAM**

UTOL VS1SSISZZ0018Q x - -

,,,:~:,:~~

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 35

' REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

' SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)

~CHEMICAL & VOLUME CONTROi.

CLASS 2 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO MET HOO PROCEDURE c MR **CALIBRATION BLOCK**

3-CV-2160 ~REF. DWG. NO. B-722 359840 3-CV-2160-42 C-F-1 PT VS1SSISZZQ003Q x W.O. 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q - x - WELD REPLACED

SUMMARY

  1. 359800, DUE TO UT45T x ALARA CONCERNS. THEWELD WAS LOCATED UT45TAN x . - INSIDE THE SEAL WATER INJECTION FILTER UTOL VS1SSISZZ0018Q x ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE WELD ROOT.
    • 3-SS-160-.451-30-SAM**

359860 3-CV-2160-43 C-F-1 PT VS1SSISZZ0003Q x - - W.O. 931121035 TO PERFORM NOE. THIS ELBOW TO PIPE CS.21 UT45 VS1SSISZZ0014Q - x - WELD REPLACED

SUMMARY

  1. 359820, DUE TO UT45T x ALARA CONCERNS. THE WELD WAS LOCATED UT45TAN x - - INSIDE THE SEAL WATER INJECTION-FILTER UTOL VS1SSl.SZZ0018Q x ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE COUNTERBORE.
    • 3-SS-160-.451-30-SAM**

359880 3-CV-2160-44 C-F-1 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NOE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q - x - WELD REPLACES

SUMMARY

  1. 360000, DUE TO UT45T x ALARA CONCERNS. THE WELD WAS LOCATED UT45TAN x - - INSIDE THE SEAL WATER INJECTION FILTER UTOL VS1SSISZZ0018Q x - - ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE COUNTERBORE.
    • 3-SS-160-.451-30-SAM**

2-CV-2170 ~REF i aw&. NO. B-81l 366000 2-CV-2170-1 C-F-1 PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NOE.

REDUCER TO ELBOW C5.30 2-CV-2167 CREF. DWG. NO: B-90>

366620 2-CV-2167-7 C-F-1 PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

PIPE TO REDUCER C5.30 2-CV-2164 CREF. DWG. NO. B-90) 368300 2-CV-2164-1 C-F-1 PT VS1SSISZZ0003Q X - - W.0.#931121035 TO PERFORM NOE.

REDUCER TO PIPE C5.30

, DATE: ,03/04/94 SALEM NUCLEAR POWER STATION UNIT PAGE: 36 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

~CHEMICAL SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS

& VOLUME CONTROL N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

2-CV-2158 CREF. DWG. NO. B-90) 369620 2*CV-2158-7 C-F-1 PT VS1SSISZZ0003Q X ~ - W.0.#931121035 TO PERFORM NOE.

PIPE TO REDUCER C5.30

~<.~~

, DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 37 R!iVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS AFETY INJECTION N 0 ASHE 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK**

4*SJ-2113 ~REF. DWG. NO. B-98l 383820 4-SJ-2113-3 C-F-1 PT VS1SSISZZ0003Q x - - w.o.#931121035 TO PERFORM NOE. THE UT45 FLANGE TO PIPE C5.21 UT45 VS1SSISZZ0014Q - x - INDICATION.IS A GEOMETRIC REFLECTOR FROM UT45T x THE WELD ROOT.

UT45TAN x UTO VS1SSISZZ0018Q x - - **4-SS-160-.533-28-SAM-R**

383940 4-SJ-2113-15 C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE.

ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q - x - LIMITATION: EXAM LIMITED TO 73X, DUE TO UT45T x THE PROXIMITY OF THE CONCRETE STRUCTURE.

UT45TAN x - " THE UT45 INDICATION IS A G~OMETRIC UTO VS1SSISZZ0018Q x - - INDICATION FROM THE WELD ROOT.

    • 4-SS-160-.533-28-SAM-R**

4-SJ-2113 ~REF. DWG. NO. B-100) 384200 4-SJ-2113-29 C-F-1 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NDE. THIS PIPE TO ELBOW C5.21 UT45 VS1SSISZZ0014Q - x- . WELD REPLACED

SUMMARY

  1. 384280, DUE TO UT45T x HANGER INTERFERENCE. THE UT45 UT45TAN x -. - INDICATIONS ARE GEOMETRIC REFLECTORS UTOL. VS1SSISZZ0018Q x FROM THE WELD ROOT.
    • 4-SS-160-.533-28-SAM-R**

384220 4-SJ-2113-30 C~F-1 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NDE. THIS ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q x WELD REPLACES

SUMMARY

  1. 384300, DUE TO UT45T x HANGER INTERFERENCE.

- UT45TAN x

~ .~~.. UTO VS1SSISZZ0018Q x **4-SS-160-.533-28-SAM-R**

384260 4-SJ-2113-32 C-F-1 PT VS1SSISZZ0003Q x - - W.0.#931121035 TO PERFORM NDE. THE UT45 PIPE TO FLANGE C5.21 UT45 VS1SSISZZ0014Q - x - INDICATION IS A GEOMETRIC REFLECTOR FROM UT45T x THE WELD ROOT.

UT45TAN x UTOL VS1SSISZZ0018Q x - - **4-SS-160-.533-28-SAM-R**

2-SJ-2126 CREF. DWG. NO; B-104) 386600 2-SJ-2126-6R C-F-1 PT VHSSSSPZZ0204Q x - - PSI BASELINE EXAMINATION WAS PERFORMED, REDUCER TO ORIFICE C5.30 DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930628119, ACT #5)

'DATE: 03/04/94 SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 38 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

~AFETY SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS INJECTION N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

2-SJ-2126 (REF. DWG. NO. B-104) 386620 2-SJ-2126-7R C~F-1 PT VHSSSSPZZ0204Q X - - PSI BASELINE EXAMINATION WAS PERFORMED, ORIFICE TO REDUCER C5.30 DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930628119, ACT #5) 2-SJ-2123 (REF. DWG. NO. B-105) 387100 2-SJ-2123-6R C-F-1 PT VHSSSSPZZ0204Q X - - PSI BASELINE EXAMINATION WAS PERFORMED, REDUCER TO ORIFICE C5.30 DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5) .

387120 2-SJ-2123-7R C-F~1 PT VHSSSSPZZ0204Q X - - PSI BASELINE EXAMINATION WAS PERFORMED, ORIFICE TO REDUCER C5.30 DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5)

' DATE: '03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 39 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS AUXILIARY FEEDWATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

AF1053 CREF. DWG. NO. AF-1,3A 01) 500145 14AFWG-002 F-C VT-3 S1SSISZZ0020Q x - - PRESERVICE PER 1EC-3226-01, W.0.#

GUIDE F3.10 930203~23, CJP# PS-93-004.

500150 14AFWG-003 F-C VT-3 S1SSISZZ0020Q x - - PRESERVICE PER 1EC-3226-01, W.0.#

GUIDE F3.10 930203123, CJP# PS-93-004.

AF1063 CREF. DWG. NO. AF-1-3A 01) 500390 13AFWA-046 D-A VT-3 S1SSISZZ0020Q X - - PRESERVICE PER 1EC-3226-01, W.0.#

ANCHOR 01 .20 930203123, CJP# PS-93-004.

AF1075 CREF. DWG. NO. AF-1-3A 01) 500630 12AFWG-002 F-C VT-3 S1SSISZZ0020Q X - - PRESERVICE PER 1EC-3226-01, W.0.#

GUIDE F3.10 930203123, CJP# PS-93-004.

AF1089 ~REF. DWG. NO. AF-1-3A 01l 5oono 11AFWS-050 F-C VT-3 S1SSISZZ0020Q x - - PRESERVICE PER 1EC-3226-01, W.0.#

SUPPORT F3.10 930203123, CJP# PS-93-004.

""'~ ..

500785 11AFWG-050A F-C VT-3 S1SSISZZ0020Q x - - PRESERVICE PER 1EC-3226-01, W.0.#

GUIDE F3.10 930203123, CJP# PS-93-004.

  • DATE: *03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 40 REVISION: 0 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS COMPONENT COOLING SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

CC1010 (REF. DWG. NO. CC-1-2A 02) 501255 1A-CCH*404 VT-3 THIS SUPPORT (SUM.# 501255) WAS DELETED HANGER PER EC-3255/PS-93-050/930610082.

CC1022 CREF. DWG. NO. CC-1-2A 02) 501355 1A-CCH-405 VT-3 .THIS SUPPORT (SUM.# 501355) WAS DELETED HANGER PER 1EC-3255/PS-93-050/930610082.

CC1051 CREF. DWG. NO. CC-1-2A 02) 501380 1A-CCH-402 VT-3 THIS SUPPORT (SUM.# 501380) WAS DELETED HANGER PER 1EC-3255/PS-93-050/930610082.

501390 1A*CCH-403 F-C VT-3 THIS SUPPORT (SUM.# 501390) WAS DELETED HANGER F3.10 PER 1EC-3255/PS-93-050/930610082.

CC1066 CREF. DWG. NO. CC-1-2A 02) 501425 1A-CCH-406 VT-3 THIS SUPPORT (SUM.# 501425) WAS DELETED HANGER PER 1EC-3255/PS-93-050/930610082.

501430 1A-CCH-082 VT-3 S1SSISZZ0020Q X - - PRESERVICE PER 1EC-3255-1, CJP# PS-93-50 HAN~ER & W.0.# 930610082.

' DATE: *03/04/94 SALEH NUCLEAR POWER STATION UNIT 1 PAGE: 41 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS CONTAINMENT SPRAY SYSTEM N 0 ASHE 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SJ1094 CREF. DWG. NO. CS-1-1A 01) 502910 1A-CSS-158 F-C VT-3 S1SSISZZ0020Q X " - W.0.#931121035 TO PERFORM NOE. RE-EXAM SUPPORT F3.10 FROM 1RF0#10.

' DATE: .03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 42 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS CHEMICAL AND VOLUME CONTROL SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOO . PROCEDURE c M R **CALIBRATION BLOCK**

CV1161 ~REF. DIJG. NO. CV-1-2B 02l 503235 1A-CVCS-383 F-C VT-3 S1SSISZZ002QQ - - x IJ.0.#931121035 TO PERFORM NOE.

SUPPORT F3.10 RESCHEDULED FROM 1RF0#10. NEED TO REMOVE CONCRETE BLOCK FOR EXAM. THE INSPECTION FOUND BORON ON THE SUPPORT.

IJ.O. #931027158 CLEANED THE BORON OFF.

A RE-EXAM IJAS SCHED. FOR S1RF0#12 (ACCESSIBILITY PROBLEMS).

RC1077 ~REF. DIJG. NO. CV-1-4B 01l 503945 1C-CVCH-326 VT-3 S1SSISZZ0020Q x - - THIS SUPPORT IJAS MODIFIED PER HANGER 1EC-3167/PS-92-40/920805116.

503970 1C-CVCG-276 VT-3 S1SSISZZ0020Q X - - .THIS SUPPORT IJAS MODIFIED PER GUIDE 1EC-3167/PS-92-40/920805116.

' DATE: '03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 43 REVISION: 0 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS

.MAIN STEAM SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

MS1003 CREF. DWG. NO. MS-1-2 04) 504315 1P-MS-VS006 F-C VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NDE. RE-EXAM 1 LUG F3.10 FROM 1RF0#10.

MS1112 CREF. DWG. NO~ MS-1-2 04) 504535 1P-MSH-122T VT-3/4 S1SSISZZ0020Q x - - PRE-SERVICE INSPECTION WAS PERFORMED HANGER UNDER W.O. #931121035 & 931002088, DUE TO THE DISASSEMBLY OF THE '2MS167 VALVE ACTUATOR. ADDITIONAL STEEL PLATE AND GOUGE MARKS IN THE SUPPORT CHANNELS WERE FOUND TO BE ACCEPTABLE PER NON DR.

MS1269 CREF. DWG. NO. MS-1-2 04) 504710 1P-MSH-124T VT-3/4 S1SSISZZ0020Q x - - PRE-SERVICE INSPECTION WAS PERFORMED HANGER UNDER W.O. #931121035 &931002089, DUE TO THE DISASSEMBLY OF THE 14MS167 VALVE ACTUATOR. NO MODIFICATIONS WERE PERFORMED ON THIS HANGER. CSEE NON DR, FOR ADDITIONAL INFORMATION)

, DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 44 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI CIJ4PLETE CIJ4PONENTS PRESSURIZING SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

RC1276 (REF. DWG. NO. RC-1-1A 01>

505065 1C-PSH-001 F-C VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED HANGER F3.10 PER NRC BULLETIN 88-11.

505066 R-239776-1 A-E VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11 PER NRC BULLETIN 88-11.

505067 R-239776-2 A-E VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED.

NB88-11 PER NRC BULLETIN 88-1.1.

505068 R-239776-3 A-E VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO .PERFORM NOE. EXAMINED NB88-11 PER NRC BULLETIN 88-11.

05069 R-239776-4 A-E VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11 PER NRC BULLETIN 88-11.

505070 1C-PSH-002 F-C VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED HANGER F3.10 PER NRC BULLETIN 88-11.

505071 R-239776-5 A-E VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11 PER NRC BULLETIN 88-11.

505072 R-239776-6 A-E VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11 P~R NRC BULLETIN 88-11.

505073 R-239776-7 A-E VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE. EXAMINED NB88-11 PER NRC BULLETIN 88-11.

'DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 45 REVISION: 0 OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0)

~PRESSURIZING SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

RC1276 (REF. DWG. NO. RC-1-1A 01>

505075 1C-PSH*003 F*C VT-3 S1SSISZZ0020Q X *

  • W.0.#931121035 TO PERFORM NOE. EXAMINED HANGER F3.10 PER NRC BULLETIN 88*11.

'DATE: 03/04/94 SALEM NUCLEAR PO\JER STATION UNIT 1 PAGE: 46 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS PRESSURIZER RELIEF SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

RC1287 (REF. DWG. NO. RC-1-2B 01) 505300 1C-PRH-177 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3168/PS-92-41/920805117.

' DATE: '03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 47 REVISION: 0 . CXJTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND CXJTAGE C93RF)

CLASS 2 SECTION XI COMPLETE COMPONENTS

.RESIDUAL HEAT REMOVAL SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

RH1013 CREF. DWG. NO. RH-1-1A 02) 505755 1A-RHRA-PS30 F-C VT-3 S1SSISZZ0020Q X - - W.0.#931121035 TO PERFORM NOE.

ANCHOR F3.10

' DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 48 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 1 SECTION XI COMPLETE COMPONENTS SAFETY INJECTION SYSTEM N 0 ASME O G T SEC *. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

RC1023 CREF. DWG. NO. RH*1-3F 01) 506195 1C*11SIS*133 F-C VT*3 S1SSISZZ0020Q X -

  • W.0.#931121035 TO PERFORM NOE. RE*EXAM SUPPORT F3.10 FROM 1RF0#10.

' DATE: ,D3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 49 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOO PROCEDURE C M R **CALIBRATION BLOCK**

SW1136 CREF. DWG. NO. SW-1-7K 01>

508920 1MSWPG-049A D-B VT-3 S1SSISZZ002QQ X - - THIS GUIDE WAS DISSASSEMBLED AND A NEW GUIDE D2.20 WELD WAS ADDED TO FACILITATE THE REMOVAL OF PIPE SPOOL RD-1-SW-75, .UNDER CJP

  1. S-92-332 AND W.O. #920512075 *.

SW1169 CREF. DWG. NO. SW-1-3B 01>

508990 A1-SWG-364 GUIDE VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/9304220!3.

508995 A1-SWA-354 VT-3. S1SSISZZ0020Q x - - THIS SUPPORT WAS MOOIFIED PER ANCHOR 1EC-3149/PS-93-030/930422073.

509000 A1-SWG-366 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509005 A1-SWG-367 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED*PER GUIDE . 1EC-3149/PS-93-030/930422073.

SW1176 CREF. DWG. NO. SW-1-38 01) 509010 A1-SWA-345 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER ANCHOR 1EC-3149/PS-93-030/930422073.

509015 A1-SWG-344 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509020 A1-SWG-316 VT*3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

I DATE: g3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: so REVISION: 0 OUTAGE ISi EXAMINATION RESULTS_(S1RF0#11, REV.0)"

~SERVICE SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N O ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1176 (REF. DWG. NO. SW-1-3B 01) 509025 A1*SWA-315 D-B VT-3 S1SSISZZ0020Q x THIS SUPPORT WAS MODIFIED PER ANCHOR D2.20 1EC-3149/PS-93-030/930422073.

509030 A1-SWH-314 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3149/PS*93-030/930422073.

509035 A1-SWG-313 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509040 A1-SWG-324 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

09045 A1*SWH-323 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3149/PS-93*030/930422073.

509050 A1-SWA-WS08 D-B S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER ANCHOR D2.20 1EC-3149/PS-93-030/930422073.

SW1181 CREF. DWG. NO. SW-1-3B 01) 509055 A1-SWG-378 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS*93-030/930422073.

509060 A1-SWA*358 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER ANCHOR 1EC-3149/PS-93-030/930422073.

509065 A1-SWG-377 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

'DATE: 93/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 51 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1181 CREF. DWG. NO. SW-1-3B 012 509070 A1-SWG-376 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509075 A1-SWG-348 VT-3 THIS SUPPORT (SUM.# 509075) WAS DELETED GUIDE PER 1EC-3149/PS-93-030/930422073.

509080 A1-SWG-347 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509085 A1-SWG-346 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

SW1185 CREF. DWG. NO. SW-1-3B 012 509090 A1-SWS-369 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

509095 A1-SWG-368 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509100 A1-SWA-356 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER ANCHOR 1EC-3149/PS-93-030/930422073.

509105 A1-SWG-370 vr-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

SW1191 CREF. DWG. NO. SW-1-1B 022 509110 P1-SWA-WS12 D-B VT-3 S1SSISZZ002QQ X - - PRESERVICE PER ANCHOR D2.20 1EC-3150-1/PS-93-006/930615162.

'DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 52 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~SERVICE WATER SYSTEM CLASS 3 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1197 CREF. DWG. NO. SW-1-1A 02) 509160 C-13SWH-2 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3054-2/PS-93-021/920115113.

509165 C-13SWG-3C VT-3 S1SSISZZ0020Q X - - PRESERVICE (NO MOO.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

SW1220 CREF. DWG. NO. SW-1-1A 02) 509270 C-12SWH-1 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3054-2/PS-93-021/920115113.

509275 C-11SWG-3B VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

.,,.,,., C-11SWG-4B GUIDE VT-3 THIS SUPPORT (SUM.# 509280) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.

509285 C-11SWG-5B VT-3 S1SSISZZ0020Q X - - PRESERVICE (NO MOO.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

509290 C-12SWG-3A VT-3 S1SSISZZ0020Q X - - PRESERVICE (NO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

509295 C-12SWG-4 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS.MODIFIED PER ANCHOR 1EC-3054-2/PS-93-021/920115113.

509300 C-11SWG-9B VT-3 THIS SUPPORT (SUM.# 509300) WAS DELETED GUIDE PER 1EC-3054-2/PS-93-021/920115113.

' DATE: *03/04/94 SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 53 R~VISION: 0 ClJTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND ClJTAGE (93RF)

CLASS 3 SECTION XI CQ4PLETE COMPONENTS

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1220 CREF. DWG. NO. SW-1-1A 02>

509305 C-11SIJG-11A VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

509310 C-11SWG-6 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

509315 C-12SWG-7A VT-3 S1SSISZZ0020Q X - - PRESERVICE (NO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

509320 C-12SWH-9 HANGER VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

SW1220 CREF. DWG. NO. SW-1-5B 02>

  • 5.09345 C-12SWG-12 F-C VT-3 S1SSISZZ0020Q x . - THIS SUPPORT WAS MODIFIED PER GUIDE F3.10 1EC*3054-2/PS*93*021/920115113.

SW1238 (REF. DWG. NO. SW-1-1A 02>

509370 C-11SWH-1 VT-3 S1SSISZZ0020Q X * - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3054*2/PS-93-021/920115113.

509375 C-11SWG*3A VT-3 S1SSISZZ0020Q X * - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

509380 C-11SWG-4A VT-3 THIS SUPPORT (SUM.# 501390) WAS DELETED GUIDE PER 1EC-3054-2/PS-93-021/920115113.

509385 C-11SWG-5A VT-3 S1SSISZZ0020Q X - - PRESERVICE (NO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

'DATE: 03/04/94 SALEM NUCLEAR P~R STATION UNIT 1 . PAGE: 54 REVISION: 0 OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0)

~SERVICE SECOND INTERVAL, SECOND PERICX>, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHCX> PROCEDURE C M R **CALIBRATION BLOCK**

SW1238 CREF. DWG. NO. SW-1-1A 02) 509395 C-11SWG-8A D-B VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MCX>IFIED PER GUIDE D2 1EC-3054-2/PS-93-021/920115113.

509400 C-11SWG-9A VT-3 S1SSISZZ0020Q X - - PRESERVICE (NO Mex>.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

509405 C-11SWH-10 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3054-2/PS-93-021/920115113.

SW1238 CREF. DWG. NO. SW-1-5A 02) 509425 C-11SWG-13 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

SW1365 CREF. DWG. NO. SW-1-3B 01) 509525 A1-SWG-343 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509530 A1-SWG-325 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

SW1366 CREF. DWG. NO. SW-1-3B 01) 509535 A1-SWG-326 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509540 A1-SWG-327 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

' DATE: fJ3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 55 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1366 (REF. DWG. NO. SW-1-3B 01) 509545 A1-SWG-304 VT-3 S1SSISZZ0020Q x - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509550 1A-SWA-303A D-B VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE D2.20 1EC-3149/PS-93-030/930422073.

509555 A1*SWG*303 VT-3 S1SSISZZ0020Q X *

  • THIS SUPPORT WAS MODIFIED PER GUIDE 1EC*3149/PS*93*030/930422073.

509560 A1-SWH*302 HANGER VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073 *

  • 509565 A1*SWG*301 GUIDE VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.

509570 A1*SWG*300 GUIDE VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.

509575 A1*SWG-318 VT-3 S1SSISZZ0020Q X -

  • THIS SUPPORT WAS MODIFIED PER GUIDE 1EC*3149/PS*93*030/930422073.

509580 A1-SWH*317 VT-3 S1SSISZZ0020Q X *

  • THIS SUPPORT WAS MODIFIED PER HANGER 1EC*3149/PS*93-030/930422073.

509585 A1-SWA*WS05 D-B VT*3 S1SSISZZ0020Q X *

  • THIS SUPPORT WAS MODIFIED PER ANCHOR D2.20 1EC*3149/PS-93*030/930422073.

'DATE: G3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 56 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

~SERVICE WATER SYSTEM CLASS 3 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1373 CREF. DWG. NO. SW-1-3B 01) 509590 A1-SWG-328 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509595 A1-SWG-329 VT-3 THIS SUPPORT (SUM.# 509595) WAS DELETED GUIDE PER 1EC-3149/PS-93-030/930422073.

SW1377 CREF. DWG. NO. SW-1-3B 01) 509600 A1-SWS-351 VT-3 THIS SUPPORT (SUM.# 509600) WAS DELETED SUPPORT PER 1EC-3149/PS-93-030/930422073.

509605 A1-SWG-352 VT-3 THIS SUPPORT (SUM.# 509605) WAS DELETED GUIDE PER 1EC-3149/PS-93-030/930422073.

  • SW1384 509635 C-14SWH-1 HANGER

~REF. DWG. NO. SW-1-1A 02)

VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

509640 C-13SWG-3D VT-3 S1SSISZZ0020Q x - - PRESERVICE (NO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

SW1496 CREF. DWG. NO. SW-1-9H 01) 5o98o5 1A-SWS-091 VT-3 S1SSISZZ0020Q x - - THIS SUPPORTS VERTICAL MEMBERS WERE SUPPORT REPLACED UNDER CJP #S-93-141 AND W.O.

  1. 920530148.

SW1498 ~REF. DWG. NO. SW-1-3B 01l 509815 A1-SWS-340 VT-3 S1SSISZZ0020Q x - -

  • THIS SUPPORT WAS MODIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

' D~TE: '03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 57 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

~SERVICE SECOND INTERVAL, SECOND PERia>, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METH<X> PROCEDURE C M R **CALIBRATION BLOCK**

SW1541 CREF. DWG. NO. SW-1-3B 01) 509840 A1-SWG-349 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509845 A1-SWG-330 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE '1EC-3149/PS-93-030/930422073.

509850 A1-SWS-350 VT-3 S1SSISZZ00200 X - - THIS SUPPORT WAS MOOIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

509855 A1-SWG-382 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS Ma>IFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509860 A1-SWA-357 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER ANCHOR 1EC-3149/PS-93-030/930422073.

509865 A1-SWG-385 VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

  • SW1542 ~REF. DWG. NO. SW-1-38 01l 509870 A1-SWS-332 VT-3 S1SSISZZ0020Q x - ~

THIS SUPPORT WAS M<X>IFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

509875 A1-SWG-312 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509880 A1-SWA-311 D-B VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER ANCHOR D2.20 1EC-3149/PS-93-030/930422073.

'DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 58 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

~SERVICE SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1542 CREF. DWG. NO. SW-1-3B 01) 509885 A1-SWG-310 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509890 A1-SWG-309 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

SW1545 CREF. DWG. NO. SW-1-3B 01) 509895 A1-SWG-341 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509900 A1-SWG-342 VT-3

  • S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.
  • SW1546 CREF. DWG. NO. SW-1-3B 01) 509905 A1-SWS-331 SUPPORT VT-3 THIS SUPPORT (SUM.# 509905) WAS DELETED PER 1EC-3149/PS-93-030/930422073.

509910 A1-SWS-339 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

509915 A1-SWG-375 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509920 A1-SWS-374 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

509925 A1-SWA-355 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER ANCHOR 1EC-3149/PS-93-030/930422073.

' DATE: *03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 59 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0)

~SERVICE SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS WATER SYSTEM N 0 ASME 0 G T SEC. XI R E .H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1546 CREF. DWG. NO. SW-1-3B 01) 509930 A1-SWG-384 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

SW1550 CREF. DWG. NO. SW-1-3B 01) 509935 A1-SWA-353 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MOOIFIED PER ANCHOR 1EC-3149/PS-93-030/930422073.

509940 A1-SWG-359 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE- 1EC-3149/PS-93-030/930422073.

509945 A1-SWG-360 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509950 A1-SWG-361 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509955 A1-SWS-334 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

509960 A1-SWG-333 VT*3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509965 A1-SWG-383 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

(REF. DWG. NO. SW-1-3B 01) 509966 A1-SWG-2433 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073. ANCHOR A1-SWA-383 WAS REPLACED WITH GUIDE A1-SWG-2433.

DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 60

,REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION - ITEM NO METHOO PROCEDURE . C M R **CALIBRATION BLOCK**

SW1551 CREF. DWG. NO. SW-1-3B 01) 509970 A1-SWG-322 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MOOIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

509975 A1-SWH-321 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3149/PS-93-030/930422073.

509980 A1-SWA-WS07 D-B VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED ~ER ANCHOR D2.20 1EC-3149/PS-93-030/930422073.

SW1556 {REF. DWG. NO. SW-1-3B 01) 509985 A1-SWS-338 VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MOOIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

  • 509990 A1-SWS-336 VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

509995 A1-SWS-335 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER SUPPORT 1EC-3149/PS-93-030/930422073.

510000 A1-SWG-337 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

SW1557 (REF. DWG. NO. SW-1-3B 01) 510005 A1-SWG-308 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

510010 1A-SWA-307A D-B VT*3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE D2.20 1EC-3149/PS-93-030/930422073.

, DATE:, D3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 61 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

. CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H sutl4ARY EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1557 CREF. DWG. NO. SW-1-3B 01) 510015 A1-SWG-307 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

510020 A1-SWG-306 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

510025 A1-SWG-305 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

510030 A1-SWA-WS06 D-B VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER ANCHOR D2.20 1EC-3149/PS-93-030/930422073.

SW1619 CREF. DWG. NO. SW-1-1A 02) 510135 C-14SWH-1 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3054-2/PS-93-021/920115113.

510225 C-13SWG-3B VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

~ *-~..

SW1640 'REF. DWG. NO. SW-1-1A 02l 510250 C-13SWH-1 VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER HANGER .---*:*"\ 1EC-3054-2/PS-93-021/920115113.

....~

510255 C-13SWG-3A VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

SW1664 'REF. DWG. NO. SW-1-1A 02l 510395 C-12SWH-2 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT- WAS MODIFIED PER HANGER 1EC-3054*2/PS-93*021/920115113.

'DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 62 REVISION: 0 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF)

, CLASS 3 SECTION XI COMPLETE COMPONENTS SERVICE WATER SYSTEM N O ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1664 CREF. DWG. NO. SW-1-1A 02>

510400 C-11SWG-3D VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

510405 C-11SWG-40 VT-3 THIS SUPPORT (SUM.# 501405) WAS DELETED GUIDE PER 1EC-3054-2/PS-93-021/920115113.

510410 C-11SWG-5D VT-3 S1SSISZZ002QQ X - - PRESERVICE (NO MOD.) PER .

GUIDE 1EC-3054-2/PS-93-021/920115113.

510415 C-12SWG-38 VT-3 S1SSISZZ002QQ X - - _pRESERVICE (NO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

510420 C-12SWG-5 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER ANCHOR 1EC-3054-2/PS-93-021/920115113.

510425 C-11SWG-90 VT-3 THIS SUPPORT (SUM.# 510425) WAS D.ELETED GUIDE PER 1EC-3054-2/PS-93-021/920115113.

~ **~*

510430 C-11SWG-11C VT-3 S1SSISZZ002QQ x - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

510433 C-12SWG-6A VT-3 S1SSISZZ0020Q X - - PRESERVICE (NO MOO.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

510435 C-12SWG-58 VT-3 S1SSISZZ002QQ X - - PRESERVICE (NO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

  • . ~;;,,~;;~.
  • 1

'DATE: 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 63 REVISION: 0 OUTAGE ISi EXAMINATION RESULTS CS1RF.0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF)

~SERVICE .WATER SYSTEM

. CLASS 3 SECTION XI COMPLETE COMPONENTS N O ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1664 CREF. DWG. NO. SW-1-1A 022 510440 C-12SWG-7B VT-3 S1SSISZZ002QQ X - - PRESERVICE CNO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

510445 C-12SWG-8 VT-3 S1SSISZZ002QQ X - - PRESERVICE CNO MOO.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

510450 C-12SWG-10 VT-3 S1SSISZZ002QQ X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

510455 C-12SWH-11 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3054*2/PS-93-021/920115113._

SW1664 CREF. DWG. NO. SW-1-5B 022 510485 C-12SWG-16 F-C VT-3 S1SSISZZ0020Q X -

  • THIS SUPPORT WAS MODIFIED PER GUIDE F3.10 1EC-3054*2/PS*93*021/920115113.

SW1684 CREF. DWG. NO. SW-1-5A 02) 510520 C-11SWG-17 F-C VT-3 S1SSISZZ002QQ X *

  • THIS SUPPORT WAS MODIFIED PER GUIDE F3.10 1EC*3054*2/PS*93*021/920115113.

SW1684 CREF. DWG. NO. SW-1-1A 02>

510555 C-11SWH-2 VT-3 S1SSISZZ002QQ X *

  • THIS SUPPORT WAS MOOIFIED PER HANGER 1EC*3054*2/PS*93*021/920115113.

510560 C-11SWG-3C VT-3 S1SSISZZ002QQ X *

  • THIS SUPPORT WAS MODIFIED PER GUIDE 1EC*3054*2/PS*93-021/920115113.

DATE: _03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 64

'RE'flSI°": 0 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0)

SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE_ (93RF)

CLASS 3 SECTION XI COMPLETE COMPONENTS

_.SERVICE WATER SYSTEM N 0 ASME 0 G T SEC. XI R E H

SUMMARY

EXAMINATION AREA_ CATGY EXAM E 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE C M R **CALIBRATION BLOCK**

SW1684 CREF. DWG. NO. SW-1-1A 02>

510565 C-11SWG-4C VT-3 THIS SUPPORT (SUM.# 510565) WAS DELETED GUIDE PER 1EC-3054-2/PS-93-021/920115113.

510570 C-11SWG-5C VT-3 S1SSl!lZZ0020Q X - - PRESERVICE (NO MOD.) PER GUIDE 1EC-3054-2/PS-93-021/920115113.

U0575 C-11SWG-7 VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER ANCHOR 1EC-3054-2/PS-93-021/920115113.

I 510580 C-11SWG-8B VT-3 S1SSISZZ0020Q x - - PRESERVICE (NO MOD.) PER -,

GUIDE 1EC-3054-2/PS-93-021/920115113.

510585 *C-11SWG-9C VT-3 THIS SUPPORT (SUM.# 501585) WAS DELETED GUIDE PER 1EC-3054-2/PS-93-021/920115113.

510590 C-11SWG-11B VT-3 S1 SS I SZZ0020Q - x - - THIS.SUPPORT WAS MODIFIED PER GUIDE 1EC-3054-2/PS-93-021/920115113.

~ .-~~

510595 C-11SWH-12 VT-3 S1SSISZZ0020Q x - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3054-2/PS-93-021/920115113.

SW1986 CREF. DWG. NO.- sw-1-3B 01>

510785 A1-SWG-320 - <t:_:, VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER GUIDE 1EC-3149/PS-93-030/930422073.

510790 A1-SWH-319 VT-3 S1SSISZZ0020Q X - - THIS SUPPORT WAS MODIFIED PER HANGER 1EC-3149/PS-93-030/930422073.

Index of NI8-2 and NR-1 Forms I. NI8-2 Forms Component Work Order Brief Description 1CVE43 920514012 Replaced charging pump oil cooler 11C85 Replaced disk & nozzle 18J32 Replaced disk 1PR3 Installed modified f lexi-disc 1PR4 Installed modified flexi-disc 1PR5 Installed modified flexi-disc 2PR3 (spare) Installed modified flexi-disc 1CCE5 Modified head with manway II. NR-1 Forms Code Job l Brief Description 892-379 Replaced studs, nuts and bonnets in kind 892-392 Replace valve bolting 893-008 Replaced valve bolting 893-036 Replaced stem and valve bolting 893-082 Repaired vane holes and taper pins 893-108 Replaced bolting with upgraded material 893-114 Replaced valve disc 893-124 Replaced valve disc 893-149 Replaced modified miniflow orifice 893-150 Replaced modified miniflow orifice 893-171 Replaced valve stem, bolting and weld repair on leak-off 893-181 Replaced valve with valve of new design 893-182 Replaced valve with valve of new design 893-183 Replaced valve with valve of new design 893-184 Replaced valve with valve of new design 893-190 Replaced blind flange on fuel transfer canal in kind 893-192 Replaced stem 893-193 Replaced stem 893-207 Replaced bonnet stud 893-212 Weld repairs on valve body 893-218 Replaced snubber serial # 330 with snubber serial # 23687 893-220 Replaced transition tubes assemblies 893-221 Replace bonnet bolting 893-225 Replaced flange and spool, elbow and bolting in kind 893-226 Replaced plug and assembly in kind 893-227 Replaced snubber serial # 25784 with snubber serial # 27164 893-228 Replaced snubber serial # 445 with snubber serial # 27629

893-229 Replaced snubber serial # 11 with snubber serial # 3903 893-233 Re-weld support after inspection and re-assembly of valve 893-238 Replaced flange to valve bolting 893-240 Replaced valve bolting 893-241 Replaced bolting and nuts in kind 893-249 Replace (16) studs in kind 893-250 Replaced valve bolting 893-254 Replaced pressurizer manway cover and bolting 893-260 Replaced pressurizer relief tank rupture disc flanges 893-262 Replace (1) bolt in kind on #14 Steam Genera-tor Primary Manway Cold Leg 893-266 Replace valve disc 893-270 Replace valve with spare valve 893-276 Replace (4) cap screws and valve disc 893-277 Replaced bolting 893-278 Installed new stop pin for air lock equaliz-ing ball valve 893-279 Replaced valve in kind 893-287 Replaced snubber serial # 25784 with snubber serial # 27164 PS92-040 Modified existing support PS92-041 Modified pipe support PS93-012 Replaced stem assembly and bolting with upgraded material and replaced valve bolting PS93-045 Replaced GB4 valve internals PS93-053 Replaced valve bolting and valve internals PS93-054 Replaced valve bolting and valve internal PS93-052 Modified pressurizer piping supports PS93-055 Modified pressurizer relief tank small bore piping PS93-070 Added break flanges to pipe spool piece 1CA2310 PS93-073 Removal of boric acid blender PS93-074 Replace valve internals, bolting and nuts PS93-075 Install new condensate chambers for #11 main steam header PS93-076 Install new condensate chambers for #12 main steam header PS93-077 Install new condensate chambers for #13 main steam header PS93-078 Install new condensate chambers for #14 main steam header PS93-079 Install supports for condensate pots on #11 main steam header PS93-080 Install supports for condensate pots on #12 main steam header PS93-081 Install supports for condensate pots on #13 main steam header PS93-082 Install supports for condensate pots on #14 main steam header PS93-083 Modify pipe support C-RVVS-5 PS93-088 Replace 2 nuts on pipe support #P-CTAG-660

  • FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1. Owner Public Service Electric & Gas Co. Date _ _s_e...:p:...t_e_m_b_e_r_2_1_,_1_9_9_3_ _ _ _ __

Name End of Buttonwood Rd.Hancocks Bridge,NJ Sheet _ _ 1 _ _ of _ _1_ _ _ _ _ _ _ _ _ _ ~

Addr-Unit _ _l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

2. Plant _ _s_a_l_e_m__ N_u_c_l_e_a_r--.,.G.,..e_n_e_r_a_t_i_*_n..;:g_s_t_a_t_i_o_n__

Name End of Buttonwood Rd.,Hancocks Bridge,NJ WO# 920514012 CJP # S91-324 Repair Organlutlon P.O. No., Job No., etc.

Type Code Symbol Stamp _ _NR _ _ _ _ _ _ _ __

Authorization No. _ _ _ _ _3_6_ _ _ _ _ _ __

End of Buttonwood Rd.,Hancocks Bridge,NJ Expir111tion Date 10/3/94 Add,_

4. Identification of System_C_h_e_m_i_c_a_l __v_o_l_um __e_C_o_n_t_r_o_l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
5. (a) Applicable Construction Code N/A 19 _ _ Edition, N/A Addenda,_~N.../""'A"'-_ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or ReplacelT'!"" cs 19 83 Summer 83
6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replacad, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol 1CVE43 ITT N/A N/A N/A N/A ~eplaced No Standard 1CVE43 ITT 5-142-05 N/A N/A N/A ~eplacemenlt No Standard 014042

\

7. Description of Work _ _R_e_p_l_a_c_e_d_C_h_a_r..;:g:...i_n_g"--_P_u_m-'.P.___O_i_l_C_o_o_l_e_r_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

B. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0

  • Other QJ Pressure NOP psi Test Temp.NOT °F
  • System Inservice Test NOTE: Supplemental. sheets in form of lists, sketches, or drawings may be used, provided (1 l size is.a% in ..x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017

FORM NIS-2 (Back)

Applicable Manufnctur*r's Data Raportl to be *ttached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacemen~nforms to the rules of the ASME Code,Section XI. rep*ir or replacement

  • Certificate of Authorization No. _ _..:3:c6=-------------Expiration Date ___l.._0"'4-/_3.._/

Signed d'~ ~,,J'

  • Owner or Owner's OesignH,Title CERTIFICATE OF INSERVICE INSPECTION

.....9:..;;4.__ _ _ _ _ _ __

Date _~Z.-c___...::'2-==...7'-c----* 19 7 j>

I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Arkwright Mutual Insurance Co. of

_MA

________________________________ have inspected the components described in this Owner's Report during the period _ _ _ _7..._._-_' ...*---='2-=----to, t _ ___:tb~_-__.fc.-...i'L-_____, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Factory Mutual Engr. Assn.

~£,~ Commm~"' ~f,~Z.~P*****~.*******-'""

Date~_ _..__./():............-/-'-~---ufi 3

FORM NIS-2 OWNER'S..REPORT FOR REPAJRS OR REPLACEMENTS As Required by the Pro'!_isions of the ASME Code Section XI 1* Owner Public Service Electric i; Gas Date Nov. 2, 1993 N*m* *--- ;.!*:.w, .....

End __ of Alloway Creek ~e~k A~. ~~n~ocks' Sheet One of Cai;:

Addr- Bridge' NJ 08038 . -- . -- . ***-*---*--* ..

2. Plant ___s_a_l_e_m _ _ _ _ _ _ _ _ _ _ _ _ _ __ One Unit N*m* .. PO# P1-426636 End of Alloway Creek Ne~k Ad. Hancocks Crane-Aloyco Inc. NA Travel# 366 Addr-sr i dge, NJ A*P*lr Orgenlzetlon P.O. No., Job No.,.~-**

08038

3. Work Perfonned by_... r ...n...c......._ _ __

c_r_a....._n...e=--...:.A...l....,o...,y._.c_p.__... Type Code Symbol Stamp VA NA N*m* Authorization No.SO' 138, 261 , 262 24, 63 104 N. Chicago St; Joliet, IL 60434 Expiration Date. Ju 1 ~ 2 1 1996

  • Feb 17 ,
4. ldentiflcationofSVstem

~----*--

Add,_

Ct.Jnteinrrient Soray

  • --*-**---*-. *---* .c~t1CSS)
5. (al Applicable Construction Code N/ A 19 N/ A Edition,_.;.;N:.../-'A...__ _ _ Addenda, NI A Code Case lb) Applicable Edition of Section XI Utilized for Repain or Replacements 19 83 Summer
  • 83 Addenda

~ *t.;' .; .. *..

6. ldentiflcetion of Components Repaired or Replaced and Replacement Components

-* .. .. .. National Repaired; - Smmped Name of Name of . Manufacturer Board Other Year Replaced; ** **-eves Component Manufacturer Serial No. No. Identification Built or Replacement or Nol 11CSS Crosby 84616-3!:

Disk Valve -on.an PJ/4 N/A N/A Heolacerl Nn Crosby 088027-Nozzle Valve 16-0024 NIA N/A

7. Description of Work Replaced Disk & Nozzle, Lapped E; Set Tested
8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other~ Pressure 260 psi Test Temp. Amb i ent°F NOTE: Supplemental sheets in form of lists. sketches. or drawings may be used. provided (1) size is BY. in. x 11 in., (2) Informa-tion in items 1 through 6 on this report is included on each sheet. and (3) each sheet is numbered and the number of sheets is recorded et the top of this form.

(12/82) This Form (E000301 may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017

  • . *.~-*- ~."

FORM NIS-2 (Back)

9. Remarks_~------------------------------------------------------------------------------------

Applicable Manuf*cturer'1 Cata Reparu to b* *ttmchmd

..1. l\

CERTIFICATE OF COMPLIANCE We certify that the statemenu made in the report are correct and this Rep 1 acemencOnforms to the rules of the ASME Code,Section XI. - ** rmpair or r*piacemant Type Code Symbol Stamp ____________________________________________________________________

VA NR .,_,._._,_,,_

50,138,261 1 262 24,62 VA NA _____ _

Feb. 17, 1994 Certificate of Authorization No. --------------------------Expiration Data j U 1 Y 2 1 19 9 6 Signed_...,,.c{_,,LL _____&,~<<..k"-=*~',-J-/_..,16&,,'-=-~-... =---~=*

m0<9';,J...,- * --~..._____ oate_N_o_v_e_m_b_e_r_Z........,1_,,p

..... _ _ , 19 93 Own*r or Own*r'* Oulgnee, Tltla '

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vassel Inspectors and the :tilt*

orProvinceof New Jersey andemployedby Arkwright Mutyal Iosµrance .-? of

._.;..N.._o;;;;,,;..r.-w;.;.,.:;;;o;..;:o::o...::d,_._......:.M..:..A;..;:_______________~..,,......------r--------------~h11V9 inspected tbe components dea:rlbed in this Owner's Report during the period_.,_0--...~---....,..,...-----to I I - Cf*- 9 .::J and stata that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report In accordance with the requirements of the ASME Code,Section XI. __ .

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his ~l~er shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Factory Mut.ua l Engr. A:ssn.

~~ I nspector'1 Signature Commissions~ 20 S ~I.) I Gs.}~ iff-I' 7f J N*tional Bo*rd, St*t*, Province, and Endonemanu j

Date_l___,i/__2_'f _____19 7 _::)

  • 4 FORM NIS-2 OWNER'S REPORT FOR REPAJRS OR REPLACEMENTS As Required by the Pro~isions o_f the ASME Code Section XI
1. Owner Fu b l i c Ser v i c e El e ctr i c i;; Gas Date Nov. 2 1993 Name End of Alloway Creek Neck Ad. Han cocks Sheet One of _ _""O'"'"n.._e""-"'"--------

Addrea Bridge, NJ 08038

2. Plant _ _S_a_l;;;..;;;e...;.m~---------------- Unit One Name PD# P 1-426.636 End of Alloway Creek Neck Ad. Hancocks Crane-Aloyco Inc. NA Travel# 363 Address Bridge, NJ 08038 Repair Organization P.O. No., Job No., etc.

Crane-Aloyco

3. Work Perfonned b y - - - - - - - - - , . , . - - - - - * - - - - - Inc Type Code Symbol Stamp _ VA_ _ _ _ _ _ _ NA _ __

Name Authorization No.50' 138' 261 '262 24, 63 1_0_4__N_.__ __S_t....,...,._J__.;:;o..;;cl::..i::..*.:::e....:t::..,,__=I-=L=---=6:..::0,._4~3 4 C_h_i_c_a_,g=-o Expiration Date Jul Y 2 , 1 9 9 6 Feb

  • 17, 1994 Address
4. Identification of System Sa f e t Y I n j ect i on
5. (al Applicable Construction Code N/ A 1~/ A Edition,_N...;./_A_ _ _ _ Addenda, N/A Code Casa (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83 Summer 83 Addenda
6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol 1SJ32 Crosby "N95137-Disc ValvF! 0035 9eplaced No N/A NIA NIA I
7. Description of Work Replaced Disk, Cleaned, Lapped and Set Tested
8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Other~ Pressure 220 psi Test Temp. Arnb j ent °F
  • NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (11 size is 8% in. x 11 in .* (2) informs*

tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(12/82) This Form (E00030) may be obtained fro,01 the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017

FORM NIS-2 (Back)

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and thii.:l e g lace men :laonforms to the rules of the ASME Code,Section XI. repair or replacement NR TypeCodeSymbolStamp~V~R...;__~--~~~-~~~~~~-~----------------:-:-=---

50, 138, 261,262 24,63 VR NR Certificate of Authorization N o . - - - - - - - - - - - - - - - Expiration Date JU l y 2 , 1 SS 6 - Ee b 17 , 1 SS 4 Signed .LU~ @.~Lr Owner or Owner's Desilfnee, Title

  • Date November 2..1

.,//

. 19 93 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New .Jersey and employed by Ark wr i gh t M11t1 1a 1 In sr *ra tlc: e Cc;;i of Norwood MA have inspected the components described in this Owner's Report during the period--..,!"""'-=O=----'--~l,~--9~-~=---to __/.__1_-_9~---9_'3 _____ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his empl~yer shall be liable in a~ for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ~\ Factory Mutual Engr. Assn.

~~ . Commissions f!q. 2-oS <O If.!' I /fl .:S t '...., !.) ~ 'T :J /

Inspector's Signature National Board, State, Province, and Endorsements Date_f._l-+f-z_~-f+-/_-_ _ _19 tfJ

  • FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1. Owner Public Service Electric & Gas Co. Date __l_/_2_5_/_9_4_ _ _ _ _ _ _ _ _ _ __

Name End of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ _ 1 _ _ of _ _ 1 _ _ _ _ _ _ _ _ _ __

Address

2. Plant Salem Generating Station Unit_l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Name End of Buttonwood Rd. , Hancocks Bridge,NJ Pl-931602 Address Repair Organization P.O. No., Job No., etc.

3. Work Performed by Wy!e/Crosby Type Code Symbol Stamp _ _ _N_R _ _ _ _ _ __

Name Authorization No. _ _ _ _ _ _6_3_ _ _ _ _ __

7800 Governors Dr.,Hunstville ALA 35807 Expiration Date ___2__,/'---1_7-'-/_9_4_ _ _ _ _ _ _ __

Address

4. Identification of System Reactor Coolant ASME Sect.
5. (a) Applicable Construction Code III 1s__§_§__Edition, N/A Addenda, _ _N_/'---A____ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83 S83
6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol 1PR3 Crosby N69878-01 N/A N/A 1968 Repaired No 0001 1PR'1 Crosby RV-466 N/A N/A 1968 Repaired No 1PR5 Crosby RV-2-8010 \ N/A N/A 1968 Repaire l No 2PR3 Spare Crosby RV-464 N/A N/A 1968 Repaired No
7. Description of Work Installed modified flexi-disc - 2 and refurbished all valves.
8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Other [21 Pressure 1PR3-248~si Test TemplPR3-654 °F 2PR3 (Spare)

NOTE: Supplemental sheets in form otnsfs:;k~1~e~. or drawings m~l~ u~~d~~r~~ded (1) size is BY. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017

FORM NIS-2 (Back)

Applicable Manufacturer's Data Reports to be attached

      • ~

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code,Section XI. repair or replacement Certificate of Authorization No. ---'6=3___________ Expiration Date ---"'2""/_1_7__,_/-'-9_4________

Signed v

,Ld,L. 4...4_, /?.~

Owner or Owner's Designee, Titl8 4r

  • Date _ _ t_-~7-_,eP-o._______, 19  ? Y" CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Arkwright Mutual Ins. Co. of Norwood, MA have inspected the components described in this Owner's Report during the period Sept* 1993 to Jan* 1994 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Factory Mutual Engr. Assn.

_(}~"-"" *~~"----'f_._.,~~~-=--*L--

~~specter's

__* ___ Commissions_~AJ-=':S-~J"-7""""~""""*_I_ _ _ _ _ __

Signature National Board, State, Province, and Endorsements Date_ _ _ /_-_~_J-_*. __191 i

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Public Service Electric & Gas Co. Date _ _F_e_b_r_u_a_r...::y,__7__:_,_1_9_9_4_ _ _ _ _ __

Name End of Buttonwood Rd.,Hancocks Bridge,NJ Sheet __ l _ _ _ of _ _l_ _ _ _ _ _ _ _ _ __

Address

2. Plant Salem Nuclear Generating Station Unit _ _ _ l _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Name End of Buttonwood Rd.,Hancocks Bridge,NJ WO #931023024 CJP PS-93-086 Address Repair Organization P.O. No., Job No., etc.

3. Work Performed by Joseph Oat Corporation Type Code Symbol Stamp_--=U-=l:....__ _ _ _ _ __

Ne me Authorization No. U-184 2500 Broadway, Camden, NJ 08104 Expiration Date _ __;_7.:.../-=9...::/_9:....::4__;__ _ _ _ _ _ __

Address

~ ldentification~Synem ___C_o_m~p_o_n_e_n_t_C_o_o_l_i_n~g~--*-----------------------

5. (a) Applicable Connruction Code ASME VIII 19_filLEdition,_...;:N.;..t./..:A;.;:.__ _ _ Addenda,_.:..:N.:.../..:.A=------Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8'-3'---
6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 1CCE5 Jos-Oats S-15763A 1148 N/A 1970 Replaced y rnrn 1CCE5 Jes-Oats 2529 N/A N/A 1993 Replaceme1 t N Corn.
7. Description of Work Modified existing flat head by installing Manway S/N 2529.
8. Tests Conducted: Hydrostatic 0 Pneumatic D Nominal Operating Pressure D Other D Pressu re__.1....,6.,_7,___ _ psi Test Temp. 61
  • 2 °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y:. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017

FORM NIS-2 (Back)

9. Remarks __A~t~t~a=c=h~e~d~=~~U~-~2=A~*~M=a=n=u~f=a~c~t=u=r~e=r~'~s~P~a=r~t~i~a=l~=D~a~t~a=-~R~e~p~o"'-r_t_f_r_o_m_J_o_s_.~O_a~t_C_o_r_p_.

Applicable Manufacturer's Data Reports to be attached for Manway and Coyer.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code,Section XI. repair or replacement Certificate of Authorization No. --~3~6~-----------Expiration Date ___l_0_/~3_/_9_4_ _ _ _ _ _ _ _ __

Signed _ ~.LJ!j P--WV:...c~,./ 6'""7 . .

  • Owner or Owner's Designee, Title Date~A~~~~'"~'.?~----* 19 9 j?

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Arkwright Mutual Ins* Co* of Norwood* MA have inspected the components described in this Owner's Report during the period Sept. 1993 to Feb* ' 1994 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the Date_ _C._8_M_A:.....:..c...R.c.....=.µ,__ _ _19._C)~4

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S},iJ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l

. Work performed by Public Service Electric & Gas Co. - Nuclear Dept. CJP #892-379 (name) (repair organization"s P.O. no., job. no.,etc.)

  • Foot of arttollW'OOd Road, Hancxx::ks Bridge, NJ 08038 (address)

(name)

Foot of arttollW'OOd Road, Hancxx::ks Bridge, NJ 08038 (address)

3. Name. address and identification of nuclear power plant Salem Nuclear Generating station Unit #1 Foot of arttonwood Road, Hancxx::ks Bridge, NJ 08038
4. System Chemical Voltnne Control Nuclear Class II 5.a:~m~n~tre~~.modm~~re~~oo_l_l=~-~5_5_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Nameofmanufacrurer_~I'I'l'~...__Gr_,,,-innel...__.._l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

c: Identifying nos. SD-C-112277 WA N/A N/A --=l=-98=-8=------

(mfr's. serial no.) (Nafl.Bd.No.) Qurisdictional no.) (otner) (year built) d: Construction Code B31. 7 1969 N/A NIA II (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 SUnurer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N~/~A _ __

(edition) (addenda) (Code Case(s))

8. Applicable ooition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A N/A
  • B31. 7 (edition) (addenda) (Code Case(s))
9. Design res~nsibilities ~PS~E=&G~---------------------------------------
10. Tests conducted: hydrostatic O pneumatic O design pressure O **pressure N/A psi Code Case(s) __N~/._A-"--------
11. Description of work Replaced studs, nuts arrl bonnet in kin:i.

(use of additional sheet(s) or sketch(es) is acceptable if ;>roperly identified)

12. Remarks: __W'"... r k....._OID....._-e "o.... ...r...._..,.f_,.._:__ 2_.l.-2~1~6.....__ _ _ _ _ _ _ _~De-.f 2,..0..._9....

9 .... ....1.,*c,,....iency_,.~_....Re_po~rt~....#~:---SMD,.__"--"'9""2._-.....7....3'""6'------

Design OJange Package #: N/A Rev. N/A See attached pages for Description of Replacenent. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires oct. 3 1 , 19 94 Date Io --z. c 19.~. Signed. _ _PSE&G _ _ _eo_._-_Nu_c_l_ear __De_pt_.__ ~ .f'L/,. &; . L. Principal Erx1r (repair organization) (author:zed representative) (title)

CERTIFICATE OF INSPECTION

.1. the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / -- , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with* Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthenmore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connec!OO with this inspection.

~ / ,? Facto:r:_x Mutual system Date )O** Zf, 1~. Signed ~~ C--.. Lt-vC--- Commissions_ _A/;£~-"J--__._3-'/'-vol'-J_________

(Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boller and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev6

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT($)*

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l

  • o~~~~-~ru~bul~i~c~s~e~~~1~*rn~-E~l~~~~i~c~&~~~~s~Co~.~-~~~c~l~e~e~r~De~p~t~~*--~~~~#~S~9~2k-~3~9~2 (name) (repair organization's P .0. no., job. no.,etc.)

Foot of Buttonwood. Roa.d. Hancocks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038
4. System Containment Spray Nuclear Class II
5. a: Component repaired, modified or replaced _,l,..2"-'CS=3=6_Vi......,,,al......,,Vi_.,e.___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Nameofmanufacrurer _ __.:u,.,~""""'------------------------------------'--~

c: Identifying nos. 12024/S?OWDD _ _ _N;.,_/_A_ __ N/A 1987 (mfr's. serial no.) (Narl.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code ASME DF&V 1968 N/A N/A II ANSI B31. 7 1969 B.ilitio{fl970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 SUnuner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1968 N/A N/A
  • ASME DP&V/ANSI B31. 7 1969 F.d. 1970 Add. (edition) (addenda) (Code Case(s))
9. Design responsibilities _];~~L--------------------------------------
10. '!'ests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _ _,N""/.....,A~------

ascription of work Replaced valve bolting.

(use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: __W......,a~r~k__...Oyrl"-"-'~ear-'lj~:~9~2~0u9'"'-'<o2~1~1~7~7_ _ _ _ _ _ _ _ ___,I);-<=-f~1~*c'"""jen....._.<::;t.""'1---"'R~e~po.,,,,.._rt......._~#~:..........N;~/uA....__ _ _ _ _ _ __

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A

    • stem Insfilvice Re rt T
  • Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4_ __

Date I I .. 7 _c.

e:;; ::i PSE&G Co. -Nuclear Dept.

19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ ,,4-d<L&~.L--

/ ~/ Principal Engr.

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I/- fs' , 19 9 2 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Factocy Mutual Engr. Assn.

Date J/- Li- , 19 q) . Signed 9- Cm' f.t/ (. lr, A<:*

(Inspector)

CommissionsN 8 {°~4 t./ LJ A AJ'J ? 'Z J (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

N8*81

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S} ~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l rkperlormedby_~B~Jb~l~1~*c...._Sus;;earv-><-iuc~~=--E l~ect

....... .......~r~i~c.._.&..._,G~.;a~s...._~ca

......._-___.Nt.....,1c~l~e~a~r~~De~pilt.~*.___ _~CIP .......--:i#uS~9~3~--0~0~8_ _ _ _ __

(name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwood Rood, Hancocks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwood. Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __...S..,al.....,,em ~_..S._.ta""""t""1..,,'o,,....n.___,U~ni'-'='='t=-_,,#_,,l=------~-

......_.Nu......,.,.c,.l.,,,e.,,e...r.,___,Gen..,.,...,,,era..._,,...,t,..ing.,.'

Foot of Buttonwood Brad, Hancocks Bridge, NJ 08038

4. System Oiemj cal Volume control Nuclear Class II
5. a: Component repaired, modified or replaced _...1,,.CV2'-"-"'.,,8""4"--V........,al..._.y,""e"------------------------------

b: Name of manufacturer Anchor Dar] i ng c: Identifying nos. 9847-70 WA 1970 (mfr's. serial no.) (Narl.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code W E-Spec 4GM42FRH .........__ _~~..,l ......A~--- WA ANSI B31. 7 1969 OO!Ltio'11.970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 Summer 83 WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 ..._.N;,_,,/A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31. 7 fW E-Spec 4GM42FBH(edition) (addenda) (Code Case(s))
9. Design responsibilities __J=l.:&!~----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NGP psi Code Case(s) _ _ N;,,_/~A~------

escription of work Replar-ed valve lx>lting.

  • (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ ___..w~o~r~k__._Ord......,~e~r~#~~,___,;9~2~J~0~2u8~0u8=4'--_ _ _ _ _ _ _ ___..De-=-f~1~*c.........,ie~n C?fqr-~B~e+Po

......... .........rt-_.__~#~*._.N..,/,_.A=---------

l);sign Change Package :f!: WA Rev. N/A See attached pages for Descri.ption of Replacement. N/A

    • stem Inservice Test . Nor

. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __

PSE&G Co. -Nuclear Dept. Principal Engr.

Date I - I JT 19,__f__Z::_. Signed _ _ _ _ _ _ _ _ _ _ _ _ __

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of :MA. have inspected the repair, modification or replacement described in this report on - I , 19 f and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Ir CJ ,J /1 . _., / 1 . ;r.ac:t9:ry ~tual ~. Assn.

Date~/-~*~{_\_, 1~. Signed l ltY'n/l.h/ 4 * ~ CommissionsNP C'f1 'f J./IJ /4 JUJ} j _9

/ (Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS *- ,..: ' f l Pa e 1 o

'ork performed by _ _.B"-'-'-1b......_J.....i .....c........S....,e~rv....._.i....c_.-e'"'--E'-"-'-l-"'ect

....._.r_1.....* c._._...&--"'C..;:i,..,..s"-'C._n._.....__-__.Nl....._.1c......,.l_..e. ._oa...r__.De-=p...,....t~---'-C....TP'"'---'#Jl"S......,.9_,3'--__..0...3.._,6...__ _ _ _ __

(name) (repair organization's P.O. no., job. no.,etc.)

Foot of Bnttonwaad Road 1 Hancocks Bridge 1 NI 08038 (address)

(name)

Foot of Buttonwcx:x:l Road, Hancocks Bridge. N.I 08038 (address)

3. Name, address and identification of nuclear power plant _ __...S,.al.....,,em ......._.Nu..,_, ,.,.c,. l., ,ec0o"3...ri.......:Gen,,,.,,......,,era"""'...

"*"t""mq

"-""lL-looS,_,ta~t!o<d.i,,,o,,_n.___,U.,,ru...,.,*.,,t"--'#r..,l.,_________

Foot of Buttonwaad Rood 1 Hanccx:ks Bridge, ID 08038

4. System _ ___.R..,,,~ t~---------------------------"'Nu......,c,,.l

.....ct......._..._n....r_,,eoo.......,..,,,.l.....a. . .n..........

...-a ...e""oa""""r__,,C,,,,l,.,,,as"""'s~I=---

5. a: Component repaired, modified or replaced -l... FS .......2....,,8..__V.~a-...l~Vi~e~-----------------------------

b: Name of manufacturer --.lL.C::..u;;,..u_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

c: Identifying nos. ___.8_,_l.._J.._7_,___ _ __ 1977 (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code ASME DP&V 1 968 N/A ANSI B31. 7 1969 00Ltior!l_970 Add. (addenda) (Code Case (s)) (Code Class)

6.Section XI 1983 si wmer 8 3 WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N:~IA~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1968 N/A N/A
  • ASME DP&V/ANSI B31. 7 1969 Ed. 1970 Add. (edition) (addenda) (Code Case(s))
9. Design responsibilities __.IJ;2.ldQ!1.2...._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NDP psi Code Case(s)_~N;~/A.....__ _ _ _ __
11. Description of work Replace stem and valve bolting.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

r:,...,k__._O.t..1.rd-'-"'e"'r--;#lf-*_9~2....,Q,...8"-'0....4....l_,7"""9'------------...,De="-f......i.._c....i""e.._n.._cy~_...R""e-+/-po,.,....,...rt_,__,#rF--*_N..,.,f-l""A.____ _ _ _ _ _ __
12. Remarks: _ _....,w..._o.....

Design Change 'Package :If: N;/A Rev. N;/A See attached. pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3,

  • 19~9_4~--

PSE&G Co. -Nuclear Dept. / / ./ , Principal Engr.

Date /-I y 19,~. S i g n e d _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~b&e (repair organization) ..-7 (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described. in this report on / - If . 19"'f and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty,

/ /.

ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Facto:ry Mutual Engr. Assn.

Date )-0 ,1{lj__. Signed£,vm.J;../

9 'z. *

(Inspector)

~ CommissionsNJ (f1 t/ Y:)./ J( 4AJ12}

(Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB*81 Rev.6

. FORM NR*1 REPORT OF REPAIR ~ MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed ' / -=-.Pub=l=i=*c=-=Serv:o==-..;_::i=ce=-=--=E=l=-=ectr=-=-==-=i=-=c--=&--=Ga=lS=-Co=--=--.;__--=-Nu.:...:..:..:c-=l=-=e=e=r--=De...:::Jii:cp-=t-=._ _ _CJP..::...::....:---'#"-S_9--=3=----=0--=8=2:___ _ _ __

(name) (repair organization's P.O. no .. JOO. no .. etc.)

Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) 2.0wner __.Pub __ l_ic_Serv _ _i_'ce _ _E_l_ectr ___ i_c_an:l _ _Gas_ _Co __

  • _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(name)

Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address)

3. Name. address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocd Road, Hancocks Bridge, NJ 08038
4. System Service Water Nuclear Class I I
5. a: Component repaired, modified or replaced 13SW58

~--------0-:-:-~-------------------------~

b: Name of manufacturer Ma.sonellian International Inc.

c: Identifying nos. N-00113-40-3 N/A N/A N/A 1974 ASME Draft (ili!&Vsel966 F.d. Mqm'arlia7..G.J Add. Uurisdictional no.) (other) (year built) d: Construction Code ANSI B31. 7 1969 N/A N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 summer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications. or replacements were made: 1983 S83 N/A

~----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A N/A (addenda) (Code Case(s))
  • ANES&GI B31. 7 /ASME Draft P&V 1968 Ed. Mar 1970 Add. (edition)
9. PS Design responsibilities ---=--------------------,.-,---------,-.,-------------0...,,.-,~------
10. Tests conducted: hydrostatic O pneumatic O design pressure O **pressure NOP psi Code Case(s) _ _ N~/_A_ _ _ _ _ __
11. Description of work Re}?aired vane holes and taper pins by welding.

(use of add111onal sheet(s) or sketch(es) 1s acceptable if properiy 1denuf:ec)

12. Remarks: _ _,W_,_,,o..,.r...._k"-""Ord,.,_,.,er,.,,,,__~#"--':..__.9=3~0=3=3'-""1=1=0=3_ _ _ _ _ _ _ _--=De=f=i""'c""'iency~=:..z....--=Re=po=rt=-=-_ll.#-=-:-'SMD=:o__:9:..::3o._-_,,0'....'..7_,,,2_ _ __

Design O'lanqe Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A

    • Inservice Leak Exam Temp. NOI' CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __

PSE&G co. -Nuclear Dept. Principal Engr.

Date L/" -3 () 19,_!j_3__. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(repair organization) (authorized representauve) (title)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance CO of MA have inspected the repair, modification or replacement described in this report on 4 // , 19 23' and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied. concerning the repair, modification or replacement described in this report. Furthermore. neither the Inspector nor his employer shall be in any manner for any personal injury or pro~erty dama e or a loss of any kind arising from or connected with this inspection .

./"7i Factory Mutual Engr. Assn.

Date h l*u;. C 19 9.:!f Signecf.-__.f*-:::=.e.: */(,ff,,:-*/'-- Commissions //f/ 1'/6 /;. ){;f /CJ£?

r: (Inspector) (Na:!.8d.No.(;nclud1rg e~co*s"~en:s)s<ate o* P'OV;nce a~c c,c-,p~*:

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229 .

FORM NR*1 REPORT OF REPAIR D MODIFICATION g'l OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS

. Pae 1 of 1 ark performed by __,P1E<1ubou1o1ol.=,l.~*c..r--.Sa<~~y..,n.~*c...e-.El~ectso.;-\..t:.ri-..l.~*C.r-<&llf--\Qlsaa;_.c

...c~._,-=--.it;"'4:fu_.c

...li.ce.:..a*lrl.----iDe-=tp.11t~-~---'C

...:JP,>E-~#""S;i,;9;i..J->'-=.l.1.10..,.8~-----

(name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwood Road, Hancoclrs Bridge, NJ 08038 (address)

(name)

Foot of Buttonwood Road, Hanccx::;ks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant --~S-a~l~em~~Nt~1c~l~e~a r_...C~

......... ..._.n~e_rri~~t~i~ng-.....S~t--a~t~i~o~n~_I_I~n~i~t~=lf .......

l'--------

Foot of Bnttonwood Road, Hancock.s Bridge, NJ 08038

4. System Chemical Volrnne Control Nuclear Class II
5. a: Component repaired, modified or replaced _.1...cs_.....ZE.....,6c.......T...a... 1k._______________________________

in...

b: Name of manufacturer .Jos. Oa.t & Sons, Inc:.

c: Identifying nos. 1781 2A 374 N/A N/A 1969 (mfr's. serial no.) (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code As.ME III Class C 1968 N/A N/A ANSI B31. 7 1969 FA!~iti0]!.970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 SUmmer 83 N/A (edition) (addenda) (C9de Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1 983 883 ~~~/A~~~

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1 969 1970 ~~¥/~A~--
  • ANSI B31. 7 /ASME III Class C 1968 (edition) (addenda) (Code Case(s))
9. Design responsibilities --1::..:;ii:.ai.:z___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic O pneumatic D design pressure D** pressure NOP psi Code Case(s)_.....~-'¥--/""A~------
11. Description of work Repl aero bolt j ng wj th 1J?Jraded materi a 1 (use of additional sheet(s) or sketch( es) is acceptable if propedy identified)

N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 1~~4~--

Date// - 3o 19,____£:1__. Signed_ _PSE&G _ _ _eo.-Nuclear _______ Dept.

____ ~,

/ // ~ ** Principal Engr.

(repair organization) _.,. (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / !/? , 19£3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this.report. Furthermore, neither the Inspector nor his employer shall be

.1 any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

C::::-"*- Factory Mutual Engr. Assn.

Date j2- 2 '19 9.J" . Signed h,r ~~ Commissions j1)8 6 s.:ry U/./i'S 1.i VT<f.Q/

(Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l Wark performed Public Service Electric & Gas CO. - Nuclear Dept. CJP #S93-114 (name) (repair organrza!lon's P.O. no .. JOO. no .. etc.)

  • Foot of Buttonwocrl Road, Hancocks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwocrl Road, Hancocks Bridge, NJ 08038 (address)

3. Name. address and identification of nuclear power plant -=----Sal-:--:::-em  :..=.....L...::S=--ta=-=-=t~i'-"o..:.n-'--_U_Ill_.--'t'---'#'-'l=-------

__Nu_....:.c..:.l;_e_a_ir_Genera.::...::.::..::..:::..=::..t=ll'!I=*

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

4. System Safety Injection Nuclear Class I 5.a: Campanentrapairad.madH~darra~aced _1~2=~~1~5=--6~V~~~y--'e~---------------------------

b: Name of manufacturer _ _V-'-=e=l=an~--------------------------------------

c: Identifying nos. 78704 N/A N/A N/A 1968 (mfr'~e~Spec (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code ~6~7~6~2~4~1~--- N/A N/A (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 SUrrurer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Cade Section XI under which repairs. modifications. or replacements were made: 1983 883 ~N~/A _ __

(edition) (addenda) (Code Cas~(s):

8. Applicable edition of Construction Code under which repairs, modifications. or replacements were made: *676241 N/A N/A PSE&G
  • N E-Spec (edition) (addenda) (Code Case(s))
9. Design responsibilities -------------------****-----?~q()fAip;}-----------l<Nh/'-'l-A.~------
10. Tests conducted: hydros!~~ l~ce&nzym~ Jlsc~esign pressure O pressure _ _ _ _ psi Code Case(s) _ _ _ _ _ _ _ _ __
11. Description of work p (use of addrnonai sheet\S) or s~etcnies; 1s accep:able ,f properiy 1dent.f*ed)
  • ---~~~~~~~~- Wo :r k Orde:r #. 920713003 Eeficiency RepJ:rt 12.Remarks: --f'--....+.~,.......,.....,.~~,.......,.._.,""'"~.,...--.jj--,....,.,...,..,.__ _ _ _,.......,..,,....-.----_,,,,~,...__--------------------
  1. . N;'A OOSign Cl'lan3e Package #: NJA Rev. NJA See attadie:l pages fo:r Desc:riptio11 of Replacement. N;'A
    • System Il1Se:rvice Test Temp. N;'A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair. modification or replacement of the items described above conforms ta Section XI of the ASME Code and the National Boar'3t5iles as defined in the publication NB-102,~~t ~ition.

94 Certificate of Authorization no. ta use the "N R" stamp expires ' . 19- - - -

Date~fo'---'(~7~- 19,..!13__.

PSE&G Co.-Nuclear Dept.

Signed________________

/J.,

UM../~ V - /lt1'rt-1ru J}g_4,.J,

-/!-A Prµicipal Engr.

I (repair organization) (authorized representa:>Ve) (11!le)

CERTIFICATE OF INSPECTION I, the undersigned, holding a ~~i,,~~n issued by The National Board of ~~1~t5~mml~eetcate of competency issued by the stat~ province of Y and employed by-----------------------~------

cf have inspected the repair, modification or replacement described in this report on J"v1-1c 7 . 19 93 and state that to the best of 1'1Y knowledge and belief. this repair. modification or replacement has been made in accordance with Section XI of the ASME Cade and the National Board rules as defined 1n the publication NB-102, current edition. By signing this certificate. neither the Inspector nor his employer makes any warranty .

ssed or imp!ied. concerning the repair. modification or replacement described in this report. Furthermore. neither the Inspector nor his employer shall be 1n any manner far any personal injury or property damage or a loss of any kind arising from or connecte'Fg~2jf:}9sru~ Engr. Assn.

Date '. 7 . ig---2..1.__ Signed W.1~7~ 12. 1<?...,,._,, ~m: Commissions NlJ 7980 NI 8 s  ;;:r z PA- z'--"o"-4-.'---_

(l~s:ie~ (~Jn:* BaJ~o.;*nc!~c .... g e-Co*sc- ..... t?;:s*:s:a:e; o* :J*ov '"'Ce ,)'""Cr .. -*:i::*.

This form may be obtained from The National Board of Bailer and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l erk periormed

  • Public SeJ:vice Electric & Gas Co. - Nuclear Dept. CJP #893-124 (name) (repair organization's P.O. no .. job. no .. e!c.)

Foot 01 Butto:nwocxl Road, Hanax:ks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwcxx:l Road, Hancocks Bridge, NJ 08038 (address) 3 Name. address and identification of nuclear power plant Salem Nuclear Generatincf station Unit #1 Foot of Buttonwcxx:l Road, Hancocks Bridge, NJ 08038

4. System Safety Injection Nuclear Class I
5. a: Component repaired. modified or replaced 13SJ156 Valve

-"-'------------------------------------~

b: Name of manufacturer _ _V..._e~l,,,an....__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

c: Identifying nos. 78704 N/A N/A N/A 1968 (mfr'~~Spec (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code __,6,,_7,_6=2=----4~1~--- N/A NIA I (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 SUmroer 83 N/A (ed1:ion) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs. modifications, or replacements were made: 1983 883 ~N~/=A~--

(edition) (accendai (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *76241 N/A N/A PSE&G
  • ~ E-Spec (edition) (addenda) (Code Case(s))
9. Design responsibilities ---------------------ik.,.,kt--------'l"'q()AEpr--------------'llil<f/,.,"i'!A.----------
10. Tests .co.nducted: hydrost~l~ced'n~{i.~ Jlsc~esign pressure O pressure _ _ _ _ psi Code Case(s) _ _ _ _ _ _ _ _ __

11 Description of work - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

(use of add1t1onal sheet(s) or s~etc~(es) is acceptaoie if properly 1dent1~1eci; Work OI:de:r #: 900715077 Ikficie11cy Repo:t t #: N;'A 12.Remarks: ---r'l=:,,...;-,.....--r......,,......,....,....~~.n,..,.,...,..---.11--oc-t~,,_--------r:,......,.---1<T-f"ft--------------------~

Design CltarxJe Package #: N/A ReV. N/A See at tad red pages for IXs::r iptio11 of Replaceme11L. N;'A

    • 8Ys Len IllseJ:: vice Test Temp. NO!'

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or repla.cement of the items ~escribed above conforms to Section XI of the ASME Code and the National Boarc:)'5'1es as defined in the publication NB-102,Me.nt :fition.

94 Certificate of Authorization no. to use the "NR" stamp expires ' , 19_ _ __

Date IP/ "1 19,!/3.___. Signed PSE&G Co.-Nuclear r:ept. ~ j~o.A l,~l:};['ipal Engr.

(repair organ,zat!on) (aut~.o,;zea representative; CERTIFICATE OF INSPECTION I, the undersigned, holding a ~~~~n issued by The National Board of ~M-i'ts%~1~ee!8cate of competency issued by the stat~ province of Y and employed by _ _ _ _ _ _ _ _ _ _ _ _~------------------

of have inspected the repair, modification or replacement described in this report on S-vN 6 7 . 19 93 and stale that to the best of my knowledge and belief. this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board ru:es as defined 1n the publicaticn NB-102. current ednion. By signing this cernficate. neither the Inspector nor his employer makes any warranty.

ssed or implied. concerning the repair. modification or replacement described in this report Furthermore. neither the Inspector nor his employer shall be n any manner for any personal iniury or property damage or a loss of any kind arising from or connccte'F&&:~cysr.t\.I~l Engr. Assn.

Date 6 -2 . 19_&__ Signed wdka.. Ir~~?~W Commis1~:~~~~~:~~ ~;c;/!r.~~J:e ~,~c:~~c."-~~-

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) ~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1

~orkpertormedtJY~Pi~blbl.l.l.l~ic--~sen-=--¥r~i-c~e.__E~l~ect~Q;*~i~c...__&._....Gas~ c~o'+-.,--.=-~Nl-..lCw*l~eQa.r___..De~pt..__,~~--'-C~IP...._*#~S~9~3=-~J~4~9'--~~~~~

(name) (repair organization's P.0. no., job. no.,etc.)

Foot of Buttonwood Road, HanCXX"Jcs Bridge, NJ 08038 (address)

(name)

Foot of Buttonwood Rrad, Hancocks Bridge, NI 08038 (address)

3. Name, address and identification of nuclear power plant --~S~a~l~em~...N1~1c ...l~e-.;:i~~r__,,G..,.;e_.n

...e rn .......t_i...ng~_..S.... t-21

.....,t_1..,'o..,.n....____..U...n....i""t..._.,.:ff...1________

Foot of Bn:ttonwocd Road, HaJ'lCOC:ks Bridge, NJ 08038

4. System Chemical VolJJDJe Control (OTC) Nuclear Cl ass IT
5. a: Component repaired, modified or replaced _,,N...,o...,.___.J_.J.__.Ch_,*

..,a....DJ~,_.i_.ng_._J?r

......mip ............i ......f_i...c....~

........__-__.M'L1.._'n..._.i_..f_.1....aw....._-'Or ......-\,(....Ccmp

............__T.._D........_.1_..CVE....,._.u2 0y.)_ _ _ __

b: Name of manufacturer Pacific Pump Inc.

c: Identifying nos. 45603 N/A N/A N/A 1970 (mfr's. serial no.) (Nat'l.Bd.No.) Gurisdictional no.) (other) (year built) d: Construction Code W E Spec 6771.25 N/A N/A (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ....

~~/~A_ __

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A N/A
  • N E-Spec 677125 (edition) (addenda) (Code Case(s))
9. Design responsibilities __i:::.:2.1:.w..z__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic IX pneumatic D design pressure D **pressure 3550 psi Code Case(s)_~~-/~A-------

'Tbe lI!CX'Jified miniflaw orifire was replaced in accomance with the (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19=9_,.4_ __

Date j( - "2.3' a 19,--1...i._. Signed_ _PSE&G ____ Co. _ _ _ _ _Dept.

_-Nuclear _ _ __ Principal Engr.

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by ' Co of MA have inspected the repair, modification or replacement described in this report on , 19 9...J.., and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in an.y manner for any personal injury or prop~rty e_am~r a loss of any kind arising from or connected with this inspection.

, ;_ ~ Facto:cy Mutual, Engr. Assn.

Date 11/ZI 1

, 1~. Signed ~ Commissions ~-7 Z.-ofl:, 11..);s(JJ .J ,,LJT<C..?/

(Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB*81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION OR INSTALLATION OF REPLACEMENT(S) ~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS

  • Pa e 1 of 1 ork performed by e.,,,~

.......l ...i ...c....-...s... ..........,l....

--wl?1...Llb

  • c...e--.E ...ect

...1 ...............r ....i ...c__..,&,___.,.Ga,..is ~-___.N!.,.....1c_J...,ea...r-.De

.............C...o.....

(name)

.... ......p+'"-t---.....c...JP.....____,#ff"S.....9.,_,3. ._-__._J....

(repair organization's P.O. no., job. no.,etc.)

5...

0 _ _ _ _ __

Foot of Bn:ttonwood Road, Hancocks Bridge, NT 08038 (address)

(name)

Foot of B11ttonwood Raad, Hanax:ks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ _....S...a....l"""em...wL.....L:Nt 1c~l..,e

..... ..e......... ..:ra r__,.C"...i=!.,...,n...,e .......u.t....iu.ng-"!f.....JS...,...ta......,.t_i._.o...,n.....___..U....n.._i'"'t..._JJ:#...l~------

Foot of Bi rttor1wood Road, Hancccks Bridge, NT 08038

4. System Cbemi 03] Va] ume Contra] (OTC) Nuclear Class I I 5.~ Componentrepa~e~modified~re~~ed~Nua~.~1~2~~~~a~~~iu.ng~....JB~~~~-~M~iu.n~i~f~J..,~~~~~i~f_i..,c~~~*(C~~~~~I~D~l~~~~2~1~)_ _ _ __

b: Name of manufacturer Pacific l?ump Inc c: Identifying nos. 45604 N/A N/A N/A 1970 (mfr's. serial no.) (Narl.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code W E-Spec 677125 N/A N/A (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: J 983 S83 N;~/A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N;/A N/A ~N;~/~A~--
  • ¥! E-Spec 677125 (edition) (addenda) (Code Case(s))
9. Design responsibilities - - l : : L : l . . l : : . l : l l ! " " - - - - - - - - - - - - - - - - - - - - _ _ : _ - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic IX pneumatic D design pressure D** pressure 3550 psi Code Case(s)_~N;-¥-/A......__ _ _ _ __

The modified mini fl aw orifice was repJaced in accmT3ance wjth the (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

NIA I CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 199~4~--

Date II - J.. 3* 19,_fil_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

PSE&G Co. -Nuclear Dept. / / t?

4.4-?ah* -

..4c-* Principal Engr.

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by ce Co of MA have inspected the repair, modification or replacement described in this report on 'J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be

  • any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

, /.. f ~ Facto:ry Mutual. Engr. Assn.

Date~, 1 19 7~ . Signed ./JU~ Commissions A :z..o~ A./1Os1.J jv'.:J '/.JI (Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)JS TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l 1

orkpertormedby __J?!i;:..u1h.....,,J~i~c........S~e~rv.......,.~i~c~-e;;;._Ei.:.u.l~ect

.......~r~ic....__~&.._.G~.;a~s"'---'C~n~~---__.Nt........,1c J~e-eur__,De....,..pt.~

....... ..............__ _~c~IP......__#wS 9_3~--1~7~l....______~

(name) (repair organization's P.0. no., job. no.,etc.)

Foot of Buttonwood. Road, Hancoc;"ks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwood. Road, Hancocks Bridge. NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __._s...al......,em,...._Nuu.w... c..,l.,.e...e"""r~Gen!oil!iii;&.Jl!iiera:...._...i..ti...i..in;J.l..J!:,__.S""'ta:i.s.ot~,..i...a..n...__,U,,,,,ru.:._..,.',_,,t,,___,#~1=----------

FCX>t of Bnttanwoad Road, Hancxx=:ks Bridge, NT 08038

4. System Safety Injec+/-i on Nuclear C1ass I I
5. a: Component repaired, modified or replaced _____________________________

......,J,..1..,S..,J,_l..,3,.,4.....__.V.""al~v..,,e b: Name of manufacturer --..v..i::..u::u.i.--------------------------------------

c: Identifying nos. 1 540 WA 1988 (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) (year built) d: Construction Code W E-Spec 676258 ANSI B31.7 1969 ~~or!l.970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 _ _.._$1...nmne ............r...._8..._.3_ _ _ _ _ _ _ _ __ WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 .....,1'{.,__./A......___ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31.7JN E-Spec 676258 (edition) (addenda) (Code Case(s))
9. Design responsibilities --'.:..t.!.IOlll!.sr...._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. T~sts conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _ _ N;.,./_A_______
11. Description of work Replaced. valve stem: bolt:ITTJ and pe.rfonned wel.g. repair on leak.-off (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ __.Wi~o~r~k_..Qnj~~e~r.._~#~*~9~3.......,0-7~0~8~1~0~4=-----------~De--f~1~*c~i-e-n_cy~-R~e~pa~rt-~---'ff#~*_.N~/~A~---------

Design Change Package #: N/'A Rev. N/'A See attached pages for Description of Replacement. N/A

    • stem Inservice Test . Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19~9~4~--

II- PSE&G eo.-Nuclear Dept. t? .t?; -<-* :..4..,,.1 Principal Engr.

7~

Date 3 d 19,_£3_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on 3 c> , 19 lj>J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property~ge or a loss of any kind arising from or connected with this inspection.

~ .,,Facto:r:y Mutual Engr. Assn.

Date / /

1 I3o , 1~. Signed -~

(Inspector) .

Commissions f".4 2 OS~ VI HS IS' 0° £'.5 /

(Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

r==._......_._..............===========*-*-**-------

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0

./ '

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2

ork perfonned by pnhl j c Service El ectri c & C-.as Ca - Nucl ear D?pt. OTP #593-181 (name) (repair organization's P.0. no., job. no.,etc.)

Foat of Bnttonwpcx'J Road, Haneocks Bridge, N.T 08038 (address)

(name)

Foot of Buttonwood. Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __,,S..,,al.....,em..,..~Nu.....,,..,,,c,..l~e~.-::i""r~Gen~~era~~t~ing~:l-!s~ta,,,,..t"""i""o,._,n,____,,U._.m"""'"'t,,,_.u.#.:::1,________

Foot of Butt:oIJIMCXld Roadu Hancocks Bridge, N.T 08038

4. System Safecy Tnj ecti on Nuclear Class I
5. a: Component repaired, modified or replaced _1...1......... s r....1....7'--V,...,a...l...v......,.,e~----------------------------

b: Name of manufacturer Boc:kwel 1 - Fdwams c: Identifying nos. N/A N/A N/A N/A 1968 (mfr's. serial no.) (Nari.ad.No.) Ourisdictional no.) (other) (year built) d: Construction Code WE-Spec 677264 NIA N/A ANSI B31. 7 1969 H!Jiitioffi970 Add. (addenda) ' (Code Case(s)) (Code Class)

6.Section XI 1 983 _ ___.Siu.u.1!IDileW1.L=.ir__.8u.3J.-_ _ _ _ _ _ _ _ __ WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 =.;N,_,,/A=----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 NIA
  • ANSI B31.7/N E-Spec 677264 (edition) (addenda) (Code Case(s))
9. Design responsibilities -"~~"2...-----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) __N;...,_/_.._A..___ _ _ _ __
11. Description of work Replaced. valve with valve of new design.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ .............e...r........#,,..:-.-9._3....0....7...0~9....l_,_7_,5'-----------....De..-...f...i ....

___,w,......or...k~Ord c ....i ""'e._.n. _.cy*-B"'"'eqpaleAeC.Ji+.. . . _....j~*...........N;~/~A,.,___ _ _ _ _ __

D;?sjgn Change Package :ft: JE0-2309 Pkg. 1 See attached pages for Description of Replacement.

    • stem Insei:vice Test T
  • Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __

Principal Engr.

Date I- I Cf 19 *~- Signed_ _PS_E_&G __ eo_.-_Nu_c_l_ear __De_p_t_._ _

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of :MA. have inspected the repair, modification or replacement described in this report on { - // , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty,

/ /)

ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

~ xa~ory 9

Mutual Engr. Assn.

Date /- l~ , 1~. Signed tnrYV "L* ~ Commission&<t/tfi[9'L(/lJ/l MLJ 7:J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

p;;..---'"=;;;;;;;;;====;;:;;;;;;;;;;;;;;==:-....------..;;:=:==========-*------**- -----*---------

Page J _ of ....A:_

FORM NR-1 ATTACHMENT Code Job Package No.: S93-181 Work performed by: Public Service Electric & Gas Co., Nuclear Dept.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System: Safety Injection Nuclear Class: ------

I

==================================================================
  • ID of Component Replaced:

,. Name of Manufacturer:

~i~f serial No. Nat' 1. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

~- original Const. Code: Edition Addenda, Code Class f~-- Code Cases:

ID of Replacement: --=1=1=S~J_1=7~_v_a=l_v~e""----------------"-------

Name of Manufacturer: _,=E=d=w~a=r~d=-~V=a=l~v~e:;........:I=n=c=.....*~------------------

AFX-55 N/A =N~/=A'-=--- N/A 1993 Yes

~=---------...,-.,,----::~

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Replacement Const. Code: *ASME III 1989 Edition NLA_ Addenda, Code Class A._

Code Cases:N/A

  • ANSI B31.7 1969 Ed.t970 Add.
==================================================================

of Component Replaced:

of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Replacement Const. Code: Edition Addenda, Code Class _

Code Cases: - - -

======================================~===========================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

acement Const. Code: Edition Addenda Code Class Code Cases: _ __ ' -

==================================================================

- ".* ..... FORM NR*1 REPORT OF REPAIR 0 MODIFICATION$ OR INSTALLATION OF REPLACEMENT(S)

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS D

Page 1 of 2 o.rk performed by Puhl i c Service El ectri c & C..as C.O. - Nucl ear Dept. CJP =#S93- J 82

  • (name) (repair organization's P .0. no., job. no.,etc.)

Foot of Buttonwoad Roodu Hanmc'ks Bridger NJ 08038 (address)

(name)

Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 (address)

3. Name, address and identification of nuclear power plant ___S.....,al....,,em ..........Nu.,,...c,....,,l.,,.e...e...r.....,Gen~,....era:""""...,t""ing......,~...sta

.....""t""1""'o,,,,.._.n.___,U,,.m~*t=-...#c.:1,,___ _ _ _ _ __

Foot of Bnttonwoad Bnadr Han<X>Cks Bridger NT 08038

4. System Safecy Inject.ion NuclAAr Class I
5. a: Component repaired, modified or replaced _.,J,,..2.._SJ..._J._7L-V....._...a....J_,v....e..___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Name of manufacturer Roekwel 1 F'Jiwarrls c: Identifying nos. TVA TVA 1968 (mfr's. serial no.) (Narl.Bd.No.) aurisdictional no.) (other) (year built) d: Construction Code WE-Spec 677264 J\IA ANSI B31. 7 1969 MLtior1l.970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1 983 --~Si...mnneuw.i=l"'L....-'....... 83 ' - - - - - - - - - - - WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N:,_./A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31.7/N E-Spec 677264 (edition) (addenda) (Code Case(s))
9. Design responsibilities --'J.O!.IL.:l.lll!Ol..._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOF psi Code Case(s)_~J\or/~A~------
11. Description of work Replaced valve with valve of new design.

(use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: _ __,W~n~rL'k'~_,_O~rrl ......e~r._~#~*-9~2~1.....,_1~1~7~1~4~7,__ _ _ _ _ _ _ _ _ _.De .......f~1~*c......ie....._n~cy'"l'-~R~e~po~.....rt-_._~#~*____.,N¥/4A~---------

Desi..gn Change Package #: lEP--2309 Pkg. 2 See attached pages for Description of Replacement.

    • stem Inservice Test '11
  • Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19-=9'-4=---

Date /-/ y PSE&G Co. -Nuclear Dept.

19,---i.t.-. Signed_ _ _ _ _ _ _ _ _ _ _ _ ,;- </44<* dd+-4'

/J / / Principal Engr.

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co Of MA have inspected the repair, modification or replacement described in this report on /-1 , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National

~ard rules as defined in the publicati~n NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

  • ,.*:--o*,_.:.,* _C/ J ~ r- / Factory Mutual Engr. Assn.
  • Date /-)_' . 1'U...]_. Signe c. U-~- Commissions/J&f"ff$f:£'/l/,4 tJ1,?7,i
  • (Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

,. **/. ;*:>~-~~.form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229*

. :::J*:*::.~1::.\,::';::t,,:*- NB-81 Rev.6 1:_

Page ~ of ~

FORM NR-1 A'rl'ACHMENT Code Job Package No.: S93-182 Work performed by: Public Service Electric & Gas Co., Nuclear Dept.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

2. owner: Public Service Electric & Gas Co.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System: Safety Injection Nuclear Class: ~I~----
==================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class _ _

Code Cases: - - -

ID of Replacement: --=1=2=S=J~1~7.__V~a==lv--=e,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Name of Manufacturer: Edward Valve Inc.

=~~~----~'"""'-'~~~~~~~~~~~~~~~~~~~~~~

AFX-54 N/A =N~/=A;..,.-__ N/A 1993 =Y~e=s.___ _ _ _ _ _ _ __

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Replacement Const. Code: *ASME III 1989 Edition NL.A_ Addenda, Code Class .l_

Code Cases:_N_/~A~- ________________ ~~~~ ~~~~

  • ANSI B31.7 1969 Ed.1970 Add.
==================================================================

of Component Replaced:

of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year B,uilt ASME Code Stamp'd.?

Replacement Const. Code: Edition Addenda, Code Class _

Code Cases: - - -

==================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No* Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class _ _

Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

acement Const. Code: Edition Addenda, Code Class _

Code Cases: - - -

==================================================================

~----------------,--- - -----

- ...... ; - FORM NR*1 REPORT OF REPAIR D MODIFICATION ~OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of 2

ork performed by publ i c Service El ectri c & C..as Co. - Nucl ear Dept. CIP  :/tS93-183 (name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwocd Rood, Hanr.ac;ks Bridge, N.J 08038 (address)

(name)

Foot of Buttonwcxxl Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __.S..,al .....em.....,~Nu.._._,,,,,,c"'l,,,.e,,.a..,r,__,Gen=~era==t,,,ing=,__,,sta:~=t=i=o=n,___,U=m=*t~~#=l'-------

Faat of Buttonwood. Boadr Hanr.ocks Bridger N.J 08038

4. System Safety Injection Nuclear Class I
5. a: Component repaired, modified or replaced ~l..,3..,SJ ..........

l._.7_V.,._,a

...l_Vi_._,,,e,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Name of manufacturer Backwel 1 - Fdwarrls c: Identifying nos. N/A N/A N/A N/A 1968 (mfr's. serial no.) (Narl.Bd.No.) (jurisdictional no.) (other) (year built) d: Construction Code WE-Spec: 677264 N/A ANSI B31. 7 1969 MUtioaJ970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 $J TIT1IT!f>r 8 3 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N:~/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31. 7/N E-Spec 677264 (edition) (addenda) (Code Case(s))
9. Design responsibilities - " ' " " " ' " " & G " " " ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NoP psi Code Case(s)_~N~/=A=--------
11. Description of work Replaced. valve with valve of new design.

(use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: --WMo~*rkA~Ord~~e~r..._*#~*-9~2-l.l.1+7.1~4~9~~~~~~~~~-1)9&,,0;;.f_ic .......ie~nury"""i'--B~e~pa

........~rr_..__~#~*-Nu,~l~A~~~~~~~~

Design Change Package i: lE0-2309 Pkg. 3 See attached pages for Description of Replacement.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19=9-'4'----

Date / - I<( 19 ._!J_y_. Signed_ _PS_E_&G __ c_o_.-_N_u_c_l_ear _ _De_pt_.__ .....d.~'L-~""""-~:.&~~"------Pr-incipal Engr.

7 (repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / ""/J , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

/ >> Factocy Mutual Engr. Assn.

Date J- Jl, , 19qt./ . Signed ~ (. lA-v-L-- Commissions/JJ'Sf1'/ tA/A d:fJ/}

(Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The Nation al Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

~.

Page _L of _.L FORM NR-1 ATTACHMENT Code Job Package No.: S93-183 Work performed by: Public Service Electric & Gas Co., Nuclear Dept.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 owner: Public Service Electric & Gas Co.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 system: Safety Iniection Nuclear Class: ~I~~~~-

~**;1

~{' ==============================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement: _,:.1=3~S=J~1~7-'-~V~a=l~v~e::......~~~~~~~~~~~~~~--'-~~~~~~

Name of Manufacturer: Edward Valve Inc.

-=~~~~==.......,"---'~~~~~~~~~~~~~~~~~~~~~

AFX-53 N/A =N~/=A...,.___ N/A 1993 =Y~e=s"--~~~~~~~~....,,--

Serial No. Nat'l. Bd. Jurist-No. Other Year Built ASME Code Stamp'd.?

Replacement Const. Code: *ASME III 1989 Edition NLA__ Addenda, Code Class 1._

Code Cases:N/A

  • ANSI B31.7 1969 Ed.1970 Add.
==================================================================

ID of Component Replaced:

.illlllllllif of Manufacturer:

~ Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp.' d. ?

.Replacement Const. Code: Edition Addenda, Code Class _

Code Cases: - - -

========================================~=========================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

acement Const. Code: Edition Addenda, Code Class _

~=================================================================

r:;=======----*----* . -*

~ .. FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT($) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 ork performed by pnbl i c Send cp El ec+/-ri c & C'..as Co - Nuclear Dept. CIP f593-184 (name) (repair organization's P .0. no., job. no.,etc.)

Foot of Buttonw'ood Road, Hancocks Bri dgeJ NI 08038 (address)

(name)

Foot of ruttonwood. Rbad, Hancocks Eri.dqe. NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __.s..,a ....era,,.,,.,~t...inq......,~...

.......l...,em....._....Nu....,c.,..l...e,,..;:i.,....,r._,,Gen..,.,, s...,,ta......,t.,.1..,'o.,.n...___,,,U~m..,'=:t=-.....#_,.l,_________

FCXJt of Bnttanwood Road, Hanccx:ks Bridge, NT 08038

4. System Safecy Injection Nuclear Class I
5. a: Component repaired, modified or replaced _l..,4,.,S....,.J_.l_.7--'V.....a...J....y,_,._,_e,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Name of manufacturer Ro<:::krAre] l - F.dwarr'ls c: Identifying nos. NjA N,LA N/A N/A .1968 (mf~s. serial no.) (Narl.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code W E-Spec 677264 N/A N/A ANSI B31. 7 1969 flidJtio!l}970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 Srlllmler 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 583  ?{~/A...__ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31.7/.N E-Spec 677264 (edition) (addenda) (Code Case(s))
9. Design responsibilities ---1;~.:dl!l!,,;[__ _ _ _- , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s)_~N;~/=A~------
11. Description of work Repl aced valve with va]ve of new design.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current.edition.

  • Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, *, 19-=9'--'4=----

Signed_ _PSE&G _ _ _ Co.-Nuclear Dept. Principal Engr.

Date i- J 4 19,~. _______ _ _ __

7 (repair organization) (authorized representative) (title).

CERTIFICATE OF INSPECTION

_I, the undersigned, *holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /""' // , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National B d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, q //

ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

r,1, / n Factory Mutual Engr. Assn.

Date / - J.G ,1~* Signe ~~.a?'\ £:(/ '{. kM . . . . -* Commissions !i/fSf?'/ :Ct!t1 11J.f f 1}

(Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

Page _L of _L FORM NR-1 ATTACHMENT Code Job Package No.: S93-184 Work performed by: Public Service Electric & Gas Co., Nuclear Dept.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

4. system: Safety Injection Nuclear Class: --=I"--~~~-
==================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement: --=1~4=S=J~1~7""-~V~a=l~v~e:::;.,....~~~~~~~~~~~~~~~~~~~~~~

Name of Manufacturer: .....;:E~d~w~a~r=-=d~V~a~l~v~e=-=I~n~c~*~~~~~~~~~~~~~~~~~~-

AFX-52 .N/A =N~/=A.____ N/A 1993 ~Y=e=s'--------~~-

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Replacement Const. Code: *ASME III 1989 Edition NLA_ Addenda, Code Class .l_

Code Cases:N/A

  • ANSI B31.7 1969 Ed.1970 Add.
==================================================================

ID of Component Replaced:

of Manufacturer:

ial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Replacement Const. Code: Edition Addenda, Code Class _

Code Cases: - - -

==================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.?

Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist N6. Other Year Built ASME Code Stamp'd.?

acement Const. Code: Edition Addenda, Code Class _

==================================================================

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) !]'

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS f Pa e 1 o 1 ork performed by Pnblic Service Electric & Gas Co - Nucl ear Dept CJP #893-190 (name) (repair organization's P.0. no., job. no.,etc.)

Foot of Buttonwood Road, Hancxx:ks Bridge, NT 08038 (address)

(name)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ ___.S..,a ....l...em_,,._.,Nu~c....l..e,,.e,,,_r'-"Gen.,,.,.""era,,,,..,.._,,t..,ing~,,___,S""ta""""'._.t~i'°'o""n._.____,,U"'Ill...,',,__t=-..u.#-=1,___ _ _ _ _ __

Foot of l311ttonwood Road, Hanc.cx:ks Bridge, NT 08038

4. System Fuel Transfer system Nuclear Class II 5.~ Componentrepa~~.modffiedorre~aced~-~~e~l~~~~n~s~~~e~.r~~~s~~~~~B~l~~~~~F~l~~~~e~----------------

b: Name of manufacturer _ __,Wt.,.e=s.... t ...il~rXJb~...,a

....~...l:,;;:se=------------------------------------

c: Identifying nos. N/A N/A N/A NIA I 1970 (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code W E-Spec 677020 N/A N/A (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 SUmmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 N:~/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A N/A N/A
  • ¥! E-Spec 677020 (edition) (addenda) (Code Case(s))
9. Design responsibilities _..s;.:io;u:.lll.!"2-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D**pressure N,IA psi Code Case(s)_~N;'-'1--"/A~~------

Replaced blind flange on fuel transfer canal in kind from folio.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: ___......,......__...,.._......-..,..-if~__,_....,..,,,............,,......,_ _ _ _ _ _ _ _ _ _~De..,__f~J~*c .........i~e~n-cy"f--~B~e~pa .........-'fl#~*._.~~/~A~---------

........rt-Pkg. 1 NIA CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19=-9-=4_ __

,c, PSE&G Co. -Nuclear Dept. / I'/ Principal Engr.

Date i '2 - l 19,2..:l._. S i g n e d _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,dd'-4.L,, 4~

(repair organization) _. (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on '2 - , 19 '7' and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be

  • n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

/

  • Factory Mutual Engr. Assn.

Date / Z- J D , 19 q-3 . Signed ( 4rfh____- Commissions/V'/ rf'7i/ Y.-.J A A)J J 73 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l (name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Reactor Coolant Nuclear Class I 5.~ Componentrepa~ed,modffiedorre~aced~~~-7~~~a_l~v~e~-----------------------------

b: Name of manufacturer - - - = : : . u : : : u . . . i - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

c: Identifying nos. FSE-54040 NIA j

1967 (mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code W E-Spec 676258 ---~N....,1,_./A~--- WA ANSI B31. 7 1969 ti~onl970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 SI:rmmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 -=-N-/A=-=----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31. 7 JN E-Spec 676258 (edition) (addenda) (Code Case(s))
9. Design responsibilities _ , , , _ P S = E = & G ' " " ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure O **Pressure NDP psi Code Case(s)_~N,,_/~A~-----

escription of work Replaced stem.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ __,W~o~r~kA~O~n'l......,;e~r--;#~*-9~3~0u7~0A8~1uO~OU-_ _ _ _ _ _ _ _ ____._De=-..f_juc~1~*e~n r:yLJ<-~B~e~po.,,,_,_rt._._-1!'#~:----LlN;~/~A,__ _ _ _ _ _ __

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A

    • stem rnservice Test T
  • Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Qct. 3, , 19_9_4_ __

PSE&G Co.-Nuclear Dept. Principal Engr.

Date j- i l( 19,_f_£_. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co

  • of MA have inspected the repair, modification or replacement described in this report on / - I and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

n 1I ~ c::- / Facto;ry Mutual Engr. Assn.

Date /-I Y '1~. Signed ~ l

  • LY:~ CommissionsNP sfJ9t/ f./l/!I ,A.),I?Z?

(Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenu_e, Columbus, OH 43229.

NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)Jd" TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l

~rkpertormedby_~B~1~h~l~i~c.__._S~e~l'V_,.__J~*ce--.~E~l~ectr"'""" ........~ic..._~&~Ga s~Co.,,._,.'---_.Nu.__c~l=e=oa~r..__,De==iP~t~.-----"CJP==~#~S~9~3~-~1=9~3=---------

(name) (repair organization's P.O. no .. job. no .. etc.)

Foot of Buttonwood. Road. Hancc:x:::ks Bridge. N.J 08038 (address) 2.0wner_~Pub=-===l=i=c'-=S=erv~~i=ce==~E=l=ectr==-===i=c-=and=='--=Gas=='---'Co~.~-------------------------

(name)

Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of :Buttonwood Road, Hancocks Bridge, N.J 08038
4. System Reactor Coolant Nuclear Class I
5. a: Component repaired, modified or replaced ~ll'R!==6___,,V._,,hl=-Vi'-"'e=------------------------------

b: Name of manufacturer --~~~--------------------------------------

c* Identifying nos. 6381782 N/A N/A N/A 1967 (mfr's. serial no.) (Narl.Bd.No.) Ourisdictional no.) (other) (year built) d* Construction Code W E-Spec 676258 N/A N/A I ANSI B31. 7 1969 EliciitioID970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 summer s3 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83N ~/_A_ __

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31.7/N E-Spec 676258 (edition) (addenda) (Code Case(s))
9. Design responsibilities - = P S c = E = & G = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D**pressure NOP psi Code Case(s)_-"N'""/-"A~------

escription of work Replaced stern.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: __Win...o..._r_.,k.._,_O....rd_....,e.,r---:;#11'-&-:_9_,_3...L>..1.0.L.7...,0.....,8...,0c.<9.._.8'-----------~De'"""'....

f~i,.,c...

i.,,.en,,.,...cy~....

R.,,,e""'po~rt~_,#"--':"----'N,__,,/.....,A~_-------

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A

    • stern Inservice Test . Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 1994----

PSE&G Co.-Nuclear Dept. Principal Engr.

Date / - t.{ 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /- J) . 19 and state that to the best of my knowledge and belief. this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Facto:ry Mutual Engr. Assn.

t:;, {J---: /lI.DJJ Date )-/ <( , 1 A f . Signed C/- 6'--'tU!-/

(Inspector)

Commissionsfo1'/ftfV ft/A (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB*81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S),&)

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 ork performed by --=Pub=-==1=1='c=------'Sel'V=-=~1=*ce=--=El=ectr==-=1=*c=--'&=------'Gas==--'Co~.'------=Nll..o.=:c=l=-=e==e=r=---=Dept==-=-*=-----CJP~~#~S"""'9"-'3=---=2=-0=-7"--------

{name) {repair organization's P .0. no., job. no.,etc.)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

{address) 2.0wner _ _Pub __l_1_'c_Serv

___ i_ce__ E_l_ectr_ _i_c_ani _ _Ga_as __Co __

  • _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(name)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating station Unit #1 Foot of Buttonwood Road, Hanccx::ks Bridge, NJ 08038
4. System Chemical Volmre Control Nuclear Class I I 5.a:~mpoo~tre~~~.m~ffi~orre~oc~_1_1_~ __4_8_¥_hl_v_e_~ __ l_t_~-~------------------------

b: Name of manufacturer I.TI' Grinnell c: Identifying nos. 085936 N/A N/A N/A -~1=9~8~8_ _ __

{mfr's. serial no.) (Narl.Bd.No.) Uurisdictional no.) (other) {year built) d: Construction Code W E-Spec E676281 1970 N/A II ANSI B31. 7 1969 (edition) (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 --=SUnnner===-_,,8,_,,3'----------- N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N~/~Ao.___

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • ANSI B31.7~ E-Spec 676281 (edition) {addenda) (Code Case(s))
9. Design responsibilities _PS __ E&G
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _ _ N~/_A______
11. Description of work Replaced bonnet stud.

(use of additional sheet{s) or sketch{ es) is acceptable if properly identified)

12. Remarks: _ _Wo=r=k~Ord==er~~#~:~9=1=0=9=18=0=0~4,,___ _ _ _ _ _ _~I:e=f~1=*c~i,,,,,ency~'-E--~Repo""""'=rt~__.#"""':~N,,._/~A,,___ _ _ _ _ __

Desiqn Chan:Je Packaqe #: N/A Rev. N/A See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the p1:1blication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __

Date/ -

o 2- '1 19, f..7.

PSE&G Co. -Nuclear Dept.

Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Principal En3r.

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on  ! , 19 J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Factory Mutual Engr. Assn.

Date q. 7,/{ , 1ill__. SignedtVJ1\h,/

9 £.u L (Inspector)

Commissionslll/d )fqt/'!dJA &if i 23

{Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR !$] MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS f Pa e 1 o 1 orkpertormedby -~B"""lb~J........ i~c._._S~e~rv........~i~c~'P..._,E~]~ect=- .......r-iuc~&..,._~r..;:i~~s,_,,C~n......__-_~Nt~1~c~]ue~a ........r____.De-=.iP~t......_._ ___,C~TP~,__~#~S~9~3~-_..2~1~2._________

(name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwood Roadr Hancacks Bridger NI 08038 (address)

(name)

Foot of Buttonwood Road. Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __.S . . ......... ] e,...;:i...,...,r__,,Ge..,...~

a ] ....em.. ,. ._. .Nt.. . . . ,...1c... ...........

e ra .......t_1...

  • nq~___.,.S..,.ta......,t_1..,*o..,,n....__,_U.,.n...1.._t,,,,__.JJ:#_,.l~-----

Foot of BirttonwC>CX'l Road, HanCXX"!ks Bridge, NT 08038

4. System steam C..enerator Feedwater Nuclear Class II 5.~ Componentrepa~ed,modffiedorre~aced ~J~4~B-~~2~~~au]Jv~e~----------------------------

b: Name of manufacturer _ _J~c.H::wEilL------------------------------------

c: Identifying nos. PSJC-70 N/i\ ~/A 1969 (mf~spgri~ (Narl.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code 71 -61 64/70-6497 ~/A ~/A ANSI B31. 7 1969 E@lfitioi].970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 Srnmner 83 WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 ......

N;~IA......__ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
  • PS Spec 71-6164/70-6497 (edition) (addenda) (Code Case(s))
9. Design responsibilities _ _ . . . . . . . . . . , " " " " ' " ' . . . . _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure Nop psi Code Case(s) __N""-¥-/~A~------
11. Description of work }?erfonned we] d repa i rs on va]ve body.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: ~--........,,......,...,,........,>>---'TF---_..,.,...........,...,,........-...~~~~~~~~~~De._.._,f~J~*c_i~*e.n~C?;r'-'1-'-R~e~pol-"-'-:i::t: .........~#ir--*~N~,~/A<+-~~~~~~~

Bev. N;/A of Replacement. N/A

    • T
  • NOl' CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19~9~4~--

-* LLLt~

Date "'Q - l{ Li- *

  • PSE&G Co. -Nuclear Dept.

19,.f....1'.:_. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ __

Principal Engr.

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co

  • of MA have inspected the repair, modification or replacement described in this report on 2- f . 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the AS E Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore. neither the Inspector nor his employer shall be n any manner for any personal injury orzi::o erty damage~or a loss of any kind arising from or connected with this inspection.

/ c;,J / .( / /1 . , Fa~ory_Mu~ual ~- Assn.

Date ,.:, ** / . 1d:z__. Signed ~ l.

  • 4-,,t:._/' Commissions/\)ffe1'/ j ~/fl ;t/;J?J 3'

~ (Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by l?Ubl ic service Electric & Gas Co I - Nuclear Dept I CJP #S93-218

  • . (name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwood. Road, Hancocks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Residm:fl Heat Removal Nuclear Class I 5.~ Componentrepa~ed,modified~re~aced_~~-S=I=~~~--5_0_2_-_A~S~n-~~~~-----------------------

b: Name of manufacturer Paci fj c Sci entj fj c c: Identifying nos. 330 J:\IA N/A N/A __1=9~7~6~----

(mfr's. serial no.) {Nat'l.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code P8 Spec 73-6402 N/A I ANSI B31. 7 1969 F.ti<1itio!lJ970 Add. (addenda) (Code Case(s)) (Code Class)

6.Section XI 1983 Srnmner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N~/~A _ __

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1974 876 N/A
  • ASME III/ANSI B31.7 1969 F,d, 1970 Add. (edition) (addenda) (Code Case(s))
9. Design responsibilities ~PS~E=&G=---------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure N/A psi Code Case(s) __N~/_A _ _ _ _ _ __
11. Description of work Replaced snubber serial # 330 with snubber serial # 23687.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: __W~n~.._r,..,k__...O~rn~e~r-'1#....*~9~3~1~1~D~2~6=4~1_ _ _ _ _ _ _ _ _~De~f_jc_i~en~C¥.o.r--~R~e~po~rt~__.#'"""':~N;..,,/~A~--------

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A

    • vr 3 Pre-Se:rvice Terno. NIA CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __

Principal Engr.

Date / :J - 6 19, '13 . Signed_ _PSE&G eo.-Nuclear Dept.

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwriaht Mutual Iri:::;u.i;.auce Co of . MA have inspected the repair, modification or replacement described in this report on //,./ii , 19 'fJ and state thatto the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

    • . _ / / Facto:ry Mutual Engr. Assn.

Date IJ.. "'f" , 1dl__. Signed .pvzr<-?. .t*/ Z, l-oYL.

(Inspector)

Commissions/4/ /J 5'f9t./ f/f)rf /t/f" l ? J (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) )(I TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1

  • ~~~~d~-~~~~l~i~c~s~e~~~i~~~~E.l~~~~i~*c-~&~~~s~c~o~*--~N~u~c~l~e&©~r~~~p~t~*--~c~w~~t~s~9~3L-~2~2~0~----- (name) (repair organization's P .0. no., job. no.,etc.)

Foot of Buttonwcx:xi Road, Hancocks Bridge, NJ 08038 (address)

(name)

Foot of Buttonwcx:xi Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant --~S~a=l~em~~Nu~c=l=e=!a=tr~.c=Gen==era==t=ing=.:.;""-'S~ta~t=i=o=n~~U=n=i~t~.... #=1~-----

Foot of Buttonwcx:xi Road, Hancocks Bridge, NJ 08038

4. System Safety Injection Nuclear Class I
5. a: Component repaired, modified or replaced lPSISN-502 A&B, 1PS1SN503 A&B Snubbers b: Name of manufacturer Pacific Scientific c: Identifying nos. N/A N/A N/A N/A 1988 (mfr's. serial no.) (Nat'/.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code PS Spec 73-6402 N/A N-71 thru N7-l-_9~------

ANSI B31. 7 1969 l?ti}tionU-970 Add. (addenda) (Codel¢l~9ll 1/2 / N24 7 (Code Class)

6.Section XI 1983 --~SUrnme~~~r~~8~3_ _ _ _ _ _ _ _ __ NIA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N:..,.,../~A~-

(edition) N~~l, N1Q9d~s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N-71-9
  • ANSI B31. 7/PS Spec 7402 (edition) (addenda) (Code Case(s))
9. Design responsibilities __ PS_E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D *-;!pressure N/A psi Code Case(s)_~N....,,,..../~A~-----

Replaced transition tubes assemblies.

(use of additional sheet(s) or sketch(es) is acceptable if properly identified)

12. Remarks: _ ___,Wi~o=r=k'-"-O=rd~e=r~.... #~:-""'9~3~1__,,0..,,0""'6._.1....1...5"--_ _ _ _ _ _ _ _ __._De""'""f__.j~c~i~e-n~cy"",f-__.R~e....,fD~rt..__...........,:/f""*_...Nor/""'A~--------

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "N R" stamp expires Oct. 3, , 19-"-9-"4_ __

PSE&G Co.-Nuclear ~pt. Principal Engr.

Date 2. - f 19,_.tj:'._. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I

f /) ..- :2] , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

  • c: , / ~** . (,- / ,J Factory Mutual En~. Assn.

Date } - 2( , 1u.:1._. Signed~~ {.. * (.,,;.~ Commissions I]//} 5°f"?'i' J)/ A /u1 f'J?::J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

NB*81 Rev.6

FORM NR-1° REPORT OF REPAIR 0 MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) ~

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l Work performed by 'Pl Jbl j c senri ce Electric & C..as Co. - Nuclear Dept. CJP #593-221 (name) (repair organization's P.0. no., job. no.,etc.)

Foot of Buti:anwpcrl Roodq HaDCXX'!ks Bridge, NI 08038 (address)

(name)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ ___,Sal=_,,,em.....__,,Nu~c"""'l=e=>a=r"'--'Genera="-===t=rng=' "='---=sta:"-==t=i=a=n~~Uni==*""t'--"#'-=l=----------

Foot of Buttonwood Road, Hancocks Bridge, NI 08038

4. System Demin Water Nuclear Class II 5.a: Componentrepa~ed, modffiedorre~aced ~~~~~O~~~~~~~~~~~~e~-------------------------

b: Name of manufacturer - - - > 1 - 1 1 : : . . . u : : u . i - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

c: Identifying nos. ~0~2~5 ...2~---- N/A N/A 1988 (mfr's. serial no.) (Nat'l.Bd.No.) (jurisdictional no.) (other) (year built) d: Construction Code ASME Sec III 1971 1971 None (edition) (addenda) (Code Case(s)) (Code Class}

6.Section XI 1983 Smnmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83N ,,_,,/.._,,A_,,___ _

(edition) (addenda) (Code Case(s

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1971 1971 N/A
                                                                          *ASME Sec. III/B31.7 1969 Fd. 1970 Add.                                                                       (edition)                        (addenda)          (Code Case(s))
9. Design responsibilities __..L!.i!.l.dS!!iSL_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s)_~l\..,/~A~------
11. Description of work Replace bonnet boltin;J.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: --W"o ....r:.._k.,,,.....cOrd...,........,..e..._r--11#c.:~9'-'3'-"1_.1....,0.....1_.1"'2.u6'-----------De..,......_f....j ....... c i e"'"IlC¥......_.~R~epot-......_rt-......_'lf#~*__...N;r/""'A....___ _ _ _ _ __

Design OJan;Je Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __ Date Io- "J...L 19,__z:_:l__. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ PSE&G Co. -Nuclear Dept. A~~ 

                                                                                                                                                            / / /                                                       Principal E:n¥.

(repair organization) " (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on //J-' I J , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, essed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                       .                                ~                                 (""      /      II                                                    Factory Mutual En¥* Assn.

Date /0 ~].,~ .1~. Signed 71f;t) l * ~* CommissionsA//J~f9l/Ttvl/ &LJJ J 

                                                                              ~                            {Inspector)                                        (Natl.Bd.No.(inciuding endorsements)state or province and number)

This form may be obtained from The National Board of Boller and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l k performed by _Pub~~l=i~*c~S~erv~~i=*ce~~E=l=-=ectr~=i=c~&_Gas=~CO~-~-~Nu-'-="c=l=-=e=a=ir'-=De=p-=t'-=-._ _ _CJP==~#~S=-=9~3~--=2=-=2=-=5'------- (name) (repair Organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) Public Service Electric and Gas co. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Main Steam/Turl:>ine Bypass Nuclear Class II
5. ~ Componentrepa~ed, modffiedorre~aced _P_i_'p~~-~1-~ _ _2_0_0_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

b: Name of manufacturer _ __,M==-.J=--.__.Do=~l-=e=------------------------------------ c: Identifying nos. N/A N/A N/A N/A -~1=9~8~8~---- (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code ANSI B31. 7 1969 1970 N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 summer 83 N-416 (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N-416 (edition) (addenda) (Code Case(s))
8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N-416-----
                                                                          *ANSI B31. 7                                                   (edition)          (addenda)          (Code Case(s))
9. Design responsibilities - = P S = E = . : & G = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s)_~N"'"/~A~------

escription of work Replaced flange and spool, elbow and bolting in kind. (use of additional sheet(s) or sketch(es) is acceptable if properly identified)

12. Remarks: -~W~o~r~k~O~rd~e_r..._..f~:~9_2_l_2_1~6_1~5~5_ _ _ _ _ _ _ _ _ _ De~f-ic~ien~C¥-~~R~e""w~rt~__,,#,_.:~l'{,,_/~A~-------

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                      ** stem Inservice Leak Test                                                T
  • Nor '"'

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __ 9 PSE&G Co. -Nuclear Dept. Principal Engr. Date -? *- ( 19, 1 f, 7' . Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance CO of MA have inspected the repair, modification or replacement described in this report on J ,.,7 , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                             .                    ~               / I n                                                             Factory.. Mutual Engr. Assn.

Date_f-~2--~-* 1d.!l_. Signed/J1U:,/ 'z. ~ Commissions;u'/{jr/£/J.V;.J /J,17/J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) B TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by --=Pub-==l=i=c'---=S-=erv~-=i=ce"-=--=E=l=ectr=c:=-=i=c"-"&=-=Gas='----"C=o=._---=-N=u=c=l=e=!a=tr'---'=De=p=t=*--~GJP==~#-=S=9-=3'---=2=2=6=------- (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hanccx::ks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ _ _ __N_u_c_l_e_a_tr_Gen_--'era:=..;"'t-=-=ing-~S'--ta"-=t-=-=i'-"o~n~_U_n-"'i'-"t___,#'"'1"'--------

S__,a_l_em Foot of-Buttonwood Road, Hancocks Bridge, NJ 08038

4. System Main Steam Nuclear Class II 5.a: Componentrepa~ed,modffiedorre~aced_~~a=l~v'--e_1~~~~1~7'--1~----------------------------

b: Name of manufacturer -~~~~~------------------------------------~ Fisher c: Identifying nos. 5725449 N/A N/A N/A 1975 (mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code ASME Sec. III 19~7~1~_....S,,_/~1~9~7~2~- N/A (edition) (addenda) (Code Case(s}) (Code Class)

6. Section XI 1983 Summer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N~/=A~~-

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1971 S/72 N/A
                                                                                  *ASME Sec. III                                               (edition)               (addenda)         (Code Case(s})
9. Design responsibilities _PS_E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s)_~N~/A=-=--------

escription of work Replaced plug and stem assembly in kind. (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: __Wi.._,_,,.o~r~k.__,.O~rd""""e~r--+#µ:.__9~3~1~1~1""""""6~0~0=4_ _ _ _ _ _ _ _ ___.De~f.........cic...._._je....._.n~cy"l'-~R~e~po.o..u.r+/-__.__~#~:.__.N,~/~Au.___ _ _ _ _ _ __ Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                      **S stem Inse:r:vice Test                                                           T
  • Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4_ __ PSE&G Co.-Nuclear Dept. Principal Engr. Date J- lf 19,_f_!f_. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) * (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht :Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I*' i , 19 'J l and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ti c; L( /l * {. 1 Factory :Mutual Engr. Assn. Date /- / f , 19_/_. Signew~* t . l-<> 3( Commission~J.67 (<(ttl( T/Ll' fl &-Fl l2 

                                             . 7                           (Inspector)                                        (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev 6

FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) ~ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1

  • k performed by _------'Pub=--==1=1=* c"---"S"-'erv:=...o-=i=ce=-=E=l=ectr=-==ic~=&-Ga=s=---Co=.,___---=-Nu=c=l=ea=tr=--=De=:Pi::ot=..:....

(name) _ _ _CJP=-'=- -#~S=-=9'" 3,_-_,2=2'- '7_ _ _ __ (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Reactor Coolant Nuclear Class I
  ~a: Componentrepa~ed, modffiedorre~aced                            ~l~C~-~~~~-~~-O_l_O~S~n_ub~~~~-----------------------

b: Name of manufacturer Pacific Scientific c: Identifying nos. 25784 N/A N/A N/A 1976 (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code ASME III NF 1974 W76 1644-1.1644-5~-~l=------ ANSI B31. 7 1969 ~n)l970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 --~Smmner~=~~8=3~--------- N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 _N"--'/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *197 4 S70 1644-4
                                                              *ASME III/ANSI B31. 7 1969 Ed. 1970 Add. (edition)                                                                   (addenda)                  (Code Case(s))
9. Design responsibilities __ PS_E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure O *""Pressure N/A psi Code Case(s) _ __,N~/'""'A'-"------

escription of work Replaced snubber serial #25784 with snubber serial #27164. (use of additional sheet(s) or sketch(es) is acceptable if properly identified)

12. Remarks: _ ___,_W"'"""o=r=k=--=O=rd=er~..,..#..o..:-=-9=3=11=0=2,,,_0~4.....,l,,,,___ _ _ _ _ _ _ _~De~f""'1*c~i..,'en,,,,..,,cy~.....R~e"J!po"""""'rt......,.___,,:/f'--":__,,,.SMD
                                                                                                                                                                                  .......'---""9....

3_-.... 3 .... 1 ... l _ _ __ Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4_ _ Date _ 

        /- cl,            9 L.I Signed________________

19,__f__L_. PSE&G co.-Nuclear Dept. ---c__//~ ~ _ 

                                                                                                                                                                         ~cipal _Engr.

(repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / - and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. _j , ; ~ < / Fgctory Mutual Engr. Assn. Date /-/71 , 1&__. Signed -u,...../ (_,, UJ_ Commissions N'.6 '6'S [tf £1.!#/ A.)]) 7 J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)~ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l orkpertormedby -~J?r::.uJll>ul~i~c--"s~e=~.L..lol~i~c~a"-JE~l~ecti=.. 

                                                                            ......r_juc...._,&.,._~~~~~s.__.c~:o......._.---=-:.......L.Nt.....,1c_l..u::;e~a~r__.ne......,p~t......_._ ___,CJP.....,...._~#PS~9.L,J.3_-~2~2~8L-_ _ _ _ __

(name) (repair organization's P.O. no., job. no.,etc.) Foot of Fl!rt+/-onwocrl Road, Hanmcks Bridge, NI 08038 (address) (name) Foot of Buttonwood Road. Hancocks Bridge, NT 08038 (address)

3. Name, address and identification of nuclear power plant ----'8allOl!Ol..semOlll....1Nu"3.Mboc..iol.se2oa.l,jr1.......:Gen~;usera:;;.r...sO!.,t~ID;J~'---"Sl.!ta~t!.<1~*

0 ~a~n!..._...!U~m!_!,!,',.!ot'-...l#r..,l=--------- Foat of B11ttonwood Road, Hanmcks Bridge; NI 08038

4. System Steam C"-.enerator Feedwat.er Nuclear Class I 5.~ Componentrepa~ed,modmedorre~~ed_J~s~-~1-3u~~-~~~~0~1~7~B~~~~1~b~~~~--------~--------------

b: Name of manufacturer Pacific Scienti fie c: Identifying nos. 445 N/A N/A N/A 1976 (mfr's. serial no.) (Narl.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code PS Spec 73-6402 N/ll 1644-4 ASME I I I 74 W75, MS! B31. 7 1969 M.en<!J!970 Add. (Code Case(s)) (Code Class)

6. Section XI 1983 _ __.$1"1UJlDllTl8ww r___._8.._3,___ _ _ _ _ _ _ __
                                                                                                                       ......                                                                                                    WA (edition)                                                                             (addenda)                                                                              (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 =.N...,,/A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *197 4 S76 164=4~-~4~--
                                                        *ASME III/ANSI B31. 7 1969 Fd. 1970 Add. (edition)                                                                                                   (addenda)             (Code Case(s))
9. Design responsibilities --'~~!Ol...----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure N/A psi Code Case(s)_~~.,.l~A..,__ _ _ _ __
11. Description of work Repl ac.ed snubber serial # 445 with snubber serial # 27629.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) See attached pages N/A 

                       **VI'3      Presei:vice CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB* 102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19-=9'-'4=---- PSE&G Co. -Nuclear Dept. t1 / / Principal Engr. Date I 2

  • 9 19,_ll_. Signed*-------------.,,44¢1tu&~L 1 (repair organization) (authorized representative) (title)

CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on //' C . and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, *modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                      '                 C /                                                                                                        Facto:cy Mutual Engr. Assn.

Date / 2..-</ , 19Cj3 . Signed ~ z., (ddL-- CommissionsAlb'JffY ]:/(} /.J A).:J'J7 J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) @' TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ark performed by 'Blbl ic Senrice Electric & Gas Co. - Nuclear Dept. CJP #893-229 (name) (repair organization's P.O. no., job. no.,etc.) Foot of :suttonwcx:xi Road, Hancocks Bridge. N.J 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 (address)

3. Name, address and identification of nuclear power plant --~S~al=em=~Nu=c=l=e=oa=ir=---=Gen==era===t-=ing=='-"S~ta=t-=i=o=n~_U~m=*~t_#"'-1"'-------

Foot of Buttonwood Road. Hancocks Bridge, N.J 08038

4. System Reactor Coolant Nuclear Class I 5.a: Componentrepa~ed,modffiedorre~~ed ~l=C=-~~~~-~1=6=2~S~n=~~~~-------------------------

b: Name of manufacturer Paci fj c Sci entj fj c c: Identifying nos. l l l NjA N/A 1968 (mfr's. serial no.) (Narl.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code PS Spec 73-6402 N,IA 1644-4 1979 ASME III 1974 W7~}~I B31. 7 1969afhlall970 Add. (Code Case(s)) (Code Class)

6. Section XI J 983 _ __..Sl.........,mnneww r.........._8,__3..___ _ _ _ _ _ _ __
                                                                                                                                   ......                                                                                              N/A (edition)                                                                                 (addenda)                                                                               (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 ~N"--/A~--

(edition) (addenda) 16Sliiie Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1974 _W7~5~_ 1644-4
                                                                                                         *ASME III                                                                  (edition)                       (addenda)           (Code Case(s))
9. Design responsibilities ~PS~=E=&G~----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure O **Pressure N/A psi Code Case(s)_~N+-/-=-A=--------
11. Description of work Replaced snubber serial #11 with snubber serial # 3903.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 3c..LJ_.J_._D....2...,,,0=4"-'J.___ _ _ _ _ _ _ _ _....,De,,_.,f__.j_..c.....i.....e...n.....cy..q,.......R...,e-ipo"""""'rt._._--"'j~:__..,"N,~l.....A.___ _ _ _ _ _ __

12. Remarks: _ __.W.....a.....,r'-'k~O~n'l~e-r,__'lf':/f~:___.9....

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                          **VI'3 Pre-se:rvice                                                                                         TeITID.              N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3 1 , 19_9_4_ __ PSE&G Co. -Nuclear Dept. ~~~~ Date .J 1- - b 19,~. 3 Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -~~~""'""~""-~"'~-=-==-""----- (repair organization) (authorized representative) Principal Engr. (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / /-1 t; , 19 <;} and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the ~epair, modification or replacement describ~d in t~i~ report. Furthermore, n:ithe: the Inspector nor his employer shall be any manner for any personal 1niury or property damage or a loss of any kind arising from or connected with this inspection. 

*                                                                                                      - /                                                                  Facto:ry Mutual Engr. Assn.

Date ) 2- - r ' g_j_]__, 1 Signed ~ { l~ Commissions /V 8 rrq t/ :ftt)tf M -r?? J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

FORM NR-1.REPORT OF REPAIR ~ MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S} 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l orkperformedby BJblic Service Electric & C'--35 CO. - Nuclear Dept. CJP #893-233 (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge. NJ 08038 (address) (name) Foot of :Buttonwood. Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating station Unit #1 Foot of Buttonwood Roa.d, Hancocks Bridge, NJ 08038
4. System Majn steam Nuclear Class I I
5. a: Component repaired, modified or replaced ~1.,,4MS-==1'-"'6=9__,,,$tm'-=-"'po=rt"-=---------------------------

b: Name of manufacturer Fi sher Valve - J?SE&G Support c: Identifying nos. None None 1972 (mfr's. serial no.) (Nafl.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code J?SE&G Spec 69-644"'5..___.....N;..,/'""'A~--- None II ANSI B31. 7 1969 ElicUtio!IJ970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 _ __.$1 nnme
                                                                                                    .................r..__.....a.....3..__ _ _ _ _ _ _ __                                                WA (edition)                                                                       (addenda)                                                                  (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N=./<-=A=----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                                          *ANSI B31.7/PSE&G Spec 69-6445                                                       (edition)                   (addenda)       (Code Case(s))
9. Design responsibilities - - = P S E = = & G = = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D ** pressure WA psi Code Case(s)_-=N=o=n=e=------
11. Description of work Removal of SUJ;)port for valve disassembly an:i ins,pect.ion - rewelded (use of additional sheet(s) or sketch( es) is acceptable if properly identified) a of valve.

12.Remarks: __Wi......,a~r~k......,.,O~n'l.....,..e~r,__~#~*__.9~3~1~1u0~4~0~0~8.___ _ _ _ _ _ _ _ ___.J)e...o;;;;.f~i~cui~e.ncy.......,~R~e~po~~rt .........~!µ:._.N~o~nue....__ _ _ _ _ _ __ Design Change Package #: None Rev. None See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4_ __ PSE&G Co. -Nuclear Dept. / / / *- Principal Engr. Date //

  • 2- L.. 19,1L_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 44.¢w~

(repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /0 -1.5 , 19'7.S and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore,* neither the Inspector nor his employer shall be any manner for any personal injury or prope~da a loss of any kind arising from or connected with this inspection. Factory Mutual Engr. Assn. Date /~OJ , 19 CfJ . Signed ~ Commissions ~ 2. 0 S'Z:, .J1 ,g (' / ~ A.J..T ~J/ 

                                                       *                       (Inspector)                                                     (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) Bl TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS f Pa e 1 o 1 ark performed by B1hl j c Send cp El ec+/-ri c & C'-.as Co - Nuclear Dept. GIP #593-238

  • (name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwood Road, Hancocks Bridge, NI 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NI 08038
4. System Residual Heat Removal Nuclear Class I I 5.~ Compoo~tre~~d.m~ffi~orre~oc~_l~2~~~1~8~¥~a~.l~v~e~-----------------------------

b: Name of manufacturer _ _.._._..,.,_..........__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ c: Identifying nos. 11319 Nil>, I JVA JVA 1988 (mfr's. serial no.) (Na!'l.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code WE-Spec 676368 JVA ~/A ANSI B31. 7 1969 E@l!itiof1970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 S!mnrer 83 WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 =.;N_/A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                                                         *ANSI B31. 7           fi-1  E-Spec            676368                    (edition)           (addenda)          (Code Case(s))
9. D~sign responsibilities _,1;:,;;!,g,g~----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NGP psi Code Case(s)_~~~/A~------
11. Description of work Replaced flange to valve OOlting.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ __,w~a~r~k~_._Oun'l...u.ie:r,__~#~*-.:9~2~1.........,n~n~5~1~1~7,___ _ _ _ _ _ _ _ _ _~De-=-f~1~*c ........i~e~n~cy4--~R~e~po1-A-urt-__.__~#~*-'-'N~/~A"---------- Design Change Package #: N/A Rev. NIA See . attached. pages for Description of Replacement. N/A 

                         **    stem Insenrice Test                                                              T
  • Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19-"9'-'4::.....___ PSE&G Co. -Nuclear Dept. ~ / ; Principal Engr. Date / / - J 6 19, Y3 . Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ _, ~,.Lr)_L,_., (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on , 19 Cj7 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. r--- /- Facto:ry Mutual Engr. Assn. Date //- J_ 1 ,1g__:f}_. Signed tAz/ 2* Llr-tk Commissiomi\/d)f'.W Zo/l AJJ773 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)~ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 orkperformedby Blhl ic Service Electric & r..as Co. - Nuclear Dept. CJP jS93-240 (name) (repair organization's P.0. no., job. no.,etc.) (address) (name) Foot of Buttonwood Roa.d, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __.S..,a..,l.,.em...._....Nu.....,c""l ...e..,e......,r_,,Gen,,.,....,era,.,,.,_....,.t...ing""-"':1--1S....ta:.....,...,,t..,j.,,a....n.....__U,,.,.._ru;.,,'b..!t.._#:u:.=l'---------

Foot of B!rtt.onwood Road, Hanc:ocks Bridge, NJ 08038

4. System CompoDPnt Conlin;J Nuclear Class II
5. a: Component repaired, modified or replaced ~1..,cc_... 1,,.8._.7-'V....hl ....e - ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
                                                                                .....Vi b: Name of manufacturer               Anchor Dar] i ng c: Identifying nos. 1156669                         WA                                                                                                                                                                   1970 (mfr's. serial no.)          (Narl.Bd.No.)                       Gurisdictional no.)                                                      (other)                                                          (year built) d: Construction Code        W E-Spec 676258                                                                                                                 WA ANSI B31. 7 1969               ~tio!IJ970     Add.               (addenda)                                                                     (Code Case(s))                                                        (Code Class)
6. Section XI 1983 _ __,$1_....IIIDI!E?wu=-r__.8....3..____________ WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 .._,,N/.._..A.....__ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                                          *ANSI B31.7/N E-Spec 676258                                                                              (edition)                           (addenda)             (Code Case(s))
9. Design responsibilities ---':.o!.l~.z._----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NDP psi Code Case(s)_~N;..,,/""'A~------
11. Description of work Replace valve bolting.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ _...Wi_n~r~k..._..Orr] 

                                .......Me_r.__~#-*__.9~3~0A6~2~8~0.......,6~0~---------~De--f~1~*c                                          .........ie   n_'¥':i'-~B~e~pa,......rt:~-'ff#~=~N;¥/~A~--------

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19""'9-'4'----- PSE&G Co. -Nuclear Dept. # / / Principal Engr. Date (1- -13 19,___u_. S i g n e d _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4/7~.A,,"--:--4--- (repair organization) *..,, (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on i "]. - 7 , 19 'TS and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                       ~  , / c-"\                                                                                                       Facto:cy Mutual ErJgr. Assn.

Date I A- I'( '19.-1-3-. Signed h s~ Commissions & Z..o5~ Jt.) 1l.3S ( .s .u.J~J / (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) 

                                                                                                                                                                                                                                                                     . t' This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 4322_9'. ..- . :./.
                                                                                                                                                                                                                                                          ' .
  • NB-81.** .
                                                                                                                                                                                                                                                         .'* **.Rev.&

FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) 111 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS l f Pae o 1 rkperlormedby_~B~Jb~l........ i~c....... s_e~rv_..__i...ce---E...._l~ect .......wr~i~c..__,&..._G~.;a~-s~Cn-~-~----Nl~1c_l_e ~-r~De"""".lpt,......~.~~---"CJP~..........#~S~9~3,-_2.._.4~1.__~~~~- (name) (repair organization's P.O. no., job. no.,etc.) Foot of ButtoDWrl<"rl Road, Hancocks Bridge, N1 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridqe. N1 08038 (address)

3. Name, address and identification of nuclear power plant _ __...S.u:;a._J..,em...,._NJu..i.1,.,,c...,l.,.e.. .......""'""""t......,i..ng~~sta.u..
                                                                                                                                                  -a..,r'--'Genera;""""                        .......t ,..i.,,,o..n,,___,U...m.....,'~t,__,#i:,,l=-------

FCX>t of Buttonwocxj Brad, Hancxx:ks Bridge, N1 08038

4. System Reactor Cool ant Nuclear Class II
5. a: Component repaired, modified or replaced -.iu~""-----------------------------------

b: Name of manufacturer --""A...l ....~"'Pm ....a.......J..,w...n....rt._....b....,_______________________________ 

                                                       ........_._D...i_.v.......,/'""C c: Identifying nos. 70/A627-3                                         N/A                                                                                                            N/A                                       1987 (mfr's. serial no.)                        (Nat'l.Bd.No.)                                           Uurisdictional no.)                                 (other)                                                (year built) d: Construction Code        ANSI B31 . 7 1969                                                                N/A                                                           N/A (edition)                                                     (addenda)                                                         (Code Case(s))                                              (Code Class)
6. Section XI 1983 __.._$1...11llJDE? 8-..3.___________
                                                                                                                                  .......,...r~...                                                                                            N/A (edition)                                                                                             (addenda)                                                                                 (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 """"N;~/A......___ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made:
                                                                                                        *ANSI B31.7
                                                                                                                                                                                             *1969 (edition)

N/A (addenda) NIA (Code Case(s))

9. Design responsibilities -~.&.;IW=-----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure O **pressure NjA psi Code Case(s) _ _:t{¥/~A _______

escription of work Replaced. bolti..ng and nuts in kind. (use of additional sheet(s) or sketch( es) is acceptable if properly identified) CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19-'9"-4-=---- Date j - I L(

  • PSE&G Co.-Nuclear 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ __

Dept. Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwr:L t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I -1J , 19q and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ("/ a,/ ~ .C- / .. ~ Jact:o:ry Mutual Engr. Assn. Date /- ( L , 1U1__. Signeduy-= z:.., ~ Commissions ;J rb-1'/ Ij/)/f 1l) ::J3 2 -? (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)Kl TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l kpertormedby_~J?!"""ft>~l~i~c.........S~e....._rv....._.j~c~~=-E.i.;u.l~ec+/- 

                                                                                  ......~r~1~*c...._~&_,.C...::1~~s"'-'C~:n~~---__.N!~1c~l~e~aur__.De~p~~~~----C..,...TP.a..-~#~S~9......,3~-~2~4~9..__ _ _ _ __

(name) (repair organization's P.0. no., job. no.,etc.) FCX>t of Buttonwood Road: HaD<X>c:ks Bddge, NI 08038 (address) (name) Foot of Buttonwood. Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ __,S""al_em""""--"'Nu=c=l=e=a=r,,__Gen==era=..,ting=='="'"""S~ta=t=i=o"'-n=---__,U=<=m='t=-.u.#-=1,___ _ _ _ __

Foot of Bl:rtt:onwocrl Road: Hancocks Bridge, NI 08038

4. System Residual Heat Removal Nuclear Class I
5. a: Component repaired, modified or replaced _1'"'4.... RH2-....7 ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

b: Name of manufacturer Anchor Dar] ing valve c: Identifying nos. None A:va j l abl e N/A 1968 (mfr's. serial no.) (Narl.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code W E-Spec 676241 WA (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 $1 IIIIIDPr 83 WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 ""-11'{,_,/A..,,__ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A N/A N/A
                                                                                           *~     E-Spec           676241                                     (edition)              (addenda)           (Code Case(s))
9. Design responsibilities --""-l.l.~=-----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure WA psi Code Case(s)_~N~/~A~-----

Replace (16) studs in kind from folio. (use of additional sheet(s) or sketch(es) is acceptable if properly identified) CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19""'9-'4~-- Date J - I'-( PSE&G Co.-Nuclear Dept. 19,---2..L. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ __ Principal Engr. p (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co . of MA have inspected the repair, modification or replacement described in this report on / - J/ ,1 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. r.i, I ~ / / fR-~ory Mutual Engr. Assn. Iy ' 1~. S i g n e d

  • t . h / ' z_,

11 *** Date / ,- Uv"-- Commissions Nb" J 't9'/ j:,,.J/I /l)Jf7} (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boller and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)El' TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l rk performed by _.....1Pub;:..ld,l,.l.lluj..,,c,,_,,S,,,;erv.,.__,"-1..,*ce""""'-___..E..,l..,ectr"""'"' ......1..,'c..___.&'"'---"Gas"""""-'CO"""'----_J,Nu..,,.,,,c,,,,l..,,e,,.,e,,,r,,__,,De~pt,,_,,,_,*.___~CJP"""",___,#~S"""9""3!_-~2,,,,5~0!___ _ _ __ (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) 2.owner_-=Pubc-==l=i=c~serv~'°--'-'1=*ce==~El===ectr====i=c'--=and==~Gas===-CO~~*-------------------------- (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Safety Injection Nuclear Class I 5.~ Compoo~tre~~~.m~ifi~orre~oc~~1=2=~~5=5=-~~~~v~e=-----------------------------

b: Name of manufacturer Anchor Darlinq c: Identifying nos. 11542-10-61 N/A N/A N/A 1971 (mfr's. serial no.) (Narl.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code W E-Spec G67624 .... l _ _ _""N;.,_/_..A..___ __ N/A ANSI B31. 7 1969 :Hkiilion1970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 Summer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 ~N~/=A'----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                                                                                                      *ANSI B31. 7 fi-1 E-Spec G676241 (edition)                                                                                                      (addenda)        (Code Case(s))
9. Design responsibilities - - - = P S = - = E = & G = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _ _ N~/_A______

escription of work Replaced valve bolting. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ __i:Wi.,,.o.....r_.k"--'Qrr].LL.l.....e;:;. r1.. . . . . :=1f, .__,_:----..1.9..... o"'2......o,_,7_,,4.___ _ _ _ _ _ _ _ _.....

3_..J_....o.... IA= f ....i ....c.....i....e....n....cyq-_..R.,.e-;1po:""'-rt.......__:jf,,.__,_:-N;u.r/A~-------- Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                        ** stem Inservice Test                                                                                                                               T
  • Nor CERTIRCATEOFCOMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __ Date /-Ii( 4 C/ 19,_L____,L_. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ PSE&G co. -Nuclear Dept. Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by Arkwri t Mutual Insurance CO of MA have inspected the repair, modification or replacement described in this report on / *- // , 19 CJ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                                                                                                        /                                                                                                       Factory Mutual En9!". Assn.

Date /-/<{ , 1 M . S i g n e d : u , / ( *. L.r!-= Commissions/l/G f'fCJ'L°£v'fl ///JJ}J 

                                                                                           *                                (Inspector)                                                                              (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

~*.

  • FORM NR*1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT($) )ZJ'
              * * *-              TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 ork pertonned by -.,1J;!l~l.Jb.wolwib4'c~Sel40~u:?wn.Y*~ce;s-,l!El~ect:~c;:"'""i~c'--ef&-'Gas""'°~o..1oo~*.--=-"--*'Nlll01Jil!..C~l,4;;:e:Gru:*--"'De1.:pJ.Jt:-.......----1CJ   ....~~i<-1#~s~9J...;3~-""2;..;;5µ,i4,___ _ _ __

(name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood :Read, Hancocks Bridge, W 08038 (address) (name) Foat of Buttonwoo:i Road, Hanox:ks Bridge, NT 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear GeneJ:ating station Upjt ;jfJ Foot of Buttonwood Road, Hancocks Bridge, ID oso::rn
4. System Reactor Coolant Nuclear Class I
5. a: Component repaired, modified or replaced P..ressurizer - Manwa.y Cover - lRCElO b: Nameofmanufacrumr_-¥¥~les~~&11~*ngh~Ql=l~01~i::is1SEe~----------'-------------------------

c: Identifying nos. 1011 i8-7 N/A N/A 1970 (mfr's. serial no.) (Narl.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code AS.ME III 19i5 Wl9i5 N/A ANSI B31. 7 1969 FA!~itio;f.970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUmmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 N/A (edition) (addenda) (Code Case(s))
8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *See Attachment (edition) (addenda) (Code Case(s))
9. Design responsibilities _.~..,...;z.._----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure NOP psi Code Case(s) _ _,J>,..,i,,...,1A...,___ _ _ _ __
11. Description of work Replaced pressurizer marnray cover and bolting (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oc+/-. 3 1 , 19q_,_=4_ __ Date I - I If 19 ,-2.._L. Signed_ _ PS_E_&G __ eo_._-Nu_c_l_ear _ _De_p_t_._ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of of MA New Jersey and employed by have inspected the repair, modification or replacement described in this report on Arkwri gbt Mubml Insurance 

                                                                                                                                                                            / -  II            , 19 1f'f,           and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Dale (- l L{ , 1f! </ . SlgoOO qd<J>i4/. 

                                                       ~

{. (Inspector) a C-Omm1,,1oo#l!tfit;/:J'lJv!fJJ" /Assn. (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

Page _L of _L FORM NR-1 ATTACHMENT Code Job Package No.: S93-254 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System: Reactor Coolant Nuclear Class: 1 ~~----

==================================================================

ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: Pressurizer Manway Cover Name of Manufacturer: _,._W~e~s_t_i~*n~g_h~o~u=s~e~~--------------------- C42744 N/A N/A =N~/=A,__ 1987 =N=o;.___ _ _ _ _ _ _ _~ Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ASME III 1983 Edition S83_ Addenda, Code Class .l_ Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add.

==================================================================

of Component Replaced: of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Starnp'd.? Replacement Const. Code: Edition Addenda, Code Class _ Code Cases: - - -

=====~==========================================================~=

ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code starnp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: Name of Manufacturer: Nat'l. Bd. Jurist No. Other Year Built ASME Code Starnp'd.? acement Const. Code: Edition Addenda, Code Class _ 

                         --------~-

Code Cases: - - -

==================================================================

FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) lEJ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS ark performed by PIIDlic Sm:vice Electric & Gas Co. - Nuclear Dept. CJP #S93 260 (name) (repair organization's P.0. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, m 08038 (address)

2. Owner Public Service Electric anC! Gas Co.

{name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 {address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Upjt #J Foot of Buttonwood Road, Hancocks Bridge, ID 08038
4. System Reactor Coolant N'11clear Class II
5. a: Component repaired, modified or replaced Pressurizer Relief Tank-Flanges-lRCEll b: Name of manu~acturer --'lwi/<f=='es~t,,.iJOfngh-kHcfl9C=JUStfht:C!-----------------------------------

c: Identifying nos. Ir-10662 61420 N/A N/A 1969 {mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) {other) {year built) d: Construction Code ASME III 1968 N/A N/A (G) 2 ANSI B31. 7 1969 F.cfl.ditis_~70 Add. (addenda) (Code Case(s)) {Code Class)

6. Section XI 1983 N/A

{edition) (addenda) {Code Case(s))

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 N,rl=A---

(edition) (addendaJ (Code Case{s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1989 89 NIA
                                                      *ASME III/ANSI B31. 7                   1969       Ed. 1970      Add.          (edition)           (addenda)          {bode Case{s))
9. Design responsibilities -E>~oo..,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure °** pressure NOP psi Code Case(s)_N..,,.,+l~A-----------
11. Description of work Replace pressurizer :r:elief tank rupture disc flanges -vrith upgraded (use of additional sheet(s) or sketch{ es) is acceptable if properly identified)

NIA I CERTIFICATE OF COMPLIANCE We certify that the statements made ,in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct 31 , 1~-=4~-- Date  !- I 4 19 ,--2._L. Signed _ _PS_E_&G __c_o_._-_N_u_c_l_ear __ De_p_t_._ _ Principal Engr. 

                                                                                                               ?

(repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New .Jersey and employed by _ _ _--L:l~Ulll..1~4LJJL-..JL!!U..1.U1C....1-LI..Ji::u..L.LLl......._....._-"'4"'-7-l---------- ot MA have inspected the repair, modification or replacement described in this repart*an and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Bciard rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 

                            /,I , I Date~/_....~/~?__ , 1u.i__. Signed~

i* /' any manner tor any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                                'L* ~

I 11 (Inspector) CommissionsN[frCjl/

i;;as:::t;o:cyJ1q.tual Engr..., . Assn.

WI/ Jl,t[f/} (Natl.Bd.No.{including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR*1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)fe:j TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by ---=Pub-==l=i=c'--=S=erv~-=i=ce'-=---=E=l=ectr===i=c'--"&,__,,Gas=~Co=._--=Nu==c=l=e=a=tr'--=De'=.l:'p-=t=*------=CJP=-==____..#_,,,S=9-=3'---=2=6=2,___ _ __ (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwocx:l Road, Hancocks Bridge, NJ. 08038 (address) (name) Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generatirig Station Unit #1 Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038
4. System Reactor Coolant Nuclear Class I 5.~ Componemrepa~ed,modffiedmre~~ed __ #_1_4_._S_~---~ __ era

__t_o_r_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ b: Name of manufacturer Westinghouse c: Identifying nos. 1203 68-51 N/A 1971 (mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code ASME Sec. III 196=5_ _~S,..../_,,,1=9-=6=6,___ N/A (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrrnner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 _N=---/~A~_

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1965 S66 N/A
                                                                                           *ASME Sec. III                                                  (edition)            (addenda)         (Code Case(s))
9. Design responsibilities __PSE __&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D *l'fressure N/A psi Code Case(s) _ _=N,,./~A~-----

Replace (1) bolt in kind from folio on #14 Steam Generator (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ __,W_,_,,o=r=k"--"'O=rd=er=--.....
                                               #_._:---=9=3_,.,1"""'1"""0""'5=-0=33..___ _ _ _ _ _ _ _ _De                 __f.._1.,..'c..... en~cy."'r--~R~e~po 1...,'           .........rt~....,#~:~~or-/~A~-------

Desiqn Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                       **     stem        Inservice Test                               @NOP or CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_~ 4 v PSE&G Co. -Nuclear Dept. / / /

  • Principal Engr.

Date I - J Cf 19,_L_f-* Signed_ _ _ _ _ _ _ _ _ _ ~ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /~ II ' 19 L and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. C / F~~o:cy )1utual ~. Assn. Date /-J.Y- '1,jL. Signed~ c.. C/-vk Commissions tJfi:I.r'i tf .J.AIA ;JJ} n 

                                                   ,.                            (Inspector)                                            (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 rk performed by Public Service Electric & Gas CO. - Nuclear Dept. CJP #893-266

  • (name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) Public Service Electric and Gas Co. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Reactor Coolant Nuclear Class I I 5.~ Componentrepa~ed,modffiedorre~aced_1_~ __8_1_-_¥_~_v_e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Name of manufacturer _ _. . . . : A l = = - = O ' - L - - ' C O = = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - c: Identifying nos. 70/A627-3 N/A N/A N/A 1970 (rnfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code WE-Spec G-67624~1~-~R~e~'V~*~l_ _ N/A II ANSI B31. 7 1969 ~i6lnJl970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrmner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 _N~/_A_ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                         *ANSI B31. 7/rg_ E-Spec G-67624 Rev. 1 (edition)                                                (addenda)         (Code Case(s))
9. Design responsibilities __PS_E_&G _________________________________________
10. Tests conducted: hydrostatic D pneumatic D design pressure D *'f;ressure NOP psi Code Case(s) _ _N~/_A_ _ _ _ __
11. Description of work Replace valve disc.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: ------'-W'-'o=r=k"-----"O=ro'-"=er=---"#--'-:-=9=3=1=1=1=5=1=85=-----------De==f1='c=1=*en=cy~~R=e,,,,po=rt~...,,#~:~N~/,,,..A,___ _ _ _ _ __

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                        **system Inse:rvice Test                                                 Temp. Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires oct. 3, , 19'-._9_4_ _ PSE&G Co. -Nuclear Dept. / / / Principal Engr. Date__ /_-_i~t__ 19,~. Signed_ _ _ _ _ _ _ _ _ _ _- ' - - - - - * ' 44di-n~' (repair organization) (authorized representative) (title). CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Cq of MA have inspected the repair, modification or replacement described in this report on I - I/ , 19 q L/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                                             /                                                   Factory Mutual Engr. Assn.

Date /-1 { , 1~. Signed/.vrl1J.v: (. C..~ Commissions/'Jfitrc/t./ fl///1 NJ~i) J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure V.essel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ~ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1 rk performed by Public Service Electric & Gas CO. - Nuclear Dept. ClP #S93-270 (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Han.cocks Bridge, NJ 08038 (address)

2. Owner Pnblic Service Electric am Gas Co.

(name) Foot of Bnttonwcxxi Road, HanCJJCks Bridge, NI 08038 (address)

3. Name, address and identification of nuclear power plant Salem NJ1cl ear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Main Steam Ni1clear Cl ass TT 5.~ Componentrap~red,modffiedorre~aced~l~~~M~S.1~5~'z~a~l~'µre~-----------------------------

b: Name of manufacturer ----C~;}S]gy:...______________________________________ c: Identifying nos. N55100-03-0045 N/A N/A N/A 1989 (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code ASME III 1968 w1977 1440 ANSI B31. 7 1969 F.df~iti'11970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 Summer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 N,rili\..,___ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1968 wzo ~]4==4~0 _ __
                                                       *ASME III/ANSI B31. 7                       1969     F.d.       1970 Add.(editionJ                   (addenda)          (Code Case(s))
9. Design responsibilities _..,.~.ai.::>-------------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure NOP psi Code Case(s)_.... N"'t/""A""'-------
11. Description of work Replaced va l>re with spare valve from stores.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3" , 1~-~4_ __ Date I- I n/  ;; ct PSE&G Co.-Nuclear Dept.,;~~~~ 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -""'~ ....~""'-~""""-==""~"'------ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New .Jersey and employed by _ _ __J;;illWDgr:u:..._m.u:c.ucLL_,.Lill:illl::aJrn..::e._..uJ.-~--------- of MA have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date_/_-_/_7_, 1d:L_. Signed (7/J¥l4/ (. ~J---- Commission0/Jt1J}r.J}!:J£alJ:lJ*z?sn. f (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rev.6

FORM NR*1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)gl .'*  : .. TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 ori< performed by --EP1""ub~l:1:ic....,_,Sa<9I."'i~..,..,n~*C.;11S5---JEli!d.4iect~~"""='i""'c~&~Gas!Ell!Oi----1.>01iJO-.-._,-"""---jNl)tllJ.I<C:;Jli,c;eiJEElllbl:";:._tDeJeJ;;ptJb.w.--~CJkJ,JP~;;:#S~9::J.3~-,,,;247tJ61;)_----- (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bri.age, W 08038 (address) Public Se:rvke El ectri c am r-.as Co. (name) Foot of B11ttonwocd Bred, Hanax:ks Bridge, NT 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nncl ear r..enerati ng stati an Unit jl Foot of Buttonwood Road, Hancocks Bridge, W 08038
4. System Corrb:ol Air Nuc] ear CJ ass TT 5.~ Componentrep~~.modifiedorre~~ed~~~~~--------------------------------

b: Name of manufacturer Rockwsll IntenlElti.onal c: Identifying nos. Not Available N/A N/A N/A 1987 (mfr's. serial no.) (Narl.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code ,ASME Sec. III 1977 1979 N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUmmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ....

N,>r-.fA.,.,__ _ (edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1977 wzq ~~....,.l~A~--
                                                                                                   *ASME Sec. III                                                                  (edition)           (addendaJ            (Code Case(s))
9. Design responsibilities - - ' = = " " " ' " " - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic O pneumatic O design pressure D **pressure N/A psi Code Case(s) __J\\..,.,_l_..7\,.___ _ _ _ __

escription of work Replace (4) cap screws and va]ve disc in kind from fo] in (use of additional sheet(s) or sketch( es) is acceptable if properly identified) CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 1 , 19.,..9"""4.....___ Date I. 2 - c.L u .::::; ;. PSE&G Co. -Nuclear Dept. 19,___L:,L. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~,,..../L."-""'-A"-~_/~~~~~V4-=~~J_____ 

                                                                                                                                                           / ~ / - '-                                  Principal                 Engr.

(repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri gbt Mutna] Insurance Co of MA have inspected the repair, modification or replacement described in this report on /2-J , 19 9 j and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be ir;i any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                                                                    /         /                                                             Factory Mutual Engr. Assn.

Date /2- / 7 , 19 Cj) . Signed { - ~ CommissionsA.tJif t/ I;1/;:J lu:!J 2.3 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*Bl Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) i,tJ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l rkperiormedby_~Pub===l=i=c-=S=erv=..:.=i=ce=-=E=l=ectr====i=c'-=&~Ga~s-"'Co==-._-_Nu"-'-=c==l=ea~Lr=-De===:p~t==-*-------"'CJP==_,,_#=S=9=3_-=2~7~7-----~ (name) (repair organization's P.0. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem NucleaLr Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Chemical & Voll.nne Control (C'VC) NucleaLr Class II
5. a: Component repaired, modified or replaced lCVEl 7 #1 I.et Down Heat Exchanger b: Name of manufacturer -~A=t=l=as~--------------------------------------

c: Identifying nos. 843 694 N/A N/A _ ___,,l._,,9""6'-'7_ _ _ __ (mfr's. serial no.) (Narl.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code ASME Sect. VIII 1967 N/A II ANSI B31. 7 1969 Eihtioi!)970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrnrner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 -'-N_,_/A (edition) (addenda) (Code Case(s))
8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1967 N/A N/A
                                     *ASME Sec. VIII/ANSI B31. 7 1969 &l.. 1970 Add.                                               (edition)           (addenda)              (Code Case(s))
9. Design responsibilities _PS_E_&G __________________________________________
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _ _,N:..:./'-'A=-------
11. Description of work Replaced bolting.

(use of additional sheet(s) or sketch(es) is acceptable if properly identified)

12. Remarks: -~W~o=r=k~O=rd~e=r~#~:~9=3~0=9=2~4=1~34~--------~De=f1=*c=1=*en=cy=z--~R=e9'po~rt~~#~:~N-/=A~-------

Design Change Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                     **S stem Inservice Test                                                  T
  • NOT CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 1 , 19_9_4_ __ PSE&G Co. -NucleaLr Dept. / P/ Principal Engr. Date / - if 19,4-. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~~ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / - I/ , 19CJ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection . 

                                                                   ., /                                                       Factory Mutual Engr. Assn.

Date / 1 , 1~- S i g n e d * ~ * &~ Commissions Nil s;fqt( t/I/ /I /l/J.? J 7 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) (i5l TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS 1 ork performed by Public £enrice Electric & Gas Co. Nuclear Dept. CJP #S93 278 (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NI 08038 (address) (name) Foot of B11ttonwaod Road, Hanc.oc:ks Bridge, NT 08038 (address)

3. Name, address and identification of nuclear power plant Sal em NJ1cl ear r..enerating Station Unit #J Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Reactor Coolant Ni icl ear Cl ass TT
5. a: Component repaired, modified or replaced lRCE35 El 100 PersonneJ Hatch b: Name of manufacturer Chicago El.lQge and Iron c: Identifying nos. 2668 N/A N/A N/A 1970 (mfr's. serial no.) (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code ASME III 1965 W67 N/11 (E) 2 (edition) (addenda) (Code Case(s)) (Code Class)
6. Section XI 1983 SUm!:oor 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: ] 983 883 ~.....,._/=A _ __

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *J 965 W67 (.....

Fl'+-)2,u...__ _ 

                                                                         *ASME III                                                       (edition)           (addenda)          (Code Case(s))
9. Design responsibilities - - L ' < " " ' - ' " " ' - ' : % - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure N/A psi Code Case(s)_~N,.,/~A-------
11. Description of work Install new stop pin for air lock eqJJaJ izing balJ va]ve.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) NIA CERTIRCATEOFCOMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oc+/-. 3 1 , 193~4_ __ Date/~ 2 PSE&G Co -Nuclear Dept 19,~. Signed_ _ _ _ _ _* _ _ _ _ _ _ _ 

                                                                                                                   /     / /       ,;? *   /
  • _ _ ..,~~~""'~""'"""'~~""""'='::__'_ _ __

Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by _ _ ___.,,,.__""""...__.~......_-"-'.......""""'......___._~.....,._.,..L.L>.<=-~~---------- of MA have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                                   /~ /         /J                                               Facto:r;y Mutual ~. Assn.

Date / 2~ J f- , 1g_J.__l__. Signed ~ 7.. ~ Commissions1\/8 )tqt/ l,V/I 11./J JJJ (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.s

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ~ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1 ark performed by Public Sei:vice Electric & Gas Co. - Nuclear Dept. CIP #893-279

  • (name) (repair organization's P.O. no .. job. no .. etc.)

Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038
4. System Set:Vice Water Nuclear Class II
5. a: Component repaired, modified or replaced --'Bu==tterf~==l=y..._--'V.~al~v~e~=1=5SW7~~2~----------------------

b: Name of manufacturer Masoneilan International Inc. c: Identifying nos. N-00113-39-5 N/A N/A 1977 (mfr's. serial no.) (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code ASME Draft P&V -1~9~6~8~~W'¥-'7~0~-- N/A (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUmrrer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N._/~A~-

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1968 M/70 N/A
                                                                                                                            *ASME Draft P&V                                                     (edition)                       (addenda)             (Code Case(s))
9. Design responsibilities - - - ' P S E - ' - " " ' " & G " - - ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D *'ressure N/A psi Code Case(s) _ _~N~/~A~-----
                                           'Ihe valve was replaced in kind (SIN N-00203-1-8).

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ _,Wi_,_,,o,,,r..,k...__,Qrd......,..,er.,.___,#,_,:..____9~3.....l..,0..,2....,0,,..2.....2....,0.._.8..___ _ _ _ _ _ _ ___.De...,....f._j._.c.....i....e...ncy......,;l'--'B""'e-1pa
                                                                                                                                                                                                  .........rt-~-i#fF-':.___.~,,.,1.....AO>--_ _ _ _ _ __

Design Qiange Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A 

                          **        stem Inservice Test
  • N08f.NC1'
                                                                                                                                                                     -'~.Y-.- - - - - - - - - - - - - - - - - -

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair. modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ _ PSE&G Co.-Nuclear Dept. Principal Engr Date i- I 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) 

                                                                                                                                                             ,</!a2A-*(authorized representative)                                                    (title)

I CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance. Co

  • of MA have inspected the repair, modification or replacement described in this report on ,,_.// , 19C/. and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rd rules as defined in the publication NB-102, current edition. By signing this certificate, neither the .Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

a Date__,_f_*-__._/__ , 1<fL!l_. Signed 

                                                                 ~
                                                                 ~11..&/ c.. fd c            I .
  • CommissionsJ\/IJ
                                                                                                                                                                                          ,~~;ry~tuai ~* Assn.

cff</ µ,4 //.!fj)~ 

                                                                  .                                            (Inspector)                                           (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)J8l TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1 ark performed by J?! 1bl i c Send CP El ec+/-ri c & C..as Co - Nucl ear TEpt. CJP :f/:893-287 (name) (repair organization's P .0. no., job. no.,etc.) Foot of B11ttonwcxx1 Road, Hanc-0eks Bridge, NI 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NI 08038 (address)

3. Name, address and identification of nuclear power plant _ __..S""al .....em""""'. __..Nu.. . ....,cl..,e,,.'Q""""r__,,Gen.,,,,.""era,,..,,,.._,,t,,.ing~:l--'S"'-ta=.._,,t,,,,i,,,,,o,.,n...___U=m='"-'t=---.1.1.#,,,,l,_________

Foot of B11ttonwcxx1 Road, Hanc-0eks Bridge, NI 08038

4. System Reactor Coolant Nuclear Class I
5. a: Component repaired, modified or replaced ~l~C~-~PR~~--SN~O~l~O~S~n~ub~ber~--------------------------

b: Name of manufacturer Paci fi c Scientific c: Identifying nos. 25784 WA WA N/A 1976 (mfr's. serial no.) (Narl.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code ASME I I I NF 1974 W76 1644-1l1644-5 _ _~------ ANSI B31. 7 1969 F.(i~itio1970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 --...;Sl,._mune......,Lo;,jr...........8......3...__ _ _ _ _ _ _ __ WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N;..,,,_,,/A,_,,___ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1974 S70 164.....,4,_--=4_ __
                                                        *ASME III/ANSI B31.7 1969 Ed. 1970 Add.                                                                                                  (edition)                          (addenda)                       (Code Case(s))
9. Design responsibilities _.i;::.;:u:&l!,;t__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure WA psi Code Case(s) _ __,N,_, /<-'A._, __ _ _ _ __
11. Description of work Replaced snubber serial # 25784 with snubber serial # 27164.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Aemarks: ___...,,.,.,..,__.....,.,......~-ll'~-Dleo..._.....,,......,......._ _ _ _ _ _ _ _ _ _4De--.f~J-*c ........i~e~n-rt...,,__~R~e~pa..,._,,rt-~""--Tl#~*~SMD~~9~3--~3~1~1~----- Bev. NIA of Replacement. ' N/A ce T

  • NA CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19~9~4_ __ PSE&G Co.-Nuclear Dept. Principal Engr. Date I 2-- G 19,  ?' 3 . Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on - I , 19 7 Z and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

            , _G.--          ~--                      ~                            , C        /                                                                                        l~_cto1]: Mutual Engr. Assn.

Date ,.2 J '1~. Signed .4-~/ LI Lt,..yL-- Commissions/l'//.Jrlf we/;/ 1 11.F[J'J7 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR*1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 ork performed oy Blhl i c Servi c.e Electric & Gas Co. - Nncl ear Dept. CJP #PS92-040 (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttnziwncrl Raad, Hancocks Bridger NT 08038 (address) (name) Foat of 13uttonwood Bead, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ _....Sal ........,,em_.._.Nu.......,""c""'l""'e""e....r,__,,Gen.,,.,."'era:""""""t""""'ing~........,S'""'ta"""'t""1""a,.,n....____,,U~m.,,'..,t"---J#"-'1""------

Fa>t of Bnt1:onwood Road, HaT!Cl'lC!kS Bridge, NT 08038

4. System Oiemical Volume Control Nuclear Class I
5. a: Component repaired, modified or replaced ....l..,C.._-c\/l __"'"'"cs ........-.. 2. ....7...6..__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: N a m e o f m a n u f a c r u r e r _ - - 1 ; : w . i ; : . Q ; u . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - c: Identifying nos. N/2\ N/A 1975 (mfr's. serial no.) (Narl.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code Spec 69-6445 1 Rev. 9 N/A N/A (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 --Sl~Ill1D'~~r-8_3~--------- WA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N~/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A N/A N/A
                                                                                                                     *S-C-MB:X>-MCS-043                                                       Rev.               0                       (edition)               (addenda)        (Code Case(s))
9. Design responsibilities - " . U . " " " " " - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure ~/A psi Code Case(s)_~J:i..,./'"""'A~------

Mcxli fication of existing suppm:t. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ _.w....o,, .,::i::;ri'........

k Ord ..........e...r-#c..*---J.9~2... 08'""0 

                                                                                     ....5....l....l....6.,___ _ _ _ _ _ _ __,ne........_f._1...                                                                                    e~p:>
  • c_i...e.....n....cy""'f--"""B.... -r+........_-'ff=lf.~=-~"-¥-/~A--------

Desi gn O'lange Package :!f: lEC-3167 Rev. 1 See attached pages for Description of Replacement. 

                       **                                                                                                                                        T
  • NA CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 199=-=-4_ __ Date I 'l. - 7 19,_2:f._. Signed_ _ PS_E_&G __eo_._-_Nu_c_lear _ _De_p_t_._ _ /-~ ~ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I I-If: , 19 3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rd rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. { / . Facto:ry Mutual Engr_. Assn. Date /2- /{ , 1 & . Signedf)-1-x.PJ c_. L<..v/.. ,. . CommissionwPr-t1'1 INA JJJJ7) (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 

           ./
           ~~ . ,*                                              FORM NR-1 ATTACHMENT Code Job Package No.: PS92040 Page ~ of ~
                                                                                                                        .~ ~~~~{i~S.~f :'
          =~=============================================================

~~JI::.. of 0 ~o:~~~~~;t~~~~~c-e-=~~~~E~&~~=-A_-_c_v_.;__c_G_-_9_0_2____________---'""""""~~=~~~ ~~*~:. N/A N/A N/A 1972 =N~....;.;;;;=-.;:; 7:**_: Serial No. Nat'l. Bd. Jurist No. Other Year Built . ASME:;;c**

)
Original Const. Code: Spec.69-6445 Rev.9Edition N/A Adderidci~~~-'~'

Code Cases: N/A * -~:9*'

~,'  :. -------------------------------------'!"'"-------------------~~i,;~

ID of Replacement: lA-CVCG-902 . * ~*,~':'c~. Name of Manufacturer: -=P~S=E=&~G=--~---~------------""'"" N/A N/A N/A =N/._.,A"'--- Ser ial No. Nat'l. Bd. Jurist No. Other Replacement Const. Code: S-C-MBOO-MDS-043 Code Cases:N/A Rev. o 

          =======================================================

ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Original Const. Code: Edition--""'"! Code Cases: 

          ~~-~~-;~~~~~~~~~~~------------------------------~~::;~~

Name of Manufacturer: ial No. Nat'l. Bd. Jurist No. Other lacement Const. Code: Code Cases: - - - 

          ==============================================

                    ' FORM NR*1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D
              ,.~,,                       TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
                      *'~                                                                                                                                                                                        Pae 1 of 2 ork performed by             Public Service Electric:                                                        &    Gas Co         - Nuclear Dept                                     GIP #PS92-D41
                            -  7              *                                                                                        (name)                                        (repair organization's P.0. no., job. no.,etc.)
  • . Foot of Buttonwood Road, Hancocks Bridge, Iil 08038 (address)

(name) Foot of Buttonwocd Road, Hanccx:ks Bridge, NT 08038 (address)

3. Name, address and identification of nuclear power plant Sal em NJJCl ear C'..enerati ng stat i an Unit :jfl Foot of Buttonwood Road, Han.cocks Bridge, Jil 08038
4. System Reactor Coolant Nuclear Cl ass I
5. a: Component repaired, modified or replaced ...1IL.>C..:-::::;PR~J.JHi;:::-::..Jl._7,__7,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Name of manufacturer -----,!;<a,ie.ei~-------------------~----------------- c: Identifying nos. -N..../~A~.. - - - - - N/A N/A N/A 1974 (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code Spec 69-6430 :Rev-.-5~-,j,ljN~/~Ao----- ~IA (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1 983 $83 N;~/A~*---

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: N;f A ~N;~/~A~--
                                                                                                          *S-C-MBX>-MI:s-043                                                          (edition)              (addenda)         (Code Case(s))
9. Design responsibilities - & u . " " " ' ; z _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure N/A psi Code Case(s) _ _,N_.,,F/A""'-------
11. Description of work Merli fi cation of pipe suppart (use of additional sheet(s) or sketch( es) is acceptable if properly identified)
  • r--~~~~~~~~
12. Remarks: ---¥¥~lo7.tr~k,._._...o.,,,,m~eo:r,.....-'fl#.....:--7796'2'd0e-80..,,5dcl=-1=-7+------------.De......,f0=1..,..*c~i""ei ...n-c;_,,__r..,.,~....e""po""""':ct.--41#-*-N>r-/A
                                                                                                                                                                                                           ...~.,--------

Desi gn Change Package #* lEC-3168 O

  • See atta9hPd pages far Description CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires act. 3, , 199~4~-- Date/ 2

  • 3 c;.., PSE&G Co.-Nuclear Dept.

19,___L,,,2__. Signed _ _ _ _ _ _ _ _ _ _ .~ <"4.<A6-' 

                                                                                                                                                      ~     11 /            / * /                           Principal Engr.

(repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by i Mutual urance Co of MA have inspected the repair, modification or replacement described in this report on  ::J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, essed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property age-or a loss of any kind arising from or connected with this inspection. Factory....,Mutual Engr. Assn. Date I 2. I r IY . 19 '/ J . Signed b_ f (Inspector) Commissions p4 2-0-5 f:1 .lj I 0 J I J tUT If 3 / (Natl.Bd.No.(including endorsements)state or province and rfU!l;ber) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

Page J_ of _L FORM NR-1 ATTACHMENT Code Job Package No.: PS92041 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

2. Owner: Public Service Electric & Gas co.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. Syst~m: Chemical Volume Control Nuclear Class: --=I=I~~~~
==================================================================

ID of Component Replaced: __,::1~-~C~V~C=A=---=6=5=3~~~~~~~~~~~~~~~~~~~~~ Name of Manufacturer: PSE&G 

                      -=-=-~=-~~~~~~~~~~~~~~~~~~~~~~~~~

N/A N/A =N~/=A..___~ N/A 1980 =N~/A=----------- Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Spec 69-6445 Rev9 Edition N/A Addenda, Code Class J.I__ Code Cases: N/A ID of Replacement: --=i~-~C~V~C=A~--6~5~3~~~~~~~~~~~~~~~~~~~~~~~ Name of Manufacturer: PSE&G 

                      -=-=-~=-~~~~~~~~~~~~~~~~~~~~~~~~~

N/A N/A N/A N/A 1993 =N~/=A'---------~ Serial No. Nat'l .. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: Spec S-C-MBOO-MDS Edition NL.A_ Addenda, Code Class II Code Cases:N/A -043_ ~-- _ _ __

============================================================~=====

ID of Component Replaced: Name of Manufacturer: al No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? ginal Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: Edition Addenda, Code Class Code Cases: - - -

==================================================================

ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - -

~---------------------------

ID of Replacement: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Const. Code: Edition Addenda, Code Class _

  • Cases: - - -
==================================================================

FbRM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by Public Service Electric & Gas Co. - Nuclear Dept. GJP #PS93-012 (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 (address) 2.0wner_'-Pub=-==l=1='c=----:S~erv==-~1='ce==~E=l=ectr==-===ic=-and=-==--Gas===-Co==~*------------------------- (name) Foot of Buttonwocx:l Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocx:l Road, Hanccx:::ks Bridge, NJ 08038
4. System Control Air Nuclear Class I I
5. a: Componentrepa~ed, modffiedorre~aced _1_1_~ __ 3~0~and~~1=2~3~~~~3~0~~~al~~~~~--------------------

b: Name of manufacturer _ _,,Maso_.,,,,,=n....,,.e,,.i,,.l,,,an,,._.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ c: Identifying nos. N-00133-1-1&2 N/A N/A N/A 1992 (mfr's. serial no.) (Nat'l.Bd.No.) (jurisdictional no.) (other) (year built) d: Construction Code ASME I I I 1971 S/1971 N/A ANSI B31. 7 1969 W,~tioilt:)70 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUmrner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N~/A~~~

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1971 S71 N/A
                                                                  *ASME III/ANSI B31. 7 1969 Ed. 1970 Add.                                                                    (edition)            (addenda)        (Code Case(s))
9. Design responsibilities _PS==E=-=&G:=.._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure NOP psi Code Case(s) _ _.N""/_.A""-------

Description of work Replaced stem assembly and bolting on 11~30. Replace stem assembly (use of additional sheet(s) or sketch( es) is acceptable if properly identified) on 12~30. Stem assembli~ install to match new soft seats. 

                                                                                      ...1~2...,4,.___ _ _ _ _ _ _ __..J.D=.......,fc...iuc~iu:e""n.J.l.cy.q_-1R""e::J>po.LUJrt~--:<#~*.__,,N,.,/uAi-_ _ _ _ _ _ __
12. Remarks: _ _,Wi"-'o,,..r,,_,k"-'Ord"""'""er"""----l#r...i:L__o9,,,,.2"'0.c.4,..2..,1 Design Change Package #: lEC-3170 Pkg. 1 See attached pag~ for Description of Replacement. N/A
                       **       stem Inservice T~t                                                                              T
  • Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 1g3::......::4_ __ Engr. 

                                '13 . Signed. _ _PSE&G                                        Co.-Nuclear Dept.                                                                                   Principal Date      i L. - :2.. c  19,                                                 _ _ _ _ _ _ _ _ _ _ _ _ __

(repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /I*- 2 1< , 19 '?:I and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. C---'--., Facto:ry Mutual_ Engr. Assn. 

                                                                 //2,{~

1 1 Date j 2 *-J f'J , 9J . 19 Signed Commissions 4 2 oS' {::> /f/ l Jf',J I J /(./_r : / J / (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*Bl Rev 6 

                                                                                                                                                                                               <1

_.-.-- '/- FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S):g(

  • TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS * .. ,. **, 0'.
  • Page *1.* of 2 ork performed by --=Pub=-===1==1=*c~serv"-==--'-"'1=*ce~~El~ectr-~1_*c_&_Gas~-Co~*~-~Nu~c=l=e=~=ir=--=De=p"-'t::..:.,____ __,CJP"""""'--'#u::PS!:..!=!.:9:!..:3:t..-~Oo!:4:!!5~----

(name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) 2.0wner _ _ Pub __l_i_c_Serv _ _i_ce __E_l_ectr _ _i_c_and _ _Gas _ _Co_.________________________~ (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. system Generator Blowdown Nuclear Class I I 5.~ Compone~repa~ed,modmedorre~~ed_l_l_G_B4~,_1_2_G_B4_L,_1_3_G_B4~,~1_4_G_B4 __~_~_v_e_~_~ ____s____________

b: Name of manufacturer Masoneillian c: Identifying nos. See Attch. N/A N/A N/A 1974 (mfr's. serial no.) (Narl.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code ANSI B31. 7 1969 None 2 (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 Slllmner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 _N~/_A_ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A 1969 N/A
                                               *ANSI B31. 7                        /ASME         Sec. I I I 1971 - Slllmner 71 (edition)                                   (addenda)            (Code Case(s))
9. Design responsibilities _PS __E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic O pneumatic O design pressure O pressure ** psi Code Case(s)_~N,_/A~-----
11. Description of work Replace GB4 valve internals IAW DCP lEC-3226-01.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: __Wi"'"""o=r=k=--Ord==er=-_#u...:....:_,9""'3"""'0,,_,2,,_,0"""3'""1=2=3'---_ _ _ _ _ _ _ __,,,De=f=i=c=i=en=cy~R.....,e""poE"=rt~_#..._._:_,N=o=n~e=---------

Design Change Package #: lEC-3226 Rev. 01 See attached pages for Description of Replacement. 

                      ** NOP                                                                                      Temp. Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4_ __ Date~ -23 PSE&G Co. -Nuclear Dept. 19,__2J::'Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ ...,~h,'4v I .P iJ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co . of MA have inspected the repair, modification or replacement described in* this report on 2 - Zh , 19zj q and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacemen.t described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date 2-"Jfr 

                            ,I
                      . 1{/_:J__. Signed~:/~
                                                 ~                                < ~-
                                                                                          / ,                                                     Facto~ Mutual ~. Assn.

Commissionsl\/tJ)f7'{ ..J.'1/1.:/ A.JcJJ7J * 

                                                                       .          (Inspector)                                         (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The Nation al Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

I Page _.L of _.L FORM NR-1 ATTACHMENT Code Job Package No.: PS93045 by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System: Generator Blowdown Nuclear Class: 2 

                                                                                                                                   ~~----
          '=============================================================================

i/ID of Component Replaced: ~1=-=l~G:=-:B::-:4~V..:..=a=l-'-v..:::e=---=I...._n-'-'t=..:e=r=:..:n=a=l"'s,_ _ _ _ _ _ _ _ _ _ _ _ _ __ JName of Manufacturer: -=-M=a=s~o=n=e=i=l=l=a=n~-~------------------~ /:;; N2/N001301-l N/A ?*~;- N/A 

                                           ~"""""----

N/A -=1=9_,_7_.4'---- Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: ANSI B31.7 Edition 1969 Addenda, Code Class~ Code Cases: N/A --~A=S=M==E--=S~e=c~.'--'I=I==I--=1=9~7~1=---__,S=:...u=m=m==e=r'---'7~1=-- ID of Replacement: 12GB4 Valve Internals Name of Manufacturer: -=-==="-=====-=-===----------------------~ Masoneillan N2/N001301-2 N/A N/A N/A =1=9_,_7~4~-- Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? original Const. Code: ANSI B31.7 Edition 1969_ Addenda, Code Class~-- Code Cases: N/A ASME Sec. III 1971 - Summer 71 

         ==============================================================================

ID of Component Replaced: --=l=l~G~B~4=-V~a==l~v~e'---=I=n~t=e=r=n==a=l=s,_ _ _ _ _ _ _ _ _ _ _ _ _ __ e of Manufacturer: -=-==-==-=====.::::.= Masoneillan_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 001301-3 N/A =N_/=A'---- N/A 1974 al No. Nat'l. Bd. Jurist No. Other Year_B_u_i_l_t ASME Code Stamp'd.? Original Const. Code: ANSI B31.7 Edition 1969_ Addenda, Code Class ~-- Code Cases : _ N/A_ --~A=S=M==E--=S~e=c~.'--'I=I==I--=1=9~7~1=----__,S::...u=m=m=e=r=--7'-=1. ID of Replacement: 12GB4 Valve Internals Name of Manufacturer: Masoneillan N2/N00130 l - 4 N/A 

                                      -=-==="-=====-=-===-----------------------

N/A* - - - N/A -=1=9_,_7-'=4~-- Serial No. Nat'l. Bd. Jurist No. 0ther Year Built ASME Code Stamp'd.? Original Const. Code: ANSI B31.7 Edition 1969_ Addenda, Code Class ~ Code Cases: N/A ASME Sec. III 1971 - Summer 71 

        ==============================================================================

ID of component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? . "' g~~~i~:!e~~nst. Code: Edition Addenda, code class ~.Jr~:~;, 

        ~~:~;:~~~!~~~:~~~~::~--------------------------------------------------------~,
             'al No. Nat'l. Bd. Jurist No.                               Other                       Year Built             ASME Code stamp'd.j~;<f':'.*~~t~
  • li acement Const. Code:

Cases : 

        =======================================================================~~~f;~;~:*:**

Edi ti on Addenda Code Class.?§:. 

                                                                                                                                 '            :* *..:..~-*>'(.......-:: .,r
                                                                                                                      ... . 't     *jGij~~,Bt**

FORM NR-1 REPORT OF REPAIR D MODIFICATION _MOR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l 

~rkpertormedby -~B~1uh41L1~*c. . _...s~e~rv'-"- ~i~CP~- -. .E~luect'" " '. . . ._r~i~c. ._ .&, ._ ,G~.;au.; ;s._ _, ,Ca-n~-L- - ~Nu" "'c~l~e~-a~r. ._.De=,i,pt, . . _.L- ~CIP~.._~#~PS~9~3~-_,,0~5~3~-----

(name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwocrl RoadJ Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwcxxl Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant --~S=al=em=~Nu=c=l=e=ie3=Lr~~Gen~""era==t=ing=-o..~S~ta~~t=i=o~n~_U_m_'_t_#,,__l_ _ _ _ _ __

Foot of Buttonwood RoadJ Hancocks Bridge, NJ 08038

4. System Reactor Coolant Nuclear Class I 5.~ Componentrepa~ed,modffiedorre~~ed_~~~-¥~a_l~v~e~-----------------------------

b: Name of manufacturer -~C ...o....pe.,......-S~"S...l!...11,..c 

                                                                              ....o:=i~~n~----------------------------------

c: Identifying nos. 6910-95001-J 64-J N/A N/A N/A 1969 (mfr's. serial no.) (Narl.Bd.No.) ourisdictional no.) (other) (year built) d: Construction Code W E-Spec E676270 _ _ _N...,,-F-/=A.___ __ WA I ANSI B31. 7 1969 Eticiitio!J..l970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI ]983 SJ.nnmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N~/~A _ __

(edition) (addenda) (Code Case(s)) B. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A 

                                                                                            *ANSI B31. 7           ITfi    E-Spec E-676270 (edition)                                                   (addenda)         (Code Case(s))

9: Design responsibilities _,."""'E,,,,&G=---------------------------------------~-

10. Tests conducted: hydrostatic D pneumatic D design pressure D**pressure NOP psi Code Case(s) _ _,N'-'J-/=A=*--~---

Replaced. valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: __w....._a~r~k....._.Qnj....._.~e~r.L-~#~*-9~3~0~1~2c..u6~1~5~0,___ _ _ _ _ _ _ _ _~n= ........-f~j~c~i~e~n~cyq....~B~e~:pc:2[!o<'-<-rt...._~#µ:.___.1'{~/~A....__ _ _ _ _ _-'---- Design Change Package #: lEC-3219 Pkg. 1 See attached pages for Description of Replacement. N/A 

                       **SVstem           Inservice Test                                                            Temo.            Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4_ __ 

                              ~- w                               PSE&G Co. -Nuclear Dept.                                                                                                              Principal Engr.

Date I~ (2 19,__'__L_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by Arkwriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on f *- f I , 19 ~ L/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer make~ any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be

  • any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

(/ £: - Facto:i:Y Mutual ~. Assn. Date /- / 1 , 19 C/ £/ . Signed YQ-pwV v* 1.,-J____ CommissionstVtf)JJ'l'/ J. /I/;-/ 1UJ J// 

                                                      /                              (Inspector)                                                   (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rsv.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION r§' OR INSTALLATION OF REPLACEMENT($) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER P~ANTS Page l of l rkpertormedby_=Pub==-l=1=*c~S=erv==--'--=ice=='-=E=l=ectr====i=c'--=&'--"'Ga==s--=C=o~._-___;Nuo.=c=l=e=a=tr=-De==pt~~*---CJP==,,__#~PS==9~3=---=05=4-=----- (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant ___S_al7""-_em __Nu_c_l_ear___Gen __era __t_ing_~S_ta_t_i_o_n__U_ni_'_t_#~l_ _ _ _ _ __

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

4. System Reactor Coolant Nuclear Class I
5. a: Component repaired, modified or replaced 1PR2 Valve b: Name of manufacturer -------'C""o""pes==--VUl=-==can=-=--------------------------------------

c: Identifying nos. 6910-95001-164-2 N/A N/A N/A 1969 (mfr's. serial no.) (Nat'l.Bd.No.) aurisdictional no.) (other) (year built) d: Construction Code W E-Spec E676270 _ _~N~/A~-- N/A I ANSI B31. 7 1969 E'$ditioa.J970 Add. (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 (edition)

Surrrrner 83 (addenda) (Code Case(s)) NIA

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 =Nr-=/A=------

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                                            *ANSI B31.7/N E Spec E676270 (edition)                                           (addenda)           (Code Case(s))
9. Design responsibilities _PS_E_&_G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic O pneumatic O design pressure O **pressure NOP psi Code Case(s) __N~/_A _ _ _ _ __

Replaced valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: -~W~o=r=k~O=rd~e=r__,,_#~:~9~3=0~1-2=6-1~5~0_ _ _ _ _ _ _ _ _De~f_1_*c~i-*en~cy~~R~e"oEpo~rt~_,.:/f~=~N;'r-/~A~----,-----

Desiqn Change Package #: lEC-3219 Pkg. 1 See attached pages for Description of Replacement. N/A 

                        **Svstem Inservice Test NOP                                                Temn. NOT CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires act. 3, , 19_9_4_ __ f' PSE&G Co.-Nuclear Dept. Principal Engr. Date rJ- I 2 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 

                                                                                                                   ~'

(repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwrioht Mutual Insurance Co of lYIA have inspected the repair, modification or replacement described in this report on / - if q 

                                                                                                                                                     , 19 l/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be
                                                                      -/
  • 1n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
              - { c*                               ~*1                                                                             ~act:qry ~tual Engr. Assn.

Date 1 1 , 1g_jj__. Signed ( M?'\.Zt/ ~. (..,~ Commissions Mz ~ '1'1 JN if J JV f7] (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION [gl OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l orkpertormedby -~P1........1h~l~i~c~S~e-~~~i~c-!e~E~l~ect~~r_i~c~~&~C...;:i~~s~C~o~._-___.NJ.......,1c~l......e~e~r_ .De" '" lp~t. . _._.___CIP""""'...._~#µPS 

                                                                                                                                                                             ........~9~3~-~0~5~2..___ _ _ _~

(name) (repair organization's P.O. no., job. no.,etc.) Foot of ButtonwOCJd Road, Hancocks Bridge: NI 08038 (address) (name) Foot of Buttonwood Road, Hanccx::::ks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant ___S=al~em=~Nu==c=l=e=!a=tr~Gen==era==t=mg=' =~S'""'ta=t=1='=o=n~_,U=ni='t=---'#'-=1=----------

Foot of Buttonwood Road: Hancocks Bridge, NJ 08038

4. System Reactor Coolant Nuclear Class I I
5. ~ Componentrepa~ed, modffiedorre~aced ~1-C~--~~~-~4-0~4~~~~~~-~~------------------------

b: Name of manufacturer ---=--=......- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - c: Identifying nos. __.N;-¥-/A=----- N/A N;/A 1976 (mfr's. serial no.) (Nat'l.Bd.No.) aurisdictional no.) (other) (year built) d: Construction Code J?S Spec 69-6445 NIA J N/A SGS/M-FD-1 (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SJ l!JD1Jffr 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 ~N~/=A~~-

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *NIA N/A N/A
                                                                                   *PS Spec S-C-MBJO-MIE-043                                              (edition)            (addenda)              (Code Case(s))
9. Design responsibilities ~PS~E=&G~----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure WA psi Code Case(s)_~N,,_,,_/A"-=-------

Modified pressurizer piping supports. (use of additional sheet(s) or sketch( es) is acceptable if properly identified) N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __ PSE&G co.-Nuclear Dept. Principal Engr. Date i2 - 8' 19, Cf-3 . Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on 2. O 06C. , 19 lf .3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification o e I cement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal inju~ o e ge or a ss f any k" d arising from or connected with this inspection.

  • Facto:ry Mutual Engr. Assn.

Date zo Dec...' 19 Q3. Signed Commissions N8 ll.2o :;i. r A) ,4 H.J/~L:G,J (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l rk performed by Pnblic Service El ec:tri c & Gas co - Nuclear Dept GIP #PS93-055 (name) (repair organization's P.O. no., job. no.,etc.) M'oat of But+om,zoaj Raad, Hancacks Bridge, NT 08038 (address) (name) Foot of Buttonwood Road. Hancocks Bridge. NJ 08038 (address)

3. Name, address and identification of nuclear power plant _ _..,S.,,a...l""'ern,.,...~Nu.o=.,,c""l...,e,,,,e,.,r..__,,,Gen=..,era""",,.t==ing~;l---'S,.,ta=..,,t:::i""o""n..___U=m=',_,t"-J#,_,1=--------

Foat of Buttonwocx] Road, Hancacks Bridge, NI 08038

4. System Reactor Cool ant Nuclear Class I
5. a: Component repaired, modified or replaced PR!' Pipe Spcxlls Sl-RC-3220 and Sl-RC-3222 b: Name of man.ufacturer _ __.,T..,.JE.,.&,,.,C._,~/.,..PS""""E""&G"""------------------------------------

c: Identifying.nos. -N-+/.. A----- N/A N/A 1974 (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code ANSI B31 7 1969 1970 N/A ANSI B31.1 1967 (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 simrrner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 N._,,/c...:A-=----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                                                                                              *ANSI B31.7/ANSI B31.l 1967                                   (edition)             (addenda)        (Code Case(s))
9. Design responsibilities ......i;:.i.2.1,;~;;r._----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure NOP psi Code Case(s)_~N""/~A~------
11. Description of work Modi f j ed pressurizer relief tank small bore piping.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ _..w.....o...~rik...........Ord
                                                   ............eM!r~#r-.'-"'9.....3.....0....l....2-..6....l....5....0..,.__ _ _ _ _ _ _ ____.De....._.f._j~c~1~*e....n.....cy...q-~R~e--ipa~rt~_,:/J:""':~~..,.l~A~--------

Desi gn Change Package j: JEC-3219 Pkg. 1 See attached. pages for Description of Replacement. N/A 

                         **SVstem Inservice Test                                                                                                    Ti=>mn. NOT CERTIRCATEOFCOMPLIANCE Wffcertify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME *code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 199~4_ __ c; u PSE&G Co.-Nuclear Dept. d / / , Principal Engr. Date f- 2 19,______L_,L.. Signed _ _ _ _ _ _ _ _ _ _ _ _ .,,~&~-Cu~ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by Ark.wriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / *- // , 19.&-/ l/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, Date 

           /.- 1I           , 1g_j{_.

e, Signed q {; d or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be ny manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. {\/~ * (Inspector) 

                                                                                                                                   ~-                           Commissions Facto:cy Mutual EngJ::. Assn.
                                                                                                                                                                                    ,1.fF J8"1 Y J:iUIJ A.ff ?7 3 (Natl.Bd.No.(including endorsements)state or province and number)

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR*1 REPORT OF REPAIR 0 MODIFICATION-q] OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l ork performed by _ .........L.l~i..,c"'---'SeJ::v,,,..,.._,,_... _...Pub ice,,.,,.'-""'E....l.,.ectr""'""" ........_,Co""""'*.__-___.Nu~c,.,l,..e,,,,oa....._r_..De~p,_,,t._,*._____ 

                                                                                                             ......i""c"--"&.__,,Gas                                                                       __,CJP....,_,..__:tt~PS......,J.9_,.,3_-_,,,0CL7_,,,0'---"R,.,,e.,__,vu....l..___

(name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road. Hancocks Bridge. NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Control Air Nuclear Class II 5.a: Componentrepa~ed,modlliedorre~aced ~P=i~pe~~~~~=l~l=~~~3=1=0~-------------------------

b: Name of manufacturer _ _Mu..t..... t. J'-'"'---'Ib"""';y_~....l,.,,,e..___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ c: Identifying nos. N/A N/A N/A N/A 1974 (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) {other) (year built) d: Construction Code B31.1 1967/B31. 7 1969 None None (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 Summer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N'r-'/A~--

(edition) {addenda) (Code Case{s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1967 N/A None
                                                                                                                 *ANSI B31.l/B31. 7 1969                                                             (edition)                       (addenda)                        {Code Case{s))
9. Design responsibilities - - = P S = - = E = & G = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic [){ design pressure O **pressure 142 psi Code Case(s)_~N~o=n=e~-----
11. Description of work Added break flanges to pipe spool piece 1CA2310.

(use of additional sheet{s) or sketch( es) is acceptable if properly identified) 12.Remarks: _ __.Wi~o~r~k"'--'On'J"'"'-'~e....._r-'ll#~=-9u3~D~6...,_..._1~5~1~3~5,___ _ _ _ _ _ _ _ _~De~~f~i~c~i~e-n~c:y-r-B~e~po~rt-~~#~:~N~a~n~-e~------- Design Change Package #: lEC-3150-1 Rev. o See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19~9_4~-- e'1 I/ PSE&G Co. -Nuclear Dept. Principal Engr. Date ') - '"'2-L 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ {repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance of MA have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

        .                  '"'* ,/                            ~                                      ,.,,,-*        /                                                                         Factory Mutual Engr. Assn.

Date ) J Jf ,1rfL.!___. Signed ~ 7. Lo-/.__ Commissions/i)fi,!)(C/{ L/V/i ,A)\LJ J 7 {Inspector) {Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION ~OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by Public Service Electric & Gas Co. - Nuclear Dept. CJP #PS93-073 (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038
4. system Chemical & Volume Control system Nuclear Class I I
5. ~ Componentrepa~ed, modffiedorre~aced _~_r_1_'c_~_c_i_d_B_l_~ __er _________________________~

b: Name of manufacturer _ ____,_Wi=es~t=mg=* =h=o_,,,us=e:....__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ c: Identifying nos. None N/A N/A N/A _ _1=9~7~2~---- (mfr's. serial no.} (Nat'l.Bd.No.} Qurisdictional no.) (other) (year built} d: Construction Code ANSI B31. 7 1969 1970 None II ANSI B31.1 1967 (edition) (addenda) (Code Case(s)} (Code Class}

6. Section XI 1983 S1.nnmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N_/_A_ __

(edition) (addenda) (Code Case(s)}

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                                                             *ANSI B31.7/ANSI B31.l 1967                                       (edition)           (addenda)           (Code Case(s))
9. Design responsibilities
                                  -PSE&G
10. Tests conducted: hydrostatic :f;! pneumatic D design pressure O** pressure 170 psi Code Case(s)_~N"""/~A~------

escription of work Removal of boric acid blender no longer needed in chemical and (use of additional sheet(s) or sketch( es) is acceptable if properly identified) volume control syst:m and re-installation of piping.

12. Remarks: _ _,,Wi,_,,o=r=k,,____,,O=rd=e=r-..u.#~:-=9=3=0=61~8,...l,.,,_,3....,3..___ _ _ _ _ _ _ _ _De~f ......1~*c~i~*en~cy~~R~e"'fpo~rt~....,#~=~N;'f-/~A~-------

Design Change Package #: lEC-3254 Rev. O See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 1 , 193_4_ __ PSE&G Co. -Nuclear Dept. I / fl Principal Engr. Date ( * ( l( 19,__l,i_. Signed_ _ _ _ _ _ _ _ _ _ _ _ _ 7 4,4&uL~ * (authorized representative) (title) (repair organization) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwriqht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I/, 7 , 1gCO and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be

  • n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
                   /          -. ;                      ~                                  -    /                                                         Factory Mutual Engr. Assn.

Date/.--),) ,1~.Signed~JU-/?'. l~J_.____ CommissionsN/)""'t9l/ '£;J/t tJf?ZJ (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rev 6

FORM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ill TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 rk performed by Public Service Electric & Gas Co. - Nuclear Dept. CJP #PS93-074

  • (name) (repair organization's P .0. no., job. no.,etc.)

Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038
4. System Chemical & Volune Control System Nuclear Class I I
5. a: Componentrepa~ed, modifiedorre~aced _1_~ __ 7_2_Co_n_tro_ _l_~_al_~_e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

b: Name of manufacturer Copes Vulcan c: Identifying nos. 6910-95001-187-1 N/A N/A N/A 1971 (mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) (other) (year built) d: Construction Code ANSI B31. 7 1969 1970 N/A fl E-Spec 676270 (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 --~SUmmer~~-__...8""'3'----------- N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N~/~A-"'---

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 None
                                                                                                                                  *ANSI B31.7/N E-Spec 676270 (edition)                                                                               (addenda)       (Code Case(s))
9. Design responsibilities __ PS_E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic [JX pneumatic D design pressure O *"'Pressure 170 psi Code Case(s)_~N~/~A~-----
11. Description of work Replace existing lC'i/172 valve internals in accordance with ~ lEC-3254 (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

Packa: e 1 and re lacernent of bolt' and nuts r revision 1 of~ lEC-3254.

12. Remarks: _ _..W,,,,o,,,,,r,,_...k.._,,,O<<>rd,_,,,,,,,er,,,.,,__....J#w:.___.9""""3....,0....,6....1...8....l...3.._.3..___ _ _ _ _ _ _ ____.De,,,.__.f._i..,,c~i..,,e..... ...........rt.........._-..:iff~:.___.N m_..cy"-'l--.....R,,,.e.,..po ......n_...n__.,.e'"'-----------

Desiqn Change Package #: lEC-3254 Rev. o See attached pages for Description of Replacement. 

                        **NA                                                                                                                              T
  • 90°F CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3/ . 19_9_4_ _ 

                                  ,,;                                                     PSE&G Co. -Nuclear Dept.                                                        /    /    /          ~                                                       Principal            Engr.

Date j-~ /j' 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ dd~~, (repair organization) v (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / / , tf} 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, k / sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date 

                   /

J. .- Z-) , 19 q_i_ . Signed 

                                                                                                                           ~**

t** ~ tf Commissions N J F51ct01:y Mutual Engr. Assn. IJ f1t./ /ttf/1 /!) ;/f 7} I (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION ~OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by _ _,Pub=-==-=l::.:1::..:'c=----=S::...;erv==-"-'1=-*ce=-=---=El=ectr=-=-=1=-*c=-&=--Gas=~CO"-"--.'------=Nu=c::.::l::..:e==!a=tr=----=De=p::..:t=-.=-----'CJP=:...._j#u..:PS=-=9::..:3=---'0=-7:....:5:o....__ _ __ (name) (repair organization's P.0. no., job. no.,etc.) Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 (address) 2.owner _ _Pub __l_i_c_S_erv __i_ce __E_l_ectr _ _i_c_and _ _Gas _ _co_._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ (name) Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038
4. System Main Steam Nuclear Class I I
5. a: Component repaired, modified or replaced 1.MSE57, 1.MSE58, 1MSE59, 1.MSE60 COndensate Chambers
                                                                                ....,-----~---~----~----------------------

b: Name of manufacturer COnnex Pipe Systems c: Identifying nos. See Attachment N/A N/A N/A 1993 (mfr's. serial no.) (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code See Attachment N/A N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 Sl..nmner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 ~N~/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1989 1989 N/A
                                                                  *ASME III/ANSI B31.7 1969 F.d. 1970 Add.                                                                         (edition)                  (addenda)                (Code Case(s))
9. Design responsibilities _PS __ E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic [JC pneumatic D design pressure D *-J;:iressure 1400psi Code Case(s)_--=N'-"/'-'A=--------

escription of work Installed new condensate chambers for #11 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ __,_,W=o=r"""k~O=rd=er=-~#"""':,__,9"""'3~0,,__,8=1,,_,0""'0=9=9'-----------=De~f,_,,i.,,c,,..i.,,,en.....,,,cy~...,R.,.,e~po""'rt..._,.,_#..,_._:_.N;LI.J/O...OA....___ _ _ _ _ __

Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __ PSE&G co.-Nuclear Dept. / / / .... Principal Engr. Date { - a-c1 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ _ ..,.~ -dd<~ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on -I , 199 ' ( and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. C / .I __. _ Facto:cy Mutual_.....~. Assn. Date / * '{ , 19-5....!L._. S i g n e d . / t * ~ Commissions ;J{) f1'it 1AJ;1 /UJ J J J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

r - Page _2_ of _2_ FORM NR-1 ATTACHMENT Code Job Package No.: PS93075

  • Work performed by: Public Service Electric & Gas co., Nuclear Dept.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

2. Owner: Public Service Electric & Gas Co.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System: ~M=a=i=n=---=S~t=e=a=m==-------------~ Nuclear Class: --=I=I=----~
      ==============================================================================

ID of Component Replacement: 1MSE57 Condensate Chamber Name of Manufacturer: ___c~o=n=n=e=x=--P.......,i_p_e-=s_y~s~t~e_m______________________, 43471 N/A N/A N/A 1993 =N=o~------~---=-- Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code stamp*d.? Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class z___ Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE58 Condensate Chamber Name of Manufacturer: ___c=o=n=n=e=x=--P=-=ip~e-=s_y~s~t~e=m-........._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 434 72 N/A N/A N/A ~1~9~9_3~___,.-- No*~--------~ Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. *code: ASME III 1989 Edition 1989 Addenda, Code Class L Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add 

      ==============================================================================

ID of Component Replaced: _:;.;N~A=------------------------~ Name of Manufacturer: 

                 'al No. Nat'l. Bd.                          Jurist No.        Other         Year Built              ASME Code Stamp'd.?

ginal Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: 1MSE59 Condensate Chamber Name of Manufacturer: ~C=o=n=n=e=x=-P=-=i=p~e-=S~v~s~t=e=m=------------------ 4347 3 N/A N/A N/A =1=9-=9~3~----=----- No S er i al No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stci.mp'd.? Replacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class L Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add 

      ==============================================================================

ID of Component Replaced: --=-'N~A=--------------,------------~ Name of Manufacturer: Serial.No. Nat'l. Bd .. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Clas$ Code Cases: _ _ _ _ _ _ _ __ 

      -------------------------------------------------~----------------------------

ID of Replacement: 1MSE60 Condensate Chamber Name of Manufacturer: ---~:=-===--=-===-=.....-=:-=~"------------------,-~~ Connex Pipe System 43474 N/A N/A N/A =1=9=9=3~__,..~ No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .6.._ Cases:N/A ANSI B31.7 1969 Ed. 1970 Add 

      ==============================================================================

_ _ _ _ _ _ _ ..--£.,, _ _ _ - -- -* - -- **- -- --- -- -- - - - --- ~ - -- -----* - " * * * -~

FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2

  • ~~~m~~-~~~=l=i=c~S~~~=i=~~=E=l=~==1=*c~&~~=~~~-~-~~=c=l~AA~r~~=~t~*--~~~~#~ffi~9~3~-~0~7~6~---- (name) (repair organization's P.0. no., job. no.,etc.)

Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Main Stearn Nuclear Class II 5.~ Componentrepa~ed,modffiedorre~aced~~~=E~6~1~,~~~=E~6~2~,~~~~E~63~,~~~=E~6~4~~~~~=~~~~~-~~~~~~-------

b: Name of manufacturer ~nnex Pipe Systems c: Identifying nos. See Attachment N/A N/A N/A 1993 (mfr's. serial no.) (Narl.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code See Attachment N/A N/A (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrnmer 83 ~/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 ~N~/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1989 1989 N/A
                                                                    *ASME III/ANSI B31.7 1969 Ed. 1970 Add.                                                        (edition)                        (addenda)            (Code Case(s))
9. Design responsibilities --=ffi~=E:..:.&G:.=-._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic [){ pneumatic D design pressure D **pressure 1400psi Code Case(s) _ __,,N""/'-'A,_,,___ _ _ _ __

escription of work Installed new cond~te chambers for #12 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ __,_,W=o,.,r...,k'--"'O""'rd"""""'er""-..il#.....:-"""9_,,,3'"'"0""8'"""1""0""0'""9'""'9~--------_...~,_._f.... . . ,,_e..._.n~cyY'--....,B.,_eof,opo~rt......__..,j'-":----"'~'+/~A.___ _ _ _ _ __

i .c,...j 

                       ~iqn Change Package #: lEC-3256 Pkq. 1 See attached                               pages       for ~cription of Replacement.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_.1_._ __ o ffiE&G Co. -Nuclear Dept. Principal Engr. Date 1= "2---<( 19,_r__z:::_. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insuran~ Co of MA have inspected the repair, modification or replacement described in this report on /-/ f , 191 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. a LI ~ / Factory Mutual Engr. Assn. 

                                                                                         ~-

1 Date J-J_tf . 19-l.i_. Signed {. Commissions NE ) (9'/ UA fC.!V 1J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

Page __L of __L FORM NR-1 ATTACHMENT Code Job Package No.: PS93076 Work performed by: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System: Main Steam Nuclear Class: -=I=I..___ __
==================================================================

ID of Component Replacement: 1MSE61 Condensate Chamber Name of Manufacturer: ----=C=o=n=n=e=x:,::........,P::...=ip==e-=S~y=s~t=e=m..____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 43471 N/A N/A N/A 1993 =N~o..______________ Se.rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class ~ Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE62 Condensate Chamber Name of Manufacturer: ----=C~o~n=n=e=x""-'P~1=*p~e=-=s~y=s~t~e~m..____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 43472 N/A N/A N/A =1~9~9~3..____,..__ No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class ~- Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

ID of Component Replaced: _,...N"'-""A"------------------------~ e of Manufacturer: ial No. Nat'l. Bd. jurist No. Other Year Built ASME Code stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: _ _ _ _ __ ID of Replacement: 1MSE63 Condensate Chamber Name of Manufacturer: ___,.=.C~o=n=n=e=x--..-P~1~*p~e=-s~y--=s~t~e~m,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~ 43473 N/A N/A. N/A 1993._ __ No 

                                                                                                           *~--------~

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class ~ Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

ID of Component Replaced: _,...N~A"-------~--~--~--~--~--~-~ Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases:

~--------------------------------------------------------------

ID of Replacement: 1MSE64 Condensate Chamber Name of Manufacturer: ----=C~o~n=n=e=x~P~i~*p~e=-=S~y=s~t=e=m..____ _ _ _ _ _ _ _ _ _ _ _ _~--- 43474 N/A N/A N/A =1~9~9~3..____,.._ No ial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? lacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class a_ e Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 8 OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by Public SeJ::vice Electric & Gas Co. - Nuclear Dept. CJP #PS93-077 (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) Public Sei:vice Electric and Gas Co. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Main Steam Nuclear Class I I 5.a: Componentrepa~ed,modffiedorre~aced _~ __E_6_5~,-~ __ E_6_6....,~~--E_6_7~,-~ __E_6_8_C_o_~_ensa _ _~ __ ~ _ _ _ _ _ _ _ _ _ _ __

b: Name of manufacturer Connex Pipe Systems c: Identifying nos. See Attachment N/A N/A N/A 1993 (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code See Attachment N/A N/A II (edition) (addenda) {Code Case(s)) (Code Class)

6. Section XI 1983 SUrnmer 83 NIA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N~/'--=A_,,____ _

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1989 1989 N/A
                                                  *ASME III/ANSI B31.7 1969 Ed. 1970 Add.                                             (edition)           (addenda)          (Code Case(s))
9. Design responsibilities - - = P S = - = E = - = - & G ' - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic ~ pneumatic D design pressure D** pressure 1400 psi Code Case(s)_~N..../~A~------

escription of work Installed new condensate chambers for #13 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: -~W~o=r~k~O=rd=er~~#~:~9~3~0~8~1=0~0=9~9_ _ _ _ _ _ _ _ _~De~f~i=c~i~en~cy.'1--~R=e""'po~rt~~#~:~N:..,.,.....IA~--------

Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 1 , 1!9_4 Date 1- -i--<-( PSE&G Co.-Nuclear Dept. 19,___f_L. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /-I and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                .                ~                     /      ,                                                Facto:ry Mutual                EfBr.        Assn.

Date /-2-j , 1~. Signed ~z:. lArvl-- Commissions NB fr1{ J:ttJ/.} 1UJ ]7J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

FORM NR3J:~~~;;;~;~,,*- Page _L of __,L 

                                              *: ;.'.ff:~:.;.;.:,;:~ca*d~~'rrt>b Package No.: PS93077
                                                ;;. ::;:~;:/:!::~\*~ .~'/ih{?* .< :._: .. -

Work performed by: Public service Elec:itric~:&-:..Gas'.-co. 1 Nuclear Dept. Foot of Buttonwood Road- Hancbcks Bridge, NJ 08038

2. Owner: Public Service Electric'&; Gas>;co.

Foot of Buttonwood Road',.- :Hanccicks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System: Main Steam Nuclear Class: --=I=I"----~
==================================================================

ID of Component Replacement: 1MSE65 Condensate Chamber Name of Manufacturer: Connex Pipe System 43471 N/A ~7.N~/~A~~~-~N~/7-A~=----1-9_9_3_____ N_o-------~ Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class ~ Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE66 condensate Chamber Name of Manufacturer: ......,;:C=o=n=n=e=x=--=P~i~p~e;_::S~y~s=t==e=m=--~~~~~~~~~~~~~~~~~- 43472 N/A N/A N/A =1=9=9~3~----=-~ No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .2._ Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================~===============================

ID of Component Replaced: _l::!Lb~~~~~~~~~~~~~~~~~~~~~~~~ e of Manufacturer: ial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: 1MSE67 Condensate Chamber Name of Manufacturer: Connex Pipe System 

                      ~~~==-=-=--~-=-"-=-~-=-'....~~~~~~~~~~~~~~~~~~

43473 N/A N/A N/A _1_9_9_3~-~ No *~~~~~~~~~~~ Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class ~- Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

ID of Component Replaced: -FN~A=--~~~~~~~~~~~~~~~~~~~~~~~~ Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: 1MSE68 Condensate Chamber Name of Manufacturer: ~C~o=n=n=e=x=--~P=i=p~e:;__:s~y~s~t~e~m~~~~~~~~~~~~~~~~~~- 43474 N/A N/A N/A =1=9=9=3~-~ No *~~~~~--:~~-:--::--=:- ial No. Nat'l. Bd. Jurist No. Other Year Built AS ME Code Stamp'd.? acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .2._ e Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

I rn .. -nwwrnrrT -or rw :; I r FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by Public SeJ:Vice Electric & Gas Co. - Nuclear Dept. CJP #PS93-078 {name) {repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 {address) {name) Foot of Buttonwood Road, Hancocks Bridge, N.J 08038 {address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, N.J 08038
4. System Main Steam Nuclear Class I I 5.~ Componentrepa~ed,modffiedorre~~ed~~~=E~6~94,~~~~~~~0~,~~~~~~1~,~~~~~~2~Co~~~=~~~~~~~~~~~~-------

b: Name of manufacturer Connex Pipe Systems c: Identifying nos. See Attachment N/A N/A N/A 1993 {mfr's. serial no.) {Narl.Bd.No.) Uurisdictional no.) {other) (year built) d: Construction Code See Attachment N/A N/A II (edition) {addenda) {Code Case{s)) (Code Class)

6. Section XI 1983 SUrrnner 83 N/A

{edition) {addenda) {Code Case{s))

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 =Nl--'/A~--

{edition) (addenda) {Code Case{s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1989 1989 N/A
                                                    *ASME III/ANSI B31. 7 1969 F.d. 1970 Add.                                                     (edition)                          {addenda)           {Code Case{s))
9. Design responsibilities _PS_E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic (8: pneumatic D design pressure D **pressure 1400 psi Code Case(s)_-=N~/-=A-=-------

scription of work Installed new condensate chambers for #14 rnain steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: -~W~o=r=k~O=rd=e=r'--"#__,,_:-=9=3-"'0=8_...l,,,_0,,,.09=9<<--_ _ _ _ _ _ _ _ _De.., ,.,_f.. _1.. ,c,,..1...,'
                                                                                                                       ' en~cy_~_...R_,,,,e"'1'po'°"""rt_,,.___,:/t,_.:'---'-N;¥-/.....A...___ _ _ _ _ __

Design Change Package #: lEC-3256 Pkg. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __ Date /-'2---Lr PSE&G Co. -Nuclear Dept. 19,~ Signed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,, ~ ~ 

                                                                                                                         # p- /                          -....                     Principal                 Engr.

{repair organization) {authorized representative) {title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of :MA. have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                                                       ,c; /                                                             Facto:ry Mutual ~. Assn.

Date r- J. 'i ' M_. 1 Signed L twL-(Inspector) Commissions ;Jp f"f<ft/ f .UJtf 4Il 1J (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.s

Page~ of~ FORM NR-1 ATTACHMENT Code Job Package No.: PS93078 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating station .,,;..

Foot of Buttonwood Road, Hancocks Bridge, NJ' 08038.

4. System: Main Steam Nuclear Class: I I

==============================================================================* ID of Component Replacement: 1MSE69 Condensate Chamber Name of Manufacturer: --C~o=n=n=e=x""'-'P=-=i_p~e-=s_y~s~t~e=m..__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 43471 N/A N/A N/A 1993 _N~o~--------- Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class 2,___ Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE70 Condensate Chamber Name of Manufacturer: ---=C=o=n=n=e=x"'-'P=-=ip==e-=S-v~s~t=e=m,.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 43472 N/A N/A N/A =1~9~9~3~- No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .a_ Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

ID of Component Replaced: _;=...N----=-A=-----------------------~ e of Manufacturer: ial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: 1MSE71 Condensate Chamber Name of Manufacturer: ---=C~o=n=n=e=x""'-'P=-=i_p=e--=s_y~s~t=e=m,.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 43473 N/A N/A N/A =1~9~9~3~- No*------,,---,------- Serial No. Nat'l. Bd. Jurist No. Other Year Built AS ME Code Stamp'd.? Replacement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .a_ Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

ID of Component Replaced: ----=N~A"------------------------~ Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Editibn Addenda, Code Class Code Cases: - - - ID of Replacement: 1MSE72 Condensate Chamber Name of Manufacturer: _-C~o=n=n=e=x"'-'P=-=ip_.=e--=s_y~s~t=e=m~------------------ 43474 N/A N/A N/A =1=9=9=3~-- No 

  ' al No. Nat'l. Bd. Jurist No.                       Other         Year Built     ASME Code Stamp'd.?

acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .a_ Cases:N/A ANSI B31.7 1969 Ed. 1970 Add

==================================================================

FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by Public Sei:vice Electric & Gas Co. - Nuclear Dept. CJP #PS93-079 (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name. address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Main Steam Nuclear Class II
5. a: Component repaired, modified or replaced 1C-MSG-2532A&B, 1C-MSG-2533A&B SUpports b: Name of manufacturer -~PS~E=&G~~-------------------------------------

c: Identifying nos. N/A N/A N/A N/A ---=1=-9=-93=-------- (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code See Attachment N/A N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 summer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N~/_A_ __

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                         *ANSI B3l.7/PS Spec S-C-MBCX:>-MLB-043, 1985                                                (edition)           (addenda)          (Code Case(s))
9. Design responsibilities _PS__E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure N/A psi Code Case(s)_~N'-"-/~A~------
11. Description of work Installed supports for condensate pots on #11 main steam header.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: -~W=o=r~k~O=rd=er~.... #~:_9=3=0=8=1=0=0=9~1~--------~De=f~i=*c=1='en=-=cy~~R=e""'po=rt~...... #~=~N:,_/A~-------

Desiqn Change Package #: lEC-3256 Pkg. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, . 199_4 9 ~ Signed_ _PSE&G Co. -Nuclear Dept. Principal Engr. Date /-3 19,~. _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on //-// , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, 

                                                                   -/

sed or implied, concerning the repair, modification or replacement described in this report. Furthermore. neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Factory Mutual Engr. Assn. Date /-J'.-'J , 1 M . Signed*tvnui.__ 9 ,,.,f-~- (Inspector) 

                                                                              /1 Commissionsµ/Jfl1t/MJA t</J)J}

(Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

Page _L of _L FORM NR-1 ATTACHMENT Code Job Package No.: PS93079 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 System: Main Stearn Nuclear Class: II ID~~~;=~~:;~~=~~=;:;~=~=~7==;=~================================================ 

           **'~hne  of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Starnp'd.? original Const. Code: Edition Addenda, Code Class 

         "-";.~~=-:::::~-------------------------------------------------------------------------
           'o of Replacement: lC-MSG-2532 A&B Supports
         ame of Manufacturer: PSE&G
                                      ---~~=---------------------------

A N/A N/A N/A =1=9=9=3~--,-~ No erial No. Nat'l. Bd. Jurist No. Other Year Built AS*----------- ME Code Starnp'd.? 

         . eplacernent Const. Code: ANSI B31. 7 1969        Edition 1970 Addenda, Code Class II
       ;/Code Cases :N/A                 PS Spec S-C-MBOO-MDS-043 1985

~,~;i:{***==============================================================================

Yfif ID of Component Replaced
~N~A=-------------------------

(\> -,,_.,, e of Manufacturer: 

*:/

rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Starnp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: ---- ID of Replacement: lC-MSG-2533 A&B Supports Name of Manufacturer: PSE&G N/A N/A 

                                      --='-=-'===-------------------------'----,-

N/A N/A =1=9=9=3~~~ No , ...**:~.- ,,.*. Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A~- PS Spec S-C-MBOO-MDS-043 1985 Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME 9Q.~r*.;. Original Const. Code: Edition Addenda,<C9.g: Code Cases: - - - - ~ ~ . _:;:~~,*:~~:~~}~ 

                                                        ---- ---- ----             .......J., .. ,,,~
         ~~-~;-;~~~~~~~~~~~--------------------------------------~-~~*~~~'.

Name of Manufacturer: ial No. Nat'l. Bd. Jurist No. Other lacernent Const. Code: e Cases: - - - - 

           -   ' FGRM NR-1 REPORT OF REPAIR 0 MODIFICATION [l OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2

rk performed by _.....:Pub::...=.::..:l=i=c=--=S:....:erv=-::...:i=-::ce:::.=......::E==l=-::ectr=.:=i:.=c=--=&_Gas==--...:Co=*=-----___!:Nu=c==l:.::e:::::e~ir:_!:::De=p~t:..!.._ ___:CJP~!:........:#11.:PS~9~3~-~0~8~0~---- (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, ID 08038 (address) 2.owner _ _Pub __l_1_'c_S_erv __1_'ce __E_l_ectr_--'-1='c_.....:and=--_Gas.c:__:_:_Co-=--*------------------------- (name) Foot of Buttonwood Road, Hancocks Bridge, ID 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, ID 08038
4. System Main Steam Nuclear Class I I 5.a: Componentrepa~ed,modifredorre~~ed _l_C_-_~ ___2_5_3_~_&_B~,_l_C_-_~_~_2_5_3_3_A_&_B_~~-~~~---------------

b: Name of manufacturer ___PS_E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ c: Identifying nos. _N~/A _ _ _ __ N/A N/A N/A 1993 (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code See Attachment N/A N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrmner 83 NIA (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 .....:N=-:../,_,,A=---

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                                      *ANSI B31. 7 /PS Spec S-C-MB'.JO-Mffi-043 1 1985 (edition)                                                                                                 (addenda)           (Code Case(s))
9. Design responsibilities __ PS_E_&G _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. Tests conducted: hydrostatic D pneumatic D design pressure O *"'Pressure N/A psi Code Case(s) _ _N~/_A _ _ _ _ __
11. Description of work Installed suppo~ for condensate pots on #12 main steam header.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ _ W_o_r_k_O_rd_er_~#~=-9~3~0~8=1~0~09~7~--------=De~f=i=c=ien=cy=.<-~R=e"""'po=rt~~#~:~N,_,,/~A~------

Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19-94 --- PSE&G Co.-Nuclear Dept. t1 pt ;;; . Principal Engr. Date j-3 19,~. Signed _ _ _ _ _ _ _ _ _ _ _ .?~L;,.4..., (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on //-I/ , 19 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or*connected with this inspection. 

                                                                                                /                                                                                      Factory Mutual Engr. Assn.

Date /- ,l LJ , 19 'f V. Signed. {. U~ Commissions It/ /J5t1t/ZJVA fiA1)J J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH _ 43229. NB-81 Rev.6 

       ' ~

Page _A_ of _A_ FORM NR-1 ATTACHMENT Code Job Package No.! PS93080 Work performed by: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

2. Owner: Public Service Electric & Gas Co.

Foot of Buttonwood Road, Han cocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System: Main Steam Nuclear Class: II
==================================================================

ID of Component Replaced: __;;..N~A=------------------------- Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: lC-MSG-2534 A&B Supports Name of Manufacturer: _,:.P~S=E=&=G=-------------------------- N/A N/A N/A N/A =1=9=9=3~---,.- No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code stamp 'd. ?* Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Addenda, Code Class II Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985

==================================================================

of Component Replaced: __;;..N..._.,.A=-------------------------- of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: lC-MSG-2535 A&B Supports Name of Manufacturer: --=P~S=E~&=G=-------------------------- N/A N/A N/A N/A =1=9=9~3~_,... No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Addenda, Code Class II Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985

==================================================================

ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of* Replacement: Name of Manufacturer: 

   'al No. Nat'l. Bd. Jurist No.       Other   Year Built         ASME Code Stamp'd.?

acement Const. Code: Edition Addenda, Code Class Code Cases: - - -

=====================================================================~

FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by Public Sel::vice Electric & Gas Co. - Nuclear Dept. CJP #PS93-081 (name) (repair organization's P.0. no., job. no.,etc.) Foot of Buttonwood Road, Hanccx::ks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hanccx::ks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Main Steam Nuclear Class II
5. a: Component repaired, modified or replaced 1C-MSG-2562A&B, 1C-MSG-2563A&B supports b: Name of manufacturer _ _ _ , , P S E & G ' - = = : = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

c: Identifying nos. N/A N/A N/A N/A __1=9=9=:;,,,;3=------- (mfr's. serial no.) (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code See Attachment N/A N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrnmer 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N_,,/_A_ __

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                             *ANSI B31.7/PS                        Spec        S-C-MBJO-MD3-043, 1985                                     (edition)                (addenda)        (Code Case(s))
9. Design responsibilities _PS=-=.::E:..:&G-=------------------------------------,----------
10. Tests conducted: hydrostatic D pneumatic D design pressure D ** pressure N/A psi Code Case(s)_--'N'""/'-'A=-=-------

escription of work Installed supports for condensate pots on #13 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _...!:Wc:::o::r_,,_..k,__O=rd=er=-_.#'-':'---"9'"""3,_,,0'""'8""1""0""'0""--99""------------"'De=f""i=c""ien""'-"'cy=-__.,R=e:;i:;po=rt'-"'--..ll.#_._:~N._,,/.....,A.....___ _ _ _ _ __

Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires act. 3, , 1994 PSE&G Co.-Nuclear Dept. Principal Engr. Date /- )' 19,--2:,L. Signed_ _ _ _ _ _~--------- .... (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri ht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on - / and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                 .                                       _                                                                          Factory Mutual Engr. Assn.

Date /-2-i.J , 1rfl!:/..-. Signed ~t[.,_, ~ CommissionsltJ/JSff'/fJUA AlfTJJ (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6

Page J _ of J _ FORM NR-1 ATTACHMENT Code Job Package No.: PS93081 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Han cocks Bridge, NJ 08038
4. System: Main Steam Nuclear Class: I I
==================================================================

ID of Component Replaced: -""'N_,__,_A=--~~~~~~~~~~~~~~~~~~~~~~~ Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: lC-MSG-2562 A&B Supports Name of Manufacturer: PSE&G __,=~~=-~~~~~~~~~~~~~~~~~~~~~~~~- N/A N/A N/A N/A =1=9=9=3~- No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Addenda, Code Class II Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985

==================================================================

ID of Component Replaced: _.:.;N"'-"A=--~~~~~~~~~~~~~~~~~~~~~~~~ ~ of Manufacturer: ~ Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: lC-MSG-2563 A&B Supports Name of Manufacturer: PSE&G 

                        .~~~-~~~~~~~~~~~~~~~~~~~~~~~~~-

N/A N/A N/A N/A__ =1=-99""""3=--___,- No*~~~~~~~~~~- Serial No. Nat'l. Bd. Jurist No. Other Year Built AS ME Code Stamp'd.? Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Addenda, Code Class II Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985

==================================================================

ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: Name of Manufacturer: 1 No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? cement Const. Code: ~~~~~~~~~- Edition Addenda, Code Class _ Cases: - - -

==================================================================
                                                                                            *- t                                                                                 ;  b ~ ::::

FORM NR-1 REPORT OF REPAIR D MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 rk performed by Public Service Electric & Gas Co. - Nuclear Dept. CJP #PS93-082 (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System Main Stearn Nuclear Class I I
5. a: Component repaired, modified or replaced 1C-MSG-2564A&B, 1C-MSG-2565A&B SUpports b: Name of manufacturer _ _ _ . P S - - = E = & G " " ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

c: Identifying nos. N/A N/A N/A N/A -~1=9~9~3_ _ __ (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code See Attachment N/A N/A II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrnrner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 =NL-'/A=-=-----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 1970 N/A
                                            *ANSI B31.7/PS Spec S-C-MB'.X>-MI:S-043, 1985                                                 (edition)           (addenda)          (Code Case(s))
9. Design responsibilities - = P S = = E = - = & G = - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
10. Tests conducted: hydrostatic D pneumatic D design pressure O**pressure N/A psi Code Case(s)_--'N=--"-/-=-A=--------

escription of work Installed supports for condensate pots on #14 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: -~Wi~o=r=k~O=rd=e=r~#~:~9=3=0=8=1=6=1=00~--------~De=f=1=*c""1""en,,,,._..,cy~_,,R,_,,,e""'po~rt....=.._,_#'"""':~N¥-/~A.___ _ _ _ _ __

Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement. 

                        **No Presei:vice Reauired                                                  Temn.       N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition.

Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4_ __ PSE&G Co.-Nuclear Dept. Principal Engr. Date I - ;J 19,__f_l._. Signed _ _ _ _ _ _ _ _ _ _ _ _ _ __ (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on //~/I , 19'J} and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be

  • n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date I - 2 if ' 19q'-/ 

                                      . Signed     rt.4./         /
                                                                 '2--    ~
                                                                           /

(Inspector) Commissions N8 Factory Mutual Engr. Assn. sr ft-/ f°N;4 rv:JJ?.J (Natl.Bd .No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

Page __L of __L FORM NR-1 ATTACHMENT Code Job Package No.: PS93082 performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

2. Owner: Public Service Electric & Gas co.

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038

3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038
4. System: Main Steam Nuclear Class: II
==================================================================

ID of Component Replaced: __N""-""A=-----------------,----------- Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Edition Addenda, Code Class Code Cases:

~-

ID of Replacement: lC-MSG-2564 A&B Supports Name of Manufacturer: PSE&G 

                       ~~~----------------------------

N/A N/A N/A N/A ~1~9~9~3~--,..-- No Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Addenda, Code Class II Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985

==================================================================

rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const~ Code: Edition Addenda, Code Class Code Cases: - - - ID of Replacement: lC-MSG-2565 A&B Supports Name of Manufacturer: PSE&G 

                       --""'~~=---------------------...;...._               ____

N/A N/A N/A N/A =1=9=9=3~-~ No 

                                                                   *---~-----~-

Serial No. Nat'l. Bd. Jurist No. Other Year Built AS ME Code Stamp'd.? Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Addenda, Code Class II Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985

==================================================================

ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code! Edition Addenda, Code Class Code Cases: - - - ID of Replacement: Name of Manufacturer: Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Const. Code: Edition Addenda, Code Class _

==================================================================

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION~ OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS f Pa e 1 o 1 ark performed by Public Service Electric & Gas Co. - Nuclear Dept. CJP #PS93-083 Rev.O (name) (repair organization's P.O. no .. job. no.,etc.) Foot of Buttonwocd Road. Hancocks Bridge, NJ 08038 (address)

2. Owner Public Service Electric an:l Gas Co.
              --=-======--===-=-==-==----=====:..====--==-==--===--=~=------------------------------

(name) Foot of Buttonwocd Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocd Road, Hancocks Bridge, NJ 08038
4. System Pressurizer Relief Tank Line SUpport Nuclear Class II 5.~ Componentrepa~ed,modffiedorre~aced~P~i~~~~~~~~~rt~~#~C~--~~~--5~----------------------~

b: Name of manufacturer In..c:;t.al 1 ed by J?SE&G c: Identifying nos. N/A N/A ~/A N/A Iruat,al led 1975 (mfr's. serial no.) (Nat'l.Bd.No.) Ourisdictional no.) (other) (year built) d: Construction Code Specification 69-6445-1974 None (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUnuner 83 N/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 N'--+/~A~--

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *See BelOW'._,_,__ _ _None
                                                                                    *Spec 696445 1974                                            (edition)          (addenda)           (Code Case(s))
9. Design responsibilities ~PS"-""E,,,.,,,&G,=._ _________________________________________
10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure N/A psi Code Case(s)_~N~o=n=e~------

escription of work M.o:lify pipe support C-RWS-5 (use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: _JW~o~rLk..,__~Ordi.w...~e~r~#~*~9L3..l...Ll~O~Ou7~1~4L7L__ _ _ _ _ _ _ _ __._ne=...f~i~c~iue~ncycn....¥-~R~e+po.11..1.1rt:_,__~#1t-o-:-N"""'a~n~e:.___ _ _ _ _ _ __ Design Change Package #: lEC-3054-2 Rev. O See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , H9-:;...4-=----

c. PSE&G Co. -Nuclear Dept. / / /  :. Principal Engr.
            -;+.£ Date ]'                       19, ?"'¥. Signed. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

(repair organization) 2 ~~ (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 

       ,n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
                ,..,....                                    ~                /      (,_                                                   Factory Mutual Engr. Assn.
                                                                ~ '7 ..,,,L--
       ')

Date J ,. 2) , 1rflL_. Signed

  • Commissions;\J,55%-i'f £v ;l ,if) 573
                                                             ~                (Inspector)                                       (Natl.Bd.No.(including   endorsements)s~te or province and n~rnber:

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S) ~ TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l r ~;======================================================================================.::=_============== ork performed by Public service Electric & Gas Co. - Nuclear Dept. CJP #PS93-088 Rev.a (name) (repair organization's P.O. no., job. no.,etc.)

  • Foot of Buttonwood Road, Hancocks Bridge, NT 08038 (address)

(name) Foot of Buttonwood Road, Hancocks Bridge, NT 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NT 08038
4. System Control Air Nuclear Class I I 5.~ Componentrepa~ed,modffiedorre~aced~P~i~pe~~~~~~rt~~~~~~~6~6~0~---------------------~

b: Name of manufacturer -~.,_,,,,,.,E.,&G.,,,.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ c: Identifying nos. N/A N/A N/A 1974 (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) (year built) d: Construction Code 69-6445/SG-SMFD-1 WA None II (edition) (addenda) (Code Case(s)) (Code Class)

6. Section XI 1983 SUrnmer 83 :t{/A (edition) (addenda) (Code Case(s))
7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 =N~/=A'----

(edition) (addenda) (Code Case(s))

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *NIA N/A None
                                                                                      *S-C--MB:X>-MCS-043                                          (edition)           (addenda)          (Code Case(s))
9. Design responsibilities ----"PS~E=&G"'-'-""-----------------------------------------
10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure N/A psi Code Case(s) __N~o~n~e~------
11. Description of work Replace 2 nuts on pipe support #P-CrAG-660.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 

           ~~~~~~~~~

12.Remarks: __Wuo~r~ka.__,.,Ord"'""'~e~r-----i#~:'---'9~3~0~6~1*5..u.1~3~5_ _ _ _ _ _ _ _ ____JDeL.&:O.f~jcl.i..Ljecnu~cy~~R~e~poa..urt._.__~#~:._,N~ounu.ce~------- Design Change Package #: lEC-3150-1 Rev. O See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19-=-9-=4=----- Date '2 - ~~ 19,-2£_. Signed._ _PS_E_&G __ eo_._-Nu_c_l_ear _ _De_p_t_.__ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual ce Co of MA have inspected the repair, modification or repla.cement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, 9 sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1 any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

         .                   c,, 1                                          c.* /                    .                                       Fc:cto:ry         Mutual ~.                  Assn.

Date J -2 ) ,1sh_. Signed ~'?My" "l,. l-c_J.__- Commissions/J~Jtz '/ J._,4/A 11153 7l (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) 1 This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rev.6}}

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