ML18100B034: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:FORM NIS-1 OWNER 1 S DATA REPORT . . FOR INSERVICE INSPECTIONS
{{#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
;.
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
: 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038
: 3. Plant Unit 1
: 3. Plant Unit 1
Line 1,901: Line 1,899:
r:                                                                                      (Inspector)                                        (Na:!.8d.No.(;nclud1rg          e~co*s"~en:s)s<ate o* P'OV;nce a~c c,c-,p~*:
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 .
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
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
Line 2,764: Line 2,761:
                       ** stem Inservice Leak Test                                                T
                       ** stem Inservice Leak Test                                                T
* Nor '"'
* 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 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 Authorization no.                  36      to use the "NR" stamp expires              Oct. 3,              , 19_9_4_ __

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}}

Retrieved from "https://kanterella.com/w/index.php?title=ML18100B034&oldid=2505590"