Text

ISI Activities - 90 Day Rept Eleventh Refueling Outage Salem Generating Station Unit 1
	ML18100B034
Person / Time
Site:	Salem
Issue date:	03/31/1994
From:	Lake L; Public Service Enterprise Group
To:	;
Shared Package
ML18100B033	List: ML18100B032; ML18100B034;
References
	NUDOCS 9404260399
	Download: ML18100B034 (180)
	v • d • e

.

L 2. 3 . 4. 5. 6. 7. 8. 9. FORM NIS-1 OWNER 1 S DATA REPORT ... FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77 .. National Board Number for Unit: N/A. Examination Dates: 08-17-92 through 02-02-94.

This report covers the examinations that were conducted during the 11th Refueling Outage. Components Inspected.

MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER APPURTENANCE OR INSTALLER OR INSTALLER PROVINCE NATIONAL #1 Reactor Vessel #11 Steam Generator

12 Steam Generator

13 Steam Generator

14 Steam Generator

1 Regen. Ht. Exch. #1 Rx. Coolant Filter Combustion Engineering Westinghouse Tampa Div. P.O. Box 19218 Tampa, FL 33616 II II II II II II Sentry Equip. Corp. Oconomowoc, WI Commercial Filters, Corp. Lebanon, IN SER. NO. NUMBER BOARD NO. 66201 Head 66101 Vessel N/A 20757 1003 N/A 68-10 1022 N/A 68-08 1023 N/A 68-09 1203 N/A 68-51 4195-A4 N/A 385, 386, 7, 8, 9 387 101238 N/A 1193 -----9404260399'

, 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. 3. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 4. 5. Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. 6. National Board Number for Unit N/A. 7. 9. Examination Dates: 08-17-92 through 02-02-94.

Components Inspected (cont'd):

MANUFACTURER COMPONENTS OR MANUFACTURER OR INSTALLER APPURTENANCE OR INSTALLER SER. NO. #1 Pressur-Delta Southern 1011 izer Chemical Volume & Control Piping System Component Cooling Sys. Containment Spray Piping System Mains team Piping sys. #11 RHR Heat Exchanger United Engineers

& Constructors (UE&C) 30 South N/A 17th st., Phila. PA 19101 UE&C N/A UE&C N/A UE&C N/A Engineers

& Sl5860-C Fabricators, Inc. Page 2 of 22 STATION OR PROVINCE NATIONAL NUMBER BOARD NO. N/A 68-8 N/A N/A N/A N/A N/A N/A N/A N/A N/A 122

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 3 . 4. 5. 6. 7. 9. owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Components Inspected (cont'd):

MANUFACTURER COMPONENTS OR MANUFACTURER OR INSTALLER APPURTENANCE OR INSTALLER SER. NO. Pressurizer UE&C N/A Relief Piping Sys. Pressurizer UE&C N/A Spray Sys. Reactor UE&C N/A Coolant Piping Sys Residual UE&C N/A Heat Removal System Service Water UE&C N/A System Steam Gen. UE&C N/A Feed Piping System Safety UE&C N/A Injection Piping Sys. Page 3 of 22 STATION OR PROVINCE NATIONAL NUMBER BOARD NO. N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

i.

2 . 3 . 4 . 5. 6 . 7. 10. 1.0 *

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Abstracts of Examinations:

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

Examinations were conducted by PSE&G as well as companies under contract to PSE&G. The following is a brief summary with further details found in the attached report and on file at the Salem Generating Station. Since nearly all inservice examination requirements can be found in Salem's Technical Specifications, this summary lists these requirements first arranged by Technical fication paragraph number followed by applicable NRC lars and Bulletins . Page 4 of 22 I 1.

2 . 3. 4. 5. 6. 7. 11.

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary 11.1 Technical Specification 4.0.5 -ASME XI (1983 Edition) During the Fall 1993 refueling outage, PSE&G, MQS and SwRI personnel performed nondestructive examinations (NDE) of selected Class 1, Class 2 and Class 3 nents at the Salem Unit 1 Generating Station. These examinations constituted the fourth inservice tion (ISI) of the second inspection interval of mercial operation.

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

Examinations were conducted on the following systems: Class .l Vessels Piping Pumps Pressurizer RPV Steam Generator

11 through #14 Chemical and Volume Control Reactor Coolant System Pressurizer Relief System Pressurizer Spray System Residual Heat Removal System Safety Injection System Reactor Coolant Pumps #12 and #14 Page 5 of 22

i.

2. 3. 4. 5. 6. 7. 11.

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required}

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (Cont'd} Integrally Welded Attachments Class .6. Vessels Piping Reactor Coolant Pumps #12 and #14 Safety Injection Head Tank #11 Reactor Coolant Filter Regenerative Heat Exchanger Main Steam System Steam Generator Feed System Containment Spray system Residual Heat Removal System Pressurizer Relief System Chemical Volume Control system Safety Injection System Integrally Welded Attachments Residual Heat Removal System Safety Injection System Main Steam System The following nonconformance was reported by SWRI: A PT examination on weld 4-SJ-1172-5 (Summary No. 131200}, revealed six (6) linear able indications.

CNF 1-1 was issued by SWRI and dispositioned by PSE&G as follows: After cosmetically blending these tions, a PT re-exam was performed with no linear indications identified.

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 lies noted, including boric acid accumulation, nuts seized on the stud or bolt, etc .. Work orders and/or deficiency reports were ed to document and correct all anomalies.

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 fied. 11.1.3 Visual Examination of Supports The Salem !SI Group conducted and/or nated visual examinations on seventeen (17) Class I, five (5) Class II and one hundred forty eight (148) Class III supports . Page 7 of 22

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 Chemical & Volume Control Component Cooling Containment Spray Residual Heat Removal Main Steam Pressurizer Relief Pressurizing Safety Injection Service Water There were no unacceptable indications fied. 11.1.4 System Pressure Tests System leakage exams were performed in ance with ASME Section XI on all Class I systems. A system leakage test was performed with the Reactor Coolant System in mode 3 (normal operating temperature and pressure) with the insulation installed.

No pressure boundary leakage was detected.

Minor mechanical age was identified and work requests were initiated for repairs. Thirty two (32) System Pressure Tests (SPT) were completed during a System Functional or Inservice Test on Nuclear Class 1, 2 and 3 components in accordance with ASME Section XI. No pressure boundary leakage was detected.

Work requests were initiated to correct minor mechanical leakage that was identified . Page 8 of 22

i.

2. 3. 4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (cont'd):

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

COMPONENT ID WELD # 174900 RH-3282-77F-A 175001 RH-3282-76F-A 175101 RH-3282-75F-A 175500 RH-3295-111F-A 179601 RH-3295-110F-A 179701 RH-3295-109F-A 184600 RH-3269-43F-A 184700 RH-3269-42F-A 184801 RH-3268-41F-A 190100 RH-3256-4F-A 190201 RH-3256-3F-A 190301 RH-3256-2F-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted. Preservice Examination was performed on Safety tion System piping weids, due to the replacement of two (2) orifices per DCP lEC-3260.

The welds that were replaced to facilitate the placement of the orifices are listed below: !SIC

SUMMARY

386600 386620 387100 387120 !SIC COMPONENT ID 2-SJ-2126-6R 2-SJ-2126-7R 2-SJ-2123-6R 2-SJ-2123-7R PSE&G WELD # SI-5-256B-A SI-5-257B-A SI-1-211C-B SI-1-212C-A The PT (PSI Baseline) was performed by MQS with no discrepancies noted. Page 9 of 22

' 1.

2. 3. 4. 5. 6. 7. 11. *

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (cont'd):

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

11. 3. 1 Overview 11. 3. 2 The original scope of Salem lRll outage was comprised of 20% bobbin and 20% top of hot leg tubesheet in all four Steam Generators.

In addition, a twelve hour* window was allotted for RPC testing of dented hot leg tube support plate Top of Tubesheet RPC Inspection The tube expansion in the Steam Generators at Salem Unit 1 were made using the WEXTEX ess (explosive expansions).

History of Wextex units has shown some cracking in the expansion transition.

Cracking of the WEXTEX region can be axial, circumferential or oblique in tation as detected by RPC. The extent of circumferential cracking and the extent to which an axial indication extends into the transition zone are critical measurements.

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

' 1 . 2. 3. 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

11. Examination Summary (cont'd):

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 tion. The entire length of this indication was contained within the WEXTEX transition, therefore the structural integrity limit of 0.41" was exceeded, prompting the 100% sion of this Steam Generator.

This tube also contained two circumferential indications at the top of the tubesheet.

Evaluation by Westinghouse determined that this tube quired stabilization.

One additional tube in this Steam Generator was evaluated for lization and determined that no stabilization was required.

Steam Generator

14 had no expansions of the Top of Tubesheet RPC inspection.

A total of 708 tubes were inspected which represents 20.9% of the Steam Generator.

11.3.3 Bobbin Inspection There were five different types of degradation detected during the bobbin inspection.

Four of these mechanisms were previously identified to some degree in Unit 1. They are: AVB WEAR All four Steam Generators have had some wear at the anti-vibration bars .. Steam Generator

11 had two tubes plugged because of this wear. COLD LEG THINNING All four Steam Generators have had thinning at peripheral tube cold leg support plate intersections.

Steam Generator

14 had one tube plugged because of this mechanism.

Page 11 of 22

' 1 .

2 . 3 . 4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (cont'd):

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

. 1. 2. 3. 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

11. Examination Summary (cont'd):

One new degradation mechanism was identified during lRll. This was ID INITIATED 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 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 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 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

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

' 1 .

2. 3. 4. 5. 6. 7. 11.

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1

owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (cont'd):

11.4 RPC of tube R3C59 at lH revealed an MAI. One of the axials was 1.742" long starting at 0.87" above the support plate. The other axial was o. 591'.' long, starting at o. 74" above the support plate. Both of these indications were determined to be OD indications rather than ID. RPC OF DENTED SUPPORT PLATE INTERSECTIONS Twelve hours were allocated for sample testing of dented support plate tions in each Steam Generator.

The 300 largest dents in each Steam Generator were selected for testing. The aim of this testing is to detect the presence of ferential indications.

Circumferential oriented indications can not be seen by bobbin probes. Due to time constraints and restrictions encountered within the tubes, none of the Steam Generators completed the 300 tube program. The number of tions inspected, ranged from 122 to 170. No indications were detected in this tion. Current Status of the Steam Generators At this time the total number of tubes plugged in the Salem Unit 1 Steam Generators are as follows: Generator

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

i. 2. 3 . 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)

N/A. commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

11. Examination Summary (cont'd):

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

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 Left (max path) of 26,372.0 SCCM was ured through all Type "B" and "C" tions. Page 15 of 22

' 1 .

2. 3. 4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (cont'd):

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

11.6.2 Results The combined As-Found leakage for these locks was 4,925.0 SCCM. After maintenance, the combined As-Left leakage for the airlocks was 5,860.0 SCCM. Both of these measured combined leakage rates satisfies the Technical Specif cation acceptance criteria of 0.05 La (10,812 SCCM) . 11.7 Technical Specification 4.7.9. (a) "Visual Inspection of Hydraulic and Mechanical Snubbers" 11. 7. 1 Summary The Salem ISI Group conducted visual tions on twenty four (24) hydraulic and one hundred and eleven {111) mechanical snubbers.

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 stalled received a satisfactory "As-Left" visual examination.

Page 16 of 22

* ' 1 . 2 . 3 . 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED' BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

11. Examination summary (cont'd):

11.8 Technical Specification 4.7.9 (c) "Functional Testing of Selected Hydraulic and Mechanical Snubbers" 11.8.1 summary -Hydraulic Snubbers 11.8.2 A. Per Technical Specifications, 10% of the installed hydraulic snubbers as well as all previous outage functional test failures are required to be tested. The 10% sample included one 200 KIP Main Steam snubber and two 1000 KIP Steam Generator snubbers.

There were no previous outage test ures. B. The 10% sample of hydraulic snubber (small size) included one (1) Lisega 3018 . There were no noted discrepancies in the Technical Specification sample. Summary -Mechanical snubbers Per Technical Specifications, 10% of the total installed mechanical snubbers as well as ous outage functional test failures were tested utilizing the WYLE Model 150 Snubber Testing machine. The 10% sample is broken down by *snubber category size (small, medium and large) with 10% from each size selected each outage. All selected snubbers are detailed below: A. The 10% sample of the medium size snubbers included two (2) PSA-l's and nine (9) PSA-3 's. B. The 10% sample of the large size snubbers included one (1) PSA-35. C. Due to previous outage failures, 100% of the small size snubbers (PSA-1/4 1 s, PSA-1/2) are tested each outage. This ed in tests being performed on.one Model 1/4 and three Model 1/2. Page 17 of 22

. 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 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 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 l 1 .

2. 3. 4. 5. 6. 7. 11.

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (cont'd):

There were several S/G (inlet & outlet) mary Manway washers replaced, due to deep galling. These washers were replaced in kind. A VT revealed wastage on the shank of one bolt on #14 S/G Outlet manway. This bolt was replaced.

There were several PZR Primary Manway bolts replaced, due to non service induced anomalies found during the VT. NOTE: 100% of all the S/G and PZR manway bolts were examined during this ing outage. There were no other unacceptable indications identified . 11.11 NRC Bulletin 88-08 "Thermal Stresses in Piping neated to Reactor Coolant System". 11.11.1 Summary Southwest Research Institute

{SwRI), and MQS under the direction of the Salem ISI Group, performed augmented ultrasonic and dye trant examinations on nine (9) 1. 5 11 Safety Injections welds, two (2) 2 11 Chemical Volume Control welds and two (2) 3 11 Chemical Volume Control welds. NOTE: Seven (7) components had the 88-08 exams waived, due to the replacement of the 11 through 14 SJ17 valves (DCP lE0-2309) . The associated replacement welds were not ultrasonically examined as required by NRC Bulletin 88-08. NRC Bulletin 88-08 is concerned with a service induced condition, which would not exist with these new welds. There were no unacceptable indications fied. Page 19 of 22 L FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 3. Plant Unit 1 4. owner's Certificate of Authorization (if required)

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 tions on all existing surge line pipe supports / HEBA restraints and their associated tion. A total of ten (10) supports were examined.

There were no unacceptable indications fied. 11.13 NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants". 11.13.1 Summary Measurements were taken at one hundred and sixty four (164) locations to identify possible pipe erosion/corrosion.

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) nent received external weld "build-up".

Other than the aforementioned areas, no other 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

' 1.

2. 3

4. 5. 6. 7. 11. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, N.J. 08038 Plant Unit 1 owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 7/1/77. National Board Number for Unit N/A. Examination Dates: 08-17-92 through 02-02-94.

Examination Summary (cont'd):

11.14.2 Results All four valves had an acceptable leak rates below the test acceptance criteria of 30,000 SCCM. No discrepancies were noted. 11.15 Summary NuReg 0578 -TMI Lessons Learned -A. Twenty-seven (27) System Pressure Tests were pleted per NUREG 0578 commitments.

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

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

Date J-l/ --------,

Commissions Page 22 of 22 National Board, State, Province and No.

- PUBLIC SERVICE ELECTRIC & GAS CO. SALEH NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.O) SECTION XI COMPLETE COXPORERTS SECORD INTERVAL, SECORD PERIOD, SECORD OUTAGE (93RF) Karch 4, 1994 REVISION 0 Date Date Date i3ld.1'1.

I -of<ifaL/'

DATE: 03/04/94 ' REVISIO'H:

0 EACTOR PRESSURE VESSEL

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND* INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: CIRCUMFERENTIAL WELDS CREF. DWG. NO. A*1) 002001 1*RPV-7042 VESSEL TO FLANGE B-A B1.30 UT1.5 UT5.7 UT12.5 THREADS IN FLANGE (REF. DWG. NO. A*2) 003700 1*RPV*LIG 1 THRU 54 B-G-1 B6.4D UTO REACTOR VESSEL SUPPORT CREF. DWG. NO. A-1> 003751 1-RPV-11CLSUPPORT SLIDING SUPPORT 003752 1-RPV-12HLSUPPORT SLIDING SUPPORT INTERIOR (REF. 1?WG-. NO. *A-1) 004310 RPV INTERNAL SURFACE F-A F2.10 F-A F2.10 VT-3 VT-3 B-N-1 VT-3 B13.10 CONTROL ROD DRIVE HOUSINGS (REF. DWG. NO. A-2B> VS1SSISRCE0094Q X * -PERFORM MANUAL UT FROM THE SURFACE OF X THE VESSEL FLANGE ON VESSEL TO X FLANGE WELD (#1 THRU 54, STUD HOLES). W.0.#931121035 TO PERFORM NOE. **53-SAM/109-SAM**

VS1SSISRCE0009Q X --EXAMINE LIGAMENTS

18 THRU #54. S1SSISZZ0020Q S1SSISZZ0020Q VS1SSISZZ002QQ W.0.#931121035 TO PERFORM NOE. **7-1.25-8-CS-60-SAM** X --THIS EXAM IS TO BE COORDINATED WITH THE SAFE END WELD EXAMINATIONS ON THE #11 COLD LEG. W.O. # 931121035, TO PERFORM NOE. X --THIS EXAM IS TO BE COORDINATED WITH THE SAFE END WELD EXAMINATIONS OF THE #12 HOT LEG. W.0.# 931121035, TO PERFORM NOE. X --SWRI TO PERFORM VT-3 INSPECTION.

W.0.#931121035 TO PERFORM NOE *. FOR SMD TO SUPPORT THE RPV VT, SEE W.0.# 930601189.

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

, DATE: ,03/04/94 REVISION:

0 .PRESSURIZER

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION BOLTING CREF. DWG. NO. A-3) 007820 PZR BOLTING-HANWAY

- SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASHE SEC. XI CATGY EXAM ITEM *No METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 2 B-G-2 B7.21 VT-1 (ISi) SCSSISZZ0010Q VT-1 (PSI) MT VSHSSSPZZ0202Q --X A FLORESCENT MT EXAM TO BE PERFORMED

?ER X --NRC BULLETIN 82-02. MQS TO PERFORM THE X --MT AND PSE&G TO PERFORM THE VT. W.O. #920401058

& 931121035 TO PERFORM NOE. SEVERAL BOLTS WERE REPLACED PER CJP #S-93-254

& w.o. #930401183

DATE: 03/04/94

REVISION:

0 TEAM GENERATOR 11

SUMMARY

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

, DATE: ,03/04/94 REVISION:

0 STEAM GENERATOR 12

SUMMARY

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

& 931105031 TO PERFORM NOE. X A FLORESCENT MT EXAM TO BE PERFORMED PER X --82-02. MQS TO PERFORM THE MT AND PSE&G TO PERFORM THE VT. W.O. #931121035

& 931105031 TO PERFORM NOE

DATE: 03/04/94 : REVISION:

0 TEAM GENERATOR 13

SUMMARY

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

, DATE: ,03/04/94 REVISION:

0 .STEAM GENERATOR 14

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION BOLTING (REF. DWG. NO. A-7) 011450 14-STG-OMB BOLTS-OUTLET MANWAY 011475 14-STG-IMB BOLTS-INLET MANWAY "'C.* ** ** SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 6 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI CCJIPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-G-2 B7.30 B-G-2 B7.30 VT-1 MT VT-1 MT PROCEDURE SCSSISZZ0010Q VSHSSSPZZ0202Q SCSSISZZ0010Q VSHSSSPZZ0202Q N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** x X A FLORESCENT MT EXAM TO BE PERFORMED PER 82-02. MQS TO PERFORM MT & PSE&G TO PERFORM VT. W.O. #931121035

& 931105033 TO PERFORM NOE. #14CL BOLT #16 WAS FOUND TO HAVE WASTAGE ON BOLT SHANK. CJP # S-93-262 REPLACED BOLT W/ SATISFACTORY PSI VT. X A FLORESCENT MT EXAM TO BE PERFORMED PER X --82-02. MQS TO PERFORM THE.MT & PSE&G TO PERFORM VT. w;o. #931105033

& 931121035 TO PERFORM NOE.

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 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 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 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 REVISION:

0 PRESSURE RELIEF SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION

4-PR-1100

{REF. DWG. 026600 4-PR-1100-8 PIPE TO TEE 3-PR-1107

{REF. DWG. 027400 3-PR-1107-6 PIPE TO ELBOW 027600 3-PR-1107-8 PIPE TO ELBOW NO. A-162 NO. A-162 3-PR-1106 CREF. DWG. NO. A-17) 028500 3-PR-1106-3 ELBOW TO PIPE SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H CATGY EXAM E 0 E REMARKS ITEM NO METHOD PROCEDURE c M R **CALIBRATION BLOCK** PAGE: 8 ----------

B-J B9.11 B-J B9.21 B-J B9.21 B-J B9.21 PT UT45 UT45T UT45TAN PT PT PT VS1SSISZZ0003Q VS1SSISZZ0014Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q x --W.0.#931121035 TO PERFORM NOE. x x --x **4-SS-160-.533-28-SAM-Rl"*

x W.0.#931121035 TO PERFORM NDE. X --W.O. 931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NDE.

' DATE: , 03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 10 REVISION:

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

COOLANT SYSTEM SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

SUMMARY

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

0 COOLANT SYSTEM

SUMMARY

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

- 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

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 REVISION:

0 SAFETY INJECTION SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION

4*SJ-1172

{REF. DWG. NO. A*75l 131200 4-SJ-1172-5 ELBO\I TO PIPE 133800 4-SJ-1172-28 TEE TO REDUCER 3-SJ-1192

{REF. DWG. NO. A-722 134700 3-SJ-1192-BA PIPE TO PIPE 2-SJ-1147 CREF. DWG. NO. A-78) 141500 2-SJ-1147-8FB FLANGE BOLTING 2-SJ-1137 CREF. DWG. NO. A-802 147900 2-SJ-1137-10FB FLANGE BOLTING SALEM NUCLEAR PO\IER STATION UNIT* 1 PAGE: 13 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY ITEM NO B-J B9.11 B-J B9.11 B-J B9.21 B-G-2 B7.50 B-G-2 87.50 EXAM METHOD PROCEDURE

PT VS1SSISZZ0003Q PT UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UTOL VS1SSISZZ0018Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q VT-1 SCSSISZZ0010Q VT-1 SCSSISZZ0010Q N 0 0 G T R E H E 0 E REMARKS c M R **CALIBRATION BLOCK** .----------------------------------------

x W.0.#931121035 CNDE). THE PT EXAM x --REVEALED 6 LINEAR RECORDABLE

-x -INDICATIONS.

DURING THE RELEVANCY x DETERMINATION PROCESS, SURFACE x CONDITIONING PROCEEDED A.RE-EXAM WITH NO LINEAR INDICATIONS IDENTIFIED.

UT45 GEOMETRIC, DUE TO WELD COUNTERBORE.

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

x W.0.#931121035 TO PERFORM NOE. THE UT45 x INDICATION IS A GEOMETRIC REFLECTOR FROM -x -THE WELD ROOT. x --x --**4-SS-160-.533-28-SAM-R**

x --W.0.#931121035 TO PERFORM NOE. X --W.O.# 920810139

& 931121035.

X --W.0.# 920810145

& 931121035.

2-SJ-1128 CREF. DWG. NO. A-83.84,852 155500 2-SJ-1128-2FB FLANGE BOLTING B-G-2 B7.50 VT-1 SCSSISZZ0010Q X --W.0.# 920810149

& 931121035.

, DATE: , 03/04/94 REVISION:

0 SAFETY INJECTION SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION_

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

B-J B9.40 B-J B9.40 A-E NB88-08 A-E NB88-08 PT PT VT-1 PT PT PT UT PT UT VS1SSISZZ0003Q VS1SSISZZ0003Q SCSSISZZ0010Q VS1SSISZZ0003Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q X --W.O. #931121035 TO PERFORM NOE. THIS WELD REPLACES

SUMMARY

157900, DUE TO HANGER INTERFERENCE

. X --W.O. #931121035 TO PERFORM NOE. THIS EXAM REPLACES

SUMMARY

159100, DUE TO ALARA CONCERNS.

SUMMARY

159100 WAS LOCATED IN THE DECAY TUNNEL. X --W.0.# 920810151

& 931121035.

x --W.O. #931121035 TO PERFORM NOE. THIS WELD REPLACED

SUMMARY

174100, DUE TO A HANGER OBSTRUCTION.

x --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-184 & W.0# 920508129.

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**

x --88-08 EXAMS WAIVED, REPLACEMENT.

W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS DUE TO THE REPLACEMENT OF THIS IJELO PER DCP 1E0-2309, CJP# S-93-184 & W.0# 920508129.

- 1.5-SS-COUP-111-SAM**

,DATE: 0,3/04/94 REVISION:

0 INJECTION SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION . SALEM NUCLEAR PO\IER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 15 1.5-SJ-1142 CREF. DWG. NO. A-89.90.91) 179500 1 1/2-SJ-1132-39R PIPE TO VALVE 179601 1 1/2-SJ-1132-40R VALVE TO PIPE 179701 PIPE TO ELBOW 179801 1 1/2-SJ-1132-42 ELBOW TO PIPE ** B-J B9.40 PT A-E PT NB88-08 UT A-E PT NB88-08 UT A-E PT NB88-08 UT45 UT45T UT70 VHSSSSPZZ0206Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q VHSSSSPZZ0206Q VS1SSISZZ0016Q X --PSI BASELINE EXAMINATION.WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0# 921117149.

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-93-183 & .W.0# 921117149.

- 1. 5-SS-COUP-*111-SAM**

X --88-08 EXAMS WAIVED, REPLACEMENT.

x x x x W.0.#931121035 TO PERFORM NOE. PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD PER DCP 1E0-2309, CJP# S-93-183 & W.0# 921117149.

- 1.5-SS-COUP-111-SAM**

EXAMINED PER NRC BULLETIN 88-08. W.O. #931121035 TO PERFORM NOE. **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 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)

INJECTION SYSTEM SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H

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:

REVISION:

0 COOLANT PUMP 12

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 18 INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 191800 12*PMP*1LG LUG 191850 12-PMP-2LG LUG 191900 12*PMP*3LG LUG B-K-1 PT B10.20 B-K-1 PT B10.20 B*K-1 B10.20 PT PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 192101 12-PMP*FLW A-E PUMP MOTOR FLYWHEEL (IN-PLACE)

RG1.14 ** UTOL UT45 VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0001Q X *

W.0.#931121035 TO PERFORM NOE. LIMITATION:

THE EXAM IS LIMITED TO 72% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X -* W.0.#931121035 TO PERFORM NOE. LIMITATION:

THE EXAM IS LIMITED TO 72% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X *

W.0.#931121035 TO PERFORM NOE. x x LIMITATION:

THE EXAM IS LIMITED TO 76% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. PERFORM IN-PLACE UT EXAMINATION PER PER NRC REGULATORY GUIDE 1.14 & W.O. #931121035 ON RCP MOTOR FLYWHEEL S/N 3S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO THE BORE AND BOLT HOLES. **42-SAM**

DATE: 03/04/94 REVISION:

0 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 19 COOLANT PUMP 14 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION ASME SEC. XI CATGY EXAM ITEM NO METHOD INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. A-98) 193400 14-PMP-1LG LUG 193450 14-PMP-2LG LUG 193500 14-PMP-3LG LUG B-K-1 PT B10.20 B-K-1 .PT B10.20 B-K-1 PT B10.20 PUMP MOTOR FLYWHEEL CREF. DWG. NO. A-98) 193701 14-PMP-FLW A-E UTOL . PUMP MOTOR FLYWHEEL (IN-PLACE)

RG1.14 UT45 ** PROCEDURE VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0001Q N 0 O G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.0.#931121035 TO PERFORM NOE. LIMITATION:

THE EXAM IS LIMITED TO 77% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X --W.0.#931121035 TO PERFORM NOE. LIMITATION:

THE EXAM IS LIMITED TO 74% COVERAGE, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X --W.0.#931121035 TO PERFORM NOE. LIMITATION:

THE EXAM IS LIMITED TO 76%, DUE TO THE PUMP BRACING AT THE BOTTOM OF THE LUG. X PERFORM IN-PLACE UT EXAMINATION PER NRC X --REGULATORY GUIDE 1.14 & W.O. #931121035 ON THE RCP MOTOR FLYWHEEL S/N 2S-76P917 "TOP SIDE ONLY". LIMITED UT, DUE TO BORE AND BOLT HOLES. **42-SAM**

, DATE: ,03/04/94 REVISION:

0

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION VALVE BODIES 193870 12 SJ 55 VB ON LINE 10-SJ-1121 BOLTING CREF. DWG. NO. 194100 1 CV 78 ON LINE 3-CV-1133 BOLTING 194700 1 PR 1 ON LINE *3-PR-1106 194800 1 PR 2 ON LINE 3-PR-1107 195400 1 PS 1 ON.LINE 4-PS-1111 195500 1 PS 3 ON LINE 4-PS-1131 197000 11 SJ 43 ON LINE 6-SJ-1112 A-10> SALEM NUCLEAR PO\IER STATION UNIT 1 PAGE: 20 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION xr COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-M-2 VT-3 B12.50 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 B-G-2 VT-1 B7.70 PROCEDURE S1SSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZo010Q SCSSISZZ0010Q SCSSISZZ0010Q N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.O. 931121035 TO PERFORM NDE. --x W.0.# 920810209 AND 931121035 TO PERFORM NDE. ONE (1) STUD WAS FOUND WITH INADEQUATE THREAD ENGAGEMENT.

A DR WAS ISSUED TO SYSTEM ENGINEERING.

w.o. #93100204 CORRECTED THE THREAD ENGAGEMENT PROBLEM. A SA Tl S FACTORY RE-EXAM WAS PERFORMED. x --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO DCP 1EC-3219-1, CJP# PS-93-053

& W.0.# 930126150.

NEW STUDS AND NUTS WERE INSTALLED.

x --PSI BASELINE 'EXAMINATION WAS PERFORMED, DUE TO DCP 1EC-3219-1, CJP# PS-93-054

& W.0.# 930126150.

NEW STUDS AND NUTS WERE INSTALLED.

x --THE BOLTING WAS REPLACED PER 1EC-3249-1/PS-93-056/930708108

& 931121035.

x --THE BOLTING WAS REPLACED PER 1EC-3249-1/PS-93-057/930708111

& 931121035.

x --W.0.# 920810155 AND 931121035 TO PERFORM NDE.

, DATE: 03/04/94 REVISION:

0

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION BOLTING CREF. DWG. NO. A-68) 197900 12 SJ 43 ON LINE 6-SJ-1122 BOLTING CREF. DWG. NO. A-56) 198200 12 SJ 55 ON LINE 10-SJ-1121 198300 12 SJ 56 ON LINE 10-SJ-1121 BOLTING CREF. DWG. NO. A-66) 198800 13 SJ 43 ON LINE 6-SJ-1132 BOLTING CREF. DWG. NO. A-67) 199200 13 SJ 156 ON LINE 6-SJ-1131 BOLTING 199500 14 RH 27 ON LINE 8-SJ-1145 199600 14 SJ 43 ON LINE 6-SJ-1142 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 21 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASHE SEC. -XI CATGY EXAM ITEM NO METHOD B-G-2 B7.70 B7.70 B-G-2 B7.70 B-G-2 B7.70 B-G-2 B7.70 B-G-2 B7.70 B-G-2 B7.70 VT-1 VT-1 VT-1 VT-1 VT-1 VT*1 VT-1 PROCEDURE SCSSISZZ001QQ SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.0.# 920810158 AND 931121035 TO PERFORM NOE. --x W.0.# 920810195

& 931121035 TO PERFORM 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 #S-93-250.

x ---W.0.# 920810203

--x W.0.# 920810161

& 931121035 TO PERFORM NOE. BORON RESIDUE WAS FOUND ON SEVERAL STUDS. W.O. #931026136 REMOVED THE BORON AND A SATISFACTORY VT RE-EXAM WAS PERFORMED.

x --W.0.# 920810173-x --THE BOLTING MATERIAL WAS REPLACED IH ACCORDANCE WITH CJP #S-93-249

& W.O. #940326008.

x --W.0.# 920810162 AND 931121035 TO PERFORM NOE.

DATE: 03/04/94 'REVIS1014:

0

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION BOLTING (REF. DWG. NO. A-54) 199700 14 SJ 54 ON LINE 10-SJ-1141 199800 14 SJ 55 ON LINE 10-SJ-1141 199900 14 SJ 56 ON LINE 10-SJ-1141 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 22 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD B-G-2 B7.70 B-G-2 B7.70 B-G-2 87.70 VT-1 VT-1 VT-1 PROCEDURE SCSSISZZ0010Q SCSSISZZ0010Q SCSSISZZ0010Q N 0 0 G T R E H E 0 E. REMARKS C M R **CALIBRATION BLOCK** --X W.0.# 920810207

& 931121035 TO PERFORM NOE. THE VT REVEALED BORON RESIDUE ON THE STUDS. W.O. #931013197 WAS INITIATED TO CLEAN OFF THE BORON. AFTER THE BORON WAS REMOVED A SATISFACTORY VT-1 EXAM WAS PERFORMED. X --W.0.# 920810201* --X W.0.# 920810206

& 931121035 TO PERFORM 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 REVISION:

0 TANKS, VESSEL 11

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\JER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASHE SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 23 CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-4) 204900 11-HT-1 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE. UPPER HEAD TO SHELL C1.20 UTOW --x LIMITATION:

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 REVISION:

0

REACTOR COOLANT FILTER

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 2 SECTION XI CC>>4PLETE CC>>4PONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 24 CIRCUMFERENTIAL WELDS CREF. DWG. NO. B-6) 205020 1-RCF-1 C-A UTOL VS1SSISZZ0018Q x W.0.#931121035 TO PERFORM NOE. UPPER HEAD TO FLANGE C1.20 UTOW x LIMITATION:

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 REVISION:

0 HEAT EXCHANGER

SUMMARY

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

x x W.0.#931121035 TO PERFORM NOE. THE UT45 x AND UT60 INDICATIONS ARE

-x -REFLECTORS FROM THE WELD ROOT. x -x -**9.5-SS-X-.750-86-SAM**

x

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION ASME SEC. XI CATGY EXAM ITEM NO METHOD INTEGRALLY WELDED SUPPORTS CREF. DWG. NO. B-8) 205170 11-RHRHEX-1VS VESSEL SUPPORT 205180 11-RHRHEX-2VS VESSEL SUPPORT c-c C3.10 c-c C3.10 PT PT PAGE: 26 REMARKS PROCEDURE

- CALIBRATION BLOCK** VS1SSISZZ0003Q X --W.0.#931121035 TO PERFORM NOE. VS1SSISZZ0003Q X --W.0.#931121035 TO PERFORM NOE.

, 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 M R **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 ' REVISION:

0 MAIN STEAM SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\IER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERia>, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO-METHOD PROCEDURE

_ N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 28 32-MS-2141 CREF. DWG. NO. B-25) 227600 32-MS-2141-1 NOZZLE TO REDUCER 32-MS-2121 CREF. DWG. NO. B-27> 229900 32-MS-2121-2PS-1 PIPE SUPPORT 30-MS-2141

{REF. 232000 30-MS-2141-1 REDUCER TO ELBOW 232040 30-MS-2141-1LD-I LONGITUDINAL 232080 30-MS-2141-1LD-O LONGITUDINAL DWG. NO. B-25) C-F-2 C5.51 c-c C3.20 C-F-2 C5.51 C-F*2 C5.52 C-F-2 C5.52 MT UT45 UT45T MT MT UT45 UT45T MT UT45 UT45T MT UT45 UT45T VS1SSISZZ0002Q X VS1SSISZZ0017Q

X x --W.0.#931121035 TO PERFORM NOE. **32*CS-XX-1.618-47-SAM**

VS1SSISZZ0002Q X --W.0.#931121035 TO PERFORM NOE. VS1SSISZZ0002Q x --W.0.#931121035 TO PERFORM NOE. THE UT45 VS1SSISZZ0017Q

-x -INDICATIONS ARE GEOMETRIC REFLECTORS x FROM THE WELD ROOT. **PL-1.5-CS-65-SAM**

VS1SSISZZ0002Q x --W.0.#931121035 TO PERFORM NOE. EXAMINE VS1SSISZZ0017Q x 2.5T OF WELD LENGTH. x **PL-1.5-CS-65-SAM**

VS1SSISZZ0002Q x --W.0.#931121035 TO PERFORM NOE. -EXAMINE VS1SSISZZ0017Q x 2.5T OF WELD LENGTH. x **PL-1.5-CS-65-SAM**

, DATE: .03/04/94 REVISION:

0 PRESSURE RELIEF SYSTEM

SUMMARY

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

SUMMARY

254400, DUE TO HANGER INTERFERENCE.

EXAMINED 2.5T OF THE INTERSECTING LONGITUDINAL SEAM ON THE UP STREAM AND DOWN STREAM SIDE. **31-SAM/66-SAM**

' DATE: P3/04/94 REliISION:

0 ESIDUAL HEAT REMOVAL SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION 263294 14-RH-2114-16PS-2 PIPE SUPPORT 263296 14-RH-2114-16PS-3 PIPE SUPPORT .,..,.. 14-RH-2114-16PS-4 PIPE SUPPORT 263304 14-RH-2114-18 FLANGE TO PUMP "'" 14-RH-2112 CREP. DWG. NO. 263384 14-RH-2112-29 TEE TO PIPE ** SALEM NUCLEAR POWER STATION UNIT 1 PAGE: OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOO c-c C3.20 c-c C3.20 c-c C3.20 C-F-1 PT PT PT PT PROCEDURE VS1SSI.SZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q VS1SSISZZ0003Q N 0 0 G T R. E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --W.0.#931121035 TO PERFORM NOE. x --W.0.#931121035 TO PERFORM NOE. x --W.0.#931121035 TO PERFORM NOE. x W.0.#931121035 TO PERFORM NOE. 30 CS.11 UT45T VS1SSISZZ0014Q x LIMITATION:

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**

B-46> C-F-1 PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. CS.11 UT45 VS1SSISZZ0014Q x EXAMINATION INCLUDES 2.ST OF THE UT45T x INTERSECTING LONGITUDINAL SEAM ON THE UT45TAN x DOWN STREAM SIDE. **14-SS-40-.438*79-SAM**

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 M R **CALIBRATION BLOCK** ------------------------------

14-SJ-2124 263716 14-SJ-2124-1 VALVE TO ELBOW 263718 14-SJ-2124-HD-I LONGITUDINAL 263no 14-SJ-2124-1LD-O LONGITUDINAL l2-SJ-2152 263830 12-SJ-2152-5 ELBOW TO PIPE 263896 12-sJ-2152-36 PIPE TO PIPE 263898 12-SJ-2152-36PS-1 PIPE SUPPORT 263900 12-SJ-2152-36PS-2 PIPE SUPPORT DWG. NO. DWG. NO. "<* B-52) C-F-1 C5.11 C-F-1 C5.12 .C-F-1 B-54) C5.12 C-F-1 C5.11 C-F-1 C5.11 c-c C3.20 c-c C3.20 PT VS1SSISZZ0003Q . UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN PT VS1SSISZZ0003Q PT VS1SSISZZ0003Q x W.0.#931121035 TO PERFORM NOE. x LIMITATION:

EXAM LIMITED TO 95X, DUE TO x CONFIGURATION OF VALVE. x **14-SS-40-.438-79-SAM**

x W.0.#931121035 TO PERFORM NOE. EXAMINE x 2.5T OF WELD LENGTH. x x **14-SS-40-.438-79-SAM**

x W.0.#931121035 TO PERFORM NOE. x -.;. EXAMINATION INCLUDED 2.5T OF THE x INTERSECTING LONGITUDINAL SEAM DOWN x STREAM. **12-SS-40-.377-31-SAM**

x W.0.#931121035 TO PERFORM NOE. EXAM -x -2.5T OF LONG SEAM ON BOTH SIDES. THE x UT45 INDICATIONS ARE GEOMETRIC x REFLECTORS FROM THE INSIDE .SURFACE.

- 12-SS-40-.377-31-SAM**

x --W.0.#931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NOE.

DATE: 03/04/94 REVISION:

0 .SAFETY INJECTION SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO'JER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOO PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 12-SJ-2152 CREF. DWG. NO. B-54)

263904 12-SJ-2152-36PS-4 PENETRATION TO PIPE ** c-c C3.20 PT VS1SSISZZ0003Q X --W.0.#931121035 TO NOE. 32

, DATE: !>3/04/94 REVISION:

0 CONTAINMENT SPRAY

SUMMARY

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

SUMMARY

355400, DUE TO A UT45T x SUPPORT INTERFERENCE.

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

0 C-F-1 PT VS1SSISZZ0003Q x W.O. #931121035 TO PERFORM NOE. THIS c5.11 UT45 VS1SSISZZ0014Q x --EXAM REPLACES

SUMMARY

355420, DUE TO A UT45T x SUPPORT INTERFERENCE.

UT45TAN x --UTO VS1SSISZZ0018Q x **8-SS-10-.140-24-SAM**

, DATE:

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 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

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

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

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 DWG. NO. B-712 359100 3-CV-2160-5 C-F-1 PT VS1SSISZZ0003Q x

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

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) '

& VOLUME CONTROi. SECOND INTERVAL, SECOND PERICO, SECOND OUTAGE (93RF)

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION

3-CV-2160 DWG. NO. B-722 359840 3-CV-2160-42 PIPE TO ELBOW 359860 3-CV-2160-43 ELBOW TO PIPE 359880 3-CV-2160-44 PIPE TO ELBOW 2-CV-2170 i aw&. NO. B-81l 366000 2-CV-2170-1 REDUCER TO ELBOW 2-CV-2167 CREF. DWG. NO: B-90> 366620 2-CV-2167-7 PIPE TO REDUCER 2-CV-2164 CREF. DWG. NO. B-90) 368300 2-CV-2164-1 REDUCER TO PIPE CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY ITEM NO C-F-1 C5.21 C-F-1 CS.21 C-F-1 C5.21 C-F-1 C5.30 C-F-1 C5.30 C-F-1 C5.30 EXAM MET HOO PROCEDURE

PT VS1SSISZZQ003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN UTOL VS1SSISZZ0018Q PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN UTOL VS1SSl.SZZ0018Q PT VS1SSISZZ0003Q UT45 VS1SSISZZ0014Q UT45T UT45TAN UTOL VS1SSISZZ0018Q PT VS1SSISZZ0003Q PT VS1SSISZZ0003Q PT VS1SSISZZ0003Q N 0 0 G T R E H E 0 E REMARKS c M R **CALIBRATION BLOCK** ----------------------------------------

x W.O. 931121035 TO PERFORM NOE. THIS -x -WELD REPLACED

SUMMARY

359800, DUE TO x ALARA CONCERNS.

THEWELD WAS LOCATED x . -INSIDE THE SEAL WATER INJECTION FILTER x ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE WELD ROOT. **3-SS-160-.451-30-SAM**

x --W.O. 931121035 TO PERFORM NOE. THIS -x -WELD REPLACED

SUMMARY

359820, DUE TO x ALARA CONCERNS.

THE WELD WAS LOCATED x --INSIDE THE SEAL WATER INJECTION-FILTER x ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE ':'.* COUNTERBORE.

- 3-SS-160-.451-30-SAM**

x W.O. 931121035 TO PERFORM NOE. THIS -x -WELD REPLACES

SUMMARY

360000, DUE TO x ALARA CONCERNS.

THE WELD WAS LOCATED x --INSIDE THE SEAL WATER INJECTION FILTER x --ROOM. THE UT45 INDICATION IS A GEOMETRIC INDICATION FROM THE COUNTERBORE.

- 3-SS-160-.451-30-SAM**

x --W.0.#931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NOE. X --W.0.#931121035 TO PERFORM NOE. . !

, DATE: ,03/04/94 REVISION:

0

& VOLUME CONTROL *

SUMMARY

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

, 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 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 UTO VS1SSISZZ0018Q x --INDICATION FROM THE WELD ROOT. **4-SS-160-.533-28-SAM-R**

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

-x-. WELD REPLACED

SUMMARY

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 PT VS1SSISZZ0003Q x W.O. 931121035 TO PERFORM NDE. THIS ELBOW TO PIPE C5.21 UT45 VS1SSISZZ0014Q x WELD REPLACES

SUMMARY

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 REVISION:

0 INJECTION

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\IER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 38 2-SJ-2126 (REF. DWG. NO. B-104) 386620 2-SJ-2126-7R ORIFICE TO REDUCER 2-SJ-2123 (REF. DWG. NO. B-105) 387100 2-SJ-2123-6R REDUCER TO ORIFICE 387120 2-SJ-2123-7R ORIFICE TO REDUCER

C5.30 C-F-1 C5.30 C5.30 PT VHSSSSPZZ0204Q PT VHSSSSPZZ0204Q PT VHSSSSPZZ0204Q X --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930628119, ACT #5) X --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5) . X --PSI BASELINE EXAMINATION WAS PERFORMED, DUE TO THE REPLACEMENT OF THIS WELD, PER DCP 1EC-3260. (REF. W.O. #930630065, ACT #5)

' DATE: '03/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 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 ASME SEC. XI

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD AF1053 CREF. DWG. NO. AF-1,3A 01) 500145 14AFWG-002 GUIDE 500150 14AFWG-003 GUIDE F-C F3.10 F-C F3.10 AF1063 CREF. DWG. NO. AF-1-3A 01) 500390 13AFWA-046 ANCHOR D-A 01 .20 AF1075 CREF. DWG. NO. AF-1-3A 01) 500630 12AFWG-002 GUIDE AF1089 5oono 11AFWS-050 SUPPORT 500785 11AFWG-050A GUIDE DWG. F-C F3.10 NO. AF-1-3A 01l F-C F3.10

.. F-C F3.10 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** x --PRESERVICE PER 1EC-3226-01, CJP# PS-93-004.

x --PRESERVICE PER 1EC-3226-01, 930203123, CJP# PS-93-004.

W.0.# W.0.# X --PRESERVICE PER 1EC-3226-01, W.0.# 930203123, CJP# PS-93-004. X --PRESERVICE PER 1EC-3226-01, W.0.# 930203123, CJP# PS-93-004.

x --PRESERVICE PER 1EC-3226-01, W.0.# 930203123, CJP# PS-93-004.

39

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 ASME SEC. XI

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD CC1010 (REF. DWG. NO. CC-1-2A 02) 501255 1A-CCH*404 HANGER CC1022 CREF. DWG. NO. CC-1-2A 02) 501355 1A-CCH-405 HANGER CC1051 CREF. DWG. NO. CC-1-2A 02) 501380 1A-CCH-402 HANGER 501390 1A*CCH-403 HANGER F-C F3.10 CC1066 CREF. DWG. NO. CC-1-2A 02) 501425 1A-CCH-406 HANGER 501430 1A-CCH-082 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** THIS SUPPORT (SUM.# 501255) WAS DELETED PER EC-3255/PS-93-050/930610082. .THIS SUPPORT (SUM.# 501355) WAS DELETED PER 1EC-3255/PS-93-050/930610082.

THIS SUPPORT (SUM.# 501380) WAS DELETED PER 1EC-3255/PS-93-050/930610082.

THIS SUPPORT (SUM.# 501390) WAS DELETED PER 1EC-3255/PS-93-050/930610082.

THIS SUPPORT (SUM.# 501425) WAS DELETED PER 1EC-3255/PS-93-050/930610082. X --PRESERVICE PER 1EC-3255-1, CJP# PS-93-50 & W.0.# 930610082.

' DATE: *03/04/94 REVISION:

0 CONTAINMENT SPRAY SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEH NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASHE SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 41 SJ1094 CREF. DWG. NO. CS-1-1A 01) 502910 1A-CSS-158 SUPPORT F-C F3.10 VT-3 S1SSISZZ0020Q X " -W.0.#931121035 TO PERFORM NOE. RE-EXAM FROM 1RF0#10.

' DATE: .03/04/94 REVISION:

0 CHEMICAL AND VOLUME CONTROL SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION

SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS N 0 ASME 0 G T SEC. XI R E H CATGY EXAM E 0 E REMARKS ITEM NO METHOO . PROCEDURE c M R **CALIBRATION BLOCK** PAGE: 42 ......................

CV1161 DIJG. NO. CV-1-2B 02l 503235 1A-CVCS-383 SUPPORT RC1077 503945 1C-CVCH-326 HANGER 503970 1C-CVCG-276 GUIDE DIJG. NO. F-C VT-3 S1SSISZZ002QQ F3.10 CV-1-4B 01l VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q --x IJ.0.#931121035 TO PERFORM NOE. RESCHEDULED FROM 1RF0#10. NEED TO REMOVE CONCRETE BLOCK FOR EXAM. THE INSPECTION FOUND BORON ON THE SUPPORT. IJ.O. #931027158 CLEANED THE BORON OFF. A RE-EXAM IJAS SCHED. FOR S1RF0#12 (ACCESSIBILITY PROBLEMS).

x --THIS SUPPORT IJAS MODIFIED PER 1EC-3167/PS-92-40/920805116. X --.THIS SUPPORT IJAS MODIFIED PER 1EC-3167/PS-92-40/920805116.

' DATE: '03/04/94 REVISION:

0 .MAIN STEAM SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 43 MS1003 CREF. DWG. NO. MS-1-2 04) 504315 1P-MS-VS006 1 LUG MS1112 CREF. 504535 1P-MSH-122T HANGER MS1269 CREF. 504710 1P-MSH-124T HANGER ** DWG. MS-1-2 DWG. NO. MS-1-2 F-C F3.10 04) 04) VT-3 S1SSISZZ0020Q VT-3/4 S1SSISZZ0020Q VT-3/4 S1SSISZZ0020Q X --W.0.#931121035 TO PERFORM NDE. RE-EXAM FROM 1RF0#10. x --PRE-SERVICE INSPECTION WAS PERFORMED UNDER W.O. #931121035

& 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. x --PRE-SERVICE INSPECTION WAS PERFORMED 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 REVISION:

0 PRESSURIZING SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION

SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI CIJ4PLETE CIJ4PONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 44 RC1276 (REF. DWG. NO. RC-1-1A 01> 505065 1C-PSH-001 HANGER 505066 R-239776-1 505067 R-239776-2 505068 R-239776-3 05069 R-239776-4 505070 1C-PSH-002 HANGER 505071 R-239776-5 505072 R-239776-6 505073 R-239776-7

- F-C VT-3 F3.10 A-E VT-3 NB88-11 A-E VT-3 NB88-11 A-E VT-3 NB88-11 A-E VT-3 NB88-11 F-C VT-3 F3.10 A-E VT-3 NB88-11 A-E VT-3 NB88-11 A-E VT-3 NB88-11 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED.

PER NRC BULLETIN 88-1.1. X --W.0.#931121035 TO .PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED NRC BULLETIN 88-11. X --W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88-11.

'DATE: 03/04/94 REVISION:

0 SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 45 RC1276 (REF. DWG. NO. RC-1-1A 01> 505075 1C-PSH*003 HANGER F*C F3.10 VT-3 S1SSISZZ0020Q X *

W.0.#931121035 TO PERFORM NOE. EXAMINED PER NRC BULLETIN 88*11.

'DATE: 03/04/94 REVISION:

0 PRESSURIZER RELIEF SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR PO\JER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: RC1287 (REF. DWG. NO. RC-1-2B 01) 505300 1C-PRH-177 HANGER

VT-3 S1SSISZZ0020Q X --THIS SUPPORT WAS MODIFIED PER 1EC-3168/PS-92-41/920805117.

46

' DATE: '03/04/94 REVISION:

0 .RESIDUAL HEAT REMOVAL SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 . CXJTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND CXJTAGE C93RF) CLASS 2 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: RH1013 CREF. DWG. NO. RH-1-1A 02) 505755 1A-RHRA-PS30 ANCHOR ** F-C F3.10 VT-3 S1SSISZZ0020Q X --W.0.#931121035 TO PERFORM NOE. 47

' DATE: 03/04/94 REVISION:

0 SAFETY INJECTION SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 1 SECTION XI COMPLETE COMPONENTS ASME SEC *. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 O G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 48 RC1023 CREF. DWG. NO. RH*1-3F 01) 506195 1C*11SIS*133 SUPPORT F-C F3.10 VT*3 S1SSISZZ0020Q X -* W.0.#931121035 TO PERFORM NOE. RE*EXAM FROM 1RF0#10.

' 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 ASME SEC. XI

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOO SW1136 CREF. DWG. NO. SW-1-7K 01> 508920 1MSWPG-049A GUIDE D-B D2.20 SW1169 CREF. DWG. NO. SW-1-3B 01> 508990 A1-SWG-364 GUIDE 508995 A1-SWA-354 ANCHOR 509000 A1-SWG-366 GUIDE 509005 A1-SWG-367 GUIDE SW1176 CREF. DWG. NO. SW-1-38 01) 509010 A1-SWA-345 ANCHOR 509015 A1-SWG-344 GUIDE 509020 A1-SWG-316 GUIDE VT-3 VT-3 VT-3. VT-3 VT-3 VT-3 VT-3 VT*3 PROCEDURE S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS GUIDE WAS DISSASSEMBLED AND A NEW WELD WAS ADDED TO FACILITATE THE REMOVAL OF PIPE SPOOL RD-1-SW-75, .UNDER CJP #S-92-332 AND W.O. #920512075

. x --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/9304220!3.

x --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED*PER . 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

I DATE: g3/04/94 REVISION:

0 WATER SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS_(S1RF0#11, REV.0)" SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1176 (REF. DWG. NO. SW-1-3B 01) 509025 A1*SWA-315 ANCHOR 509030 A1-SWH-314 HANGER 509035 A1-SWG-313 GUIDE 509040 A1-SWG-324 GUIDE 09045 A1*SWH-323 HANGER 509050 A1-SWA-WS08 ANCHOR D-B D2.20 D-B D2.20 SW1181 CREF. DWG. NO. SW-1-3B 01) 509055 A1-SWG-378 GUIDE 509060 A1-SWA*358 ANCHOR 509065 A1-SWG-377 GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q x THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS*93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93*030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS*93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

so

'DATE: 93/04/94 REVISION:

0 SERVICE WATER SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1181 CREF. DWG. NO. SW-1-3B 012 509070 A1-SWG-376 GUIDE VT-3 S1SSISZZ002QQ X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

51 509075 A1-SWG-348 GUIDE VT-3 THIS SUPPORT (SUM.# 509075) WAS DELETED PER 1EC-3149/PS-93-030/930422073.

509080 A1-SWG-347 GUIDE 509085 A1-SWG-346 GUIDE SW1185 CREF. DWG. NO. SW-1-3B 012 509090 A1-SWS-369 SUPPORT 509095 A1-SWG-368 GUIDE 509100 A1-SWA-356 ANCHOR 509105 A1-SWG-370 GUIDE SW1191 CREF. DWG. NO. SW-1-1B 022 509110 P1-SWA-WS12 ANCHOR D-B D2.20 VT-3 VT-3 VT-3 VT-3 VT-3 vr-3 VT-3 S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ002QQ X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. , X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --PRESERVICE PER 1EC-3150-1/PS-93-006/930615162.

'DATE: 03/04/94 REVISION:

0 WATER SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 52 SW1197 CREF. DWG. NO. SW-1-1A 02) 509160 C-13SWH-2 HANGER 509165 C-13SWG-3C GUIDE SW1220 CREF. DWG. NO. SW-1-1A 02) 509270 C-12SWH-1 HANGER 509275 C-11SWG-3B GUIDE .,,.,,., C-11SWG-4B GUIDE 509285 C-11SWG-5B GUIDE 509290 C-12SWG-3A GUIDE 509295 C-12SWG-4 ANCHOR 509300 C-11SWG-9B GUIDE VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOO.) PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

THIS SUPPORT (SUM.# 509280) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOO.) PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS.MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

THIS SUPPORT (SUM.# 509300) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.

' DATE: *03/04/94 0

SERVICE WATER SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION

SALEM NUCLEAR PO\IER STATION UNIT 1 ClJTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND ClJTAGE (93RF) CLASS 3 SECTION XI CQ4PLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 53 SW1220 CREF. DWG. NO. SW-1-1A 02> 509305 C-11SIJG-11A GUIDE 509310 C-11SWG-6 GUIDE 509315 C-12SWG-7A GUIDE 509320 C-12SWH-9 HANGER

5.09345 SW1220 CREF. DWG. C-12SWG-12 GUIDE NO. SW-1-5B 02> F-C F3.10 SW1238 (REF. DWG. NO. SW-1-1A 02> 509370 C-11SWH-1 HANGER 509375 C-11SWG*3A GUIDE 509380 C-11SWG-4A GUIDE 509385 C-11SWG-5A GUIDE VT-3 S1SSISZZ002QQ VT-3 S1SSISZZ002QQ VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 VT-3 S1SSISZZ0020Q X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

x . -THIS SUPPORT WAS MODIFIED PER 1EC*3054-2/PS*93*021/920115113.

X * -THIS SUPPORT WAS MODIFIED PER 1EC-3054*2/PS-93-021/920115113.

X * -THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

THIS SUPPORT (SUM.# 501390) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.

X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.

'DATE: 03/04/94 SALEM NUCLEAR STATION UNIT 1 . PAGE: REVISION:

0 WATER SYSTEM OUTAGE !SI EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERICX>, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHCX> SW1238 CREF. DWG. NO. SW-1-1A 02) 509395 C-11SWG-8A GUIDE 509400 C-11SWG-9A GUIDE 509405 C-11SWH-10 HANGER D-B D2 SW1238 CREF. DWG. NO. SW-1-5A 02) 509425 C-11SWG-13 GUIDE SW1365 CREF. DWG. NO. SW-1-3B 01) 509525 A1-SWG-343 GUIDE 509530 A1-SWG-325 GUIDE SW1366 CREF. DWG. NO. SW-1-3B 01) 509535 A1-SWG-326 GUIDE 509540 A1-SWG-327 GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MCX>IFIED PER 1EC-3054-2/PS-93-021/920115113.

X --PRESERVICE (NO Mex>.) PER 1EC-3054-2/PS-93-021/920115113.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

54

' DATE: fJ3/04/94 REVISION:

0 SERVICE WATER SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1366 (REF. DWG. NO. SW-1-3B 01) 509545 A1-SWG-304 GUIDE 509550 1A-SWA-303A GUIDE 509555 A1*SWG*303 GUIDE 509560 A1-SWH*302 HANGER

509565 A1*SWG*301 GUIDE 509570 A1*SWG*300 GUIDE 509575 A1*SWG-318 GUIDE 509580 A1-SWH*317 HANGER 509585 A1-SWA*WS05 ANCHOR D-B D2.20 D-B D2.20 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT*3 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q x -THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X *

THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.

x --THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073

x --THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.

x --THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.

X -* THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93*030/930422073.

X *

THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS*93-030/930422073.

X *

THIS SUPPORT WAS MODIFIED PER 1EC*3149/PS-93*030/930422073.

55

'DATE: G3/04/94 REVISION:

0 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 56 WATER SYSTEM OUTAGE ISi EXAMINATION RESULTS CS1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS

ASME SEC. XI CATGY EXAM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION ITEM NO METHOD SW1373 CREF. DWG. NO. SW-1-3B 01) 509590 A1-SWG-328 GUIDE 509595 A1-SWG-329 GUIDE SW1377 CREF. DWG. NO. SW-1-3B 01) 509600 A1-SWS-351 SUPPORT 509605 A1-SWG-352 GUIDE SW1384 DWG. NO. 509635 C-14SWH-1 HANGER 509640 C-13SWG-3D

. ""-" GUIDE SW-1-1A 02) SW1496 CREF. DWG. NO. SW-1-9H 01) 5o98o5 1A-SWS-091 SUPPORT SW1498 DWG. NO. SW-1-3B 01l 509815 A1-SWS-340 SUPPORT VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q

S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

x --x --x --x --THIS SUPPORT (SUM.# 509595) WAS DELETED PER 1EC-3149/PS-93-030/930422073.

THIS SUPPORT (SUM.# 509600) WAS DELETED PER 1EC-3149/PS-93-030/930422073.

THIS SUPPORT (SUM.# 509605) WAS DELETED PER 1EC-3149/PS-93-030/930422073.

THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.

THIS SUPPORTS VERTICAL MEMBERS WERE REPLACED UNDER CJP #S-93-141 AND W.O. #920530148.

THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

'

'03/04/94 REVISION:

0 WATER SYSTEM

SUMMARY

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

X --THIS SUPPORT WAS MODIFIED PER '1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS Ma>IFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

x -THIS SUPPORT WAS M<X>IFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

57

'DATE: 03/04/94 REVISION:

0 SALEM NUCLEAR POWER STATION UNIT 1 PAGE:

WATER SYSTEM OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS

ASME SEC. XI

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD SW1542 CREF. DWG. NO. SW-1-3B 01) 509885 A1-SWG-310 GUIDE 509890 A1-SWG-309 GUIDE SW1545 CREF. DWG. NO. SW-1-3B 01) 509895 A1-SWG-341 GUIDE 509900 A1-SWG-342 GUIDE SW1546 CREF. DWG. NO. SW-1-3B 01) VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q

S1SSISZZ0020Q S1SSISZZ0020Q

S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

58 509905 A1-SWS-331 SUPPORT VT-3 THIS SUPPORT (SUM.# 509905) WAS DELETED PER 1EC-3149/PS-93-030/930422073.

509910 A1-SWS-339 SUPPORT 509915 A1-SWG-375 GUIDE 509920 A1-SWS-374 SUPPORT 509925 A1-SWA-355 ANCHOR ** : *....:: .. VT-3 VT-3 VT-3 VT-3 S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ0020Q X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

' DATE: *03/04/94 REVISION:

0 WATER SYSTEM

SUMMARY

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

X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

ANCHOR A1-SWA-383 WAS REPLACED WITH GUIDE A1-SWG-2433.

DATE: 03/04/94 ,REVISION:

0

SERVICE WATER SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM -ITEM NO METHOO PROCEDURE . N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: SW1551 CREF. DWG. NO. SW-1-3B 01) 509970 A1-SWG-322 GUIDE 509975 A1-SWH-321 HANGER 509980 A1-SWA-WS07 ANCHOR SW1556 {REF. 509985 A1-SWS-338 SUPPORT

509990 A1-SWS-336 SUPPORT 509995 A1-SWS-335 SUPPORT 510000 A1-SWG-337 GUIDE DWG. NO. D-B D2.20 SW-1-3B 01) SW1557 (REF. DWG. NO. SW-1-3B 01) 510005 A1-SWG-308 GUIDE 510010 1A-SWA-307A GUIDE D-B D2.20 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT*3 S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q X --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED 1EC-3149/PS-93-030/930422073.

x --THIS SUPPORT WAS MOOIFIED PER 1EC-3149/PS-93-030/930422073.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073. X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

60

, DATE:, D3/04/94 SALEM NUCLEAR POWER STATION UNIT 1 PAGE: 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 ASME SEC. XI sutl4ARY EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD SW1557 CREF. DWG. NO. SW-1-3B 01) 510015 A1-SWG-307 GUIDE 510020 A1-SWG-306 GUIDE 510025 A1-SWG-305 GUIDE 510030 A1-SWA-WS06 ANCHOR D-B D2.20 SW1619 CREF. DWG. NO. SW-1-1A 02) 510135 C-14SWH-1 HANGER 510225 C-13SWG-3B GUIDE .. SW1640 'REF. DWG. NO. SW-1-1A 02l 510250 C-13SWH-1 HANGER .---*:*"\

., -,. .... 510255 C-13SWG-3A GUIDE SW1664 'REF. DWG. NO. SW-1-1A 02l 510395 C-12SWH-2 HANGER VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ0020Q N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

X --THIS SUPPORT-WAS MODIFIED PER 1EC-3054*2/PS-93*021/920115113.

61

'DATE: 03/04/94 REVISION:

0 SERVICE WATER SYSTEM

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISI EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (93RF) , CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 62 SW1664 CREF. DWG. NO. SW-1-1A 02> 510400 C-11SWG-3D GUIDE 510405 C-11SWG-40 GUIDE 510410 C-11SWG-5D GUIDE 510415 C-12SWG-38 GUIDE 510420 C-12SWG-5 ANCHOR 510425 C-11SWG-90 GUIDE 510430 C-11SWG-11C GUIDE 510433 C-12SWG-6A GUIDE 510435 C-12SWG-58 GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ002QQ X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

THIS SUPPORT (SUM.# 501405) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOD.) PER . 1EC-3054-2/PS-93-021/920115113. X --_pRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113. X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

THIS SUPPORT (SUM.# 510425) WAS D.ELETED PER 1EC-3054-2/PS-93-021/920115113.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOO.) PER 1EC-3054-2/PS-93-021/920115113. X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.

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

0 .WATER SYSTEM OUTAGE ISi EXAMINATION RESULTS CS1RF.0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE C93RF) . CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI

SUMMARY

EXAMINATION AREA NUMBER IDENTIFICATION CATGY EXAM ITEM NO METHOD SW1664 CREF. DWG. NO. SW-1-1A 022 510440 C-12SWG-7B GUIDE 510445 C-12SWG-8 GUIDE 510450 C-12SWG-10 GUIDE 510455 C-12SWH-11 HANGER SW1664 CREF. DWG. NO. SW-1-5B 022 510485 C-12SWG-16 GUIDE F-C F3.10 SW1684 CREF. DWG. NO. SW-1-5A 02) 510520 C-11SWG-17 GUIDE F-C F3.10 SW1684 CREF. DWG. NO. SW-1-1A 02> 510555 C-11SWH-2 HANGER 510560 C-11SWG-3C GUIDE VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 PROCEDURE S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ0020Q S1SSISZZ0020Q S1SSISZZ002QQ S1SSISZZ002QQ S1SSISZZ002QQ N O 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** X --PRESERVICE CNO MOD.) PER 1EC-3054-2/PS-93-021/920115113.

X --PRESERVICE CNO MOO.) PER 1EC-3054-2/PS-93-021/920115113.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3054*2/PS-93-021/920115113._

X -* THIS SUPPORT WAS MODIFIED PER 1EC-3054*2/PS*93*021/920115113.

X *

THIS SUPPORT WAS MODIFIED PER 1EC*3054*2/PS*93*021/920115113.

X *

THIS SUPPORT WAS MOOIFIED PER 1EC*3054*2/PS*93*021/920115113.

X *

THIS SUPPORT WAS MODIFIED PER 1EC*3054*2/PS*93-021/920115113.

.

1 63 DATE: _ 03/04/94 'RE'flSI°":

0 _.SERVICE WATER SYSTEM

SUMMARY

EXAMINATION AREA_ NUMBER IDENTIFICATION SALEM NUCLEAR POWER STATION UNIT 1 OUTAGE ISi EXAMINATION RESULTS (S1RF0#11, REV.0) SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE_ (93RF) CLASS 3 SECTION XI COMPLETE COMPONENTS ASME SEC. XI CATGY EXAM ITEM NO METHOD PROCEDURE N 0 0 G T R E H E 0 E REMARKS C M R **CALIBRATION BLOCK** PAGE: 64 SW1684 CREF. DWG. NO. SW-1-1A 02> 510565 C-11SWG-4C GUIDE 510570 C-11SWG-5C GUIDE U0575 C-11SWG-7 ANCHOR 510580 C-11SWG-8B GUIDE 510585 *C-11SWG-9C GUIDE 510590 C-11SWG-11B GUIDE 510595 C-11SWH-12 HANGER SW1986 CREF. DWG. NO.-sw-1-3B 01> 510785 A1-SWG-320

-<t:_:, GUIDE 510790 A1-SWH-319 HANGER ** VT-3 VT-3 S1SSl!lZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 VT-3 S1 SS I SZZ0020Q -VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q VT-3 S1SSISZZ0020Q THIS SUPPORT (SUM.# 510565) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.

X --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

I x --PRESERVICE (NO MOD.) PER 1EC-3054-2/PS-93-021/920115113.

-, THIS SUPPORT (SUM.# 501585) WAS DELETED PER 1EC-3054-2/PS-93-021/920115113.

x --THIS.SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

x --THIS SUPPORT WAS MODIFIED PER 1EC-3054-2/PS-93-021/920115113.

X --THIS SUPPORT WAS MODIFIED PER 1EC-3149/PS-93-030/930422073.

I. NI8-2 Forms Component 1CVE43 11C85 18J32 1PR3 1PR4 1PR5 2PR3 (spare) 1CCE5 II. NR-1 Forms Code Job l 892-379 892-392 893-008 893-036 893-082 893-108 893-114 893-124 893-149 893-150 893-171 893-181 893-182 893-183 893-184 893-190 893-192 893-193 893-207 893-212 893-218 893-220 893-221 893-225 893-226 893-227

893-228 Index of NI8-2 and NR-1 Forms Work Order 920514012 Brief Description Replaced charging pump oil cooler Replaced disk & nozzle Replaced disk Installed modified f lexi-disc Installed modified flexi-disc Installed modified flexi-disc Installed modified flexi-disc Modified head with manway Brief Description Replaced studs, nuts and bonnets in kind Replace valve bolting Replaced valve bolting Replaced stem and valve bolting Repaired vane holes and taper pins Replaced bolting with upgraded material Replaced valve disc Replaced valve disc Replaced modified miniflow orifice Replaced modified miniflow orifice Replaced valve stem, bolting and weld repair on leak-off Replaced valve with valve of new design Replaced valve with valve of new design Replaced valve with valve of new design Replaced valve with valve of new design Replaced blind flange on fuel transfer canal in kind Replaced stem Replaced stem Replaced bonnet stud Weld repairs on valve body Replaced snubber serial # 330 with snubber serial # 23687 Replaced transition tubes assemblies Replace bonnet bolting Replaced flange and spool, elbow and bolting in kind Replaced plug and assembly in kind Replaced snubber serial # 25784 with snubber serial # 27164 Replaced snubber serial # 445 with snubber serial # 27629 893-229 893-233 893-238 893-240 893-241 893-249 893-250 893-254 893-260 893-262 893-266 893-270 893-276 893-277 893-278 893-279 893-287 PS92-040 PS92-041 PS93-012 PS93-045 PS93-053 PS93-054 PS93-052 PS93-055 PS93-070 PS93-073 PS93-074 PS93-075 PS93-076 PS93-077 PS93-078 PS93-079 PS93-080 PS93-081 PS93-082 PS93-083 PS93-088 Replaced snubber serial # 11 with snubber serial # 3903 Re-weld support after inspection and assembly of valve Replaced flange to valve bolting Replaced valve bolting Replaced bolting and nuts in kind Replace (16) studs in kind Replaced valve bolting Replaced pressurizer manway cover and bolting Replaced pressurizer relief tank rupture disc flanges Replace (1) bolt in kind on #14 Steam tor Primary Manway Cold Leg Replace valve disc Replace valve with spare valve Replace (4) cap screws and valve disc Replaced bolting Installed new stop pin for air lock ing ball valve Replaced valve in kind Replaced snubber serial # 25784 with snubber serial # 27164 Modified existing support Modified pipe support Replaced stem assembly and bolting with upgraded material and replaced valve bolting Replaced GB4 valve internals Replaced valve bolting and valve internals Replaced valve bolting and valve internal Modified pressurizer piping supports Modified pressurizer relief tank small bore piping Added break flanges to pipe spool piece 1CA2310 Removal of boric acid blender Replace valve internals, bolting and nuts Install new condensate chambers for #11 main steam header Install new condensate chambers for #12 main steam header Install new condensate chambers for #13 main steam header Install new condensate chambers for #14 main steam header Install supports for condensate pots on #11 main steam header Install supports for condensate pots on #12 main steam header Install supports for condensate pots on #13 main steam header Install supports for condensate pots on #14 main steam header Modify pipe support C-RVVS-5 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. Name End of Buttonwood Rd.Hancocks Bridge,NJ Addr-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 End of Buttonwood Rd.,Hancocks Bridge,NJ Add,_ Date __ s_e...:p:...t_e_m_b_e_r_2_1_, _1_9_9_3 _____ _ 1 1 Sheet ____ of ____________ Unit __ l ________________

_ WO# 920514012 CJP # S91-324 Repair Organlutlon P.O. No., Job No., etc. Type Code Symbol Stamp __ NR ________ _ Authorization No. _____ 3_6 _______ _ Expir111tion Date 10/3/94 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

... /""'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 No Standard 1CVE43 ITT 5-142-05 N/A N/A N/A 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) 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 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.._/

..... 9:..;;4._

_______ _ Signed

Owner or Owner's OesignH,Title Date 19 7 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 Insurance Co. of _MA ________________________________

have inspected the components described in this Owner's Report during the period ____ 7..._._-_'t

... *---='2-=----to, __

... 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.

__

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 N*m* End __ of Alloway Creek Addr-Bridge' NJ 08038 2. Plant ___ s_a_l_e_m

______________

_ N*m* End of Alloway Creek Ad. Hancocks Addr-sr i dge, NJ 08038 Date Nov. 2, 1993 *---;.!*:.w, ..... Sheet One of Cai;: . --. --. ***-*---*--*

.. Unit One .. PO# P1-426636 Crane-Aloyco Inc. NA Travel# A*P*lr Orgenlzetlon P.O. No., Job Type Code Symbol Stamp VA NA 366 3. Work Perfonned by_ ... c_r_a....._n

... e=--...:.A

... l....,o...,y._.c_p.__

... r ... n ... c ....... ___ _ N*m* 104 N. Chicago St; Authorization No.SO' 138, 261 , 262 24, 63 Joliet, IL Expiration Date. Ju 1 2 1 1996

Feb 17 , Add,_ 60434

--*-**---*-.

---* . 4. ldentiflcationofSVstem Ct.Jnteinrrient Soray

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

-.. -* Name of Name of Component Manufacturer 11CSS Crosby Disk Valve Crosby Nozzle Valve .. .. .. . Manufacturer Serial No. 84616-3!: -on.an 088027-16-0024 National Board No. PJ/4 NIA Other Identification Repaired;

-Smmped Year Replaced;

- **-eves Built or Replacement or Nol N/A N/A Heolacerl Nn N/A 7. Description of Work Replaced Disk & Nozzle, Lapped E; Set Tested 8. Tests Conducted:

Hydrostatic 0 Pneumatic 0

Pressure 260 Nominal Operating Pressure 0 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) 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.

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 VA NR Type Code Symbol Stamp ____________________________________________________________________

.,_,._._,_,,_

50,138,261 1 262 24,62 VA NA _____ _ Certificate of Authorization No. --------------------------Expiration Data j U 1 Y 2 1 19 9 6 Feb. 17, Signed_...,,.c{_,,LL

_____

..

... 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;..;:_

______________

inspected tbe components dea:rlbed in this Owner's Report during the 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 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.

20 S I

iff-I' 7f J j I nspector'1 Signature N*tional Bo*rd, St*t*, Province, and Endonemanu Date_l___,i

/ __ 2_'f _____ 19 7 _::) 1994

, *

FORM NIS-2 OWNER'S 4 REPORT FOR REPAJRS OR REPLACEMENTS As Required by the 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 Bridge, NJ 08038 of __ ""O'"'"n.._e""-"'"--------

Addrea 2. Plant __

Unit One PD# P 1-426.636 Name 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 Inc VA NA 3. Work Perfonned by---------,.,.-----*-----

Type Code Symbol Stamp __________

_ Name Authorization No.50' 138' 261 '262 24, 63 1_0_4 __ N_. __ C_h_i_c_a_,g=-o

__ S_t....,...,._J__.;:;o..;;cl::..i::..*

4 Expiration Date Jul Y 2 , 1 9 9 6 Feb

Address 17, 4. Identification of System Sa f e t Y I n j e c t i o n 5. (al Applicable Construction Code N/ A 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 National Repaired, Name of Name of Manufacturer Board Other Year Replaced, Component Manufacturer Serial No. No. Identification Built or Replacement 1SJ32 Crosby "N95137-Disc ValvF! 0035 N/A NIA NIA 9eplaced 7. Description of Work Replaced Disk, Cleaned, Lapped and Set Tested 8. Tests Conducted:

Hydrostatic D Pneumatic D

Pressure 220 Nominal Operating Pressure D psi Test Temp. Arnb j ent °F ASME Code Stamped (Yes or Nol No I 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 1994

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 50, 138, 261,262 24,63 VR NR Certificate of Authorization No.---------------

Expiration Date JU l y 2 , 1 SS 6 -Ee b 1 7 , 1 SS 4 .,// Date November 2..1 .19 93 Signed

Owner or Owner's Desilfnee, Title 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--..,!"""'

__

_____ ,, 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 shall be liable in 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

___ 19 tfJ

1. 2. 3. FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Owner Public Service Electric & Gas Co. Name End of Buttonwood Rd.,Hancocks Bridge,NJ Address Plant Salem Generating Station Name End of Buttonwood Rd. , Hancocks Bridge,NJ Address Work Performed by Wy!e/Crosby Name 7800 Governors Dr.,Hunstville ALA 35807 Address Date __ l_/_2_5_/_9_4

___________

_ 1 1 Sheet ____ of ____________

_ Unit_l ________________

_ Pl-931602 Repair Organization P.O. No., Job No., etc. Type Code Symbol Stamp ___ N_R ______ _ Authorization No. ______ 6_3 ______ _ Expiration Date ___ 2__,/'---1_7-'-/_9_4

________ _ 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 Test TemplPR3-654

°F 2PR3 (Spare)

2482PSI 635 °F 1PR4-2496 1PR4-656°F NOTE: Supplemental sheets in form or drawings (1) size is BY. in. x 11 in., (2) 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 ,Ld,L. 4...4_,

4r

v Owner or Owner's Designee, Titl8 Date __

_____ , 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.

__

___

_I ______ _

Signature National Board, State, Province, and Endorsements Date ___

.. __ 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. Name End of Buttonwood Rd.,Hancocks Bridge,NJ Address 2. Plant Salem Nuclear Generating Station Name End of Buttonwood Rd.,Hancocks Bridge,NJ Address 3. Work Performed by Joseph Oat Corporation Ne me 2500 Broadway, Camden, NJ 08104 Address Date __ F_e_b_r_u_a_r...::y,__7__:_,_1_9_9_4

______ _ Sheet __ l ___ of __ l __________

_ Unit ___ l _______________

_ WO #931023024 CJP PS-93-086 Repair Organization P.O. No., Job No., etc. Type Code Symbol Stamp_--=U-=l:...._

______ _ Authorization No. U-184 --------------

Expiration Date _ __;_7.:.../-=9...::/_9:....::4__;_

_______ _

___

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) 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 __

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.

Date ___

_________

_ Signed _

6'""7 ...

Owner or Owner's Designee, Title 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,__

__

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

______________________________

_ b:

__________________________________

_ c: Identifying nos. SD-C-112277 WA N/A N/A --=l=-98=-8=------(mfr's. serial no.) (Nafl.Bd.No.)

Qurisdictional no.) d: Construction Code B31. 7 1969 N/A (edition) (addenda)

6.Section XI 1983 SUnurer 83 (edition) (addenda) (otner) NIA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable ooition of Construction Code under which repairs, modifications, or replacements were made: *B31. 7 *1969 (edition) (year built) II (Code Class) N/A (Code Case(s)) S83

__ _ (addenda) (Code Case(s)) N/A N/A (addenda) (Code Case(s)) 9. Design

10. Tests conducted:

hydrostatic O pneumatic O design pressure O **pressure N/A psi Code Case(s) __

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'""o ... r .... k ..... _OID....._-e

... r...._..,.f_,.._:

__ 9 .... 2,..0..._9

....

________

.... 1.,*

....

..... 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 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, Signed C--.. Lt-vC---Commissions

__

________ _ (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

_____ _ (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

_

c: Identifying nos. 12024/S?OWDD

___ N;.,_/_A __ _ (mfr's. serial no.) (Narl.Bd.No.)

uurisdictional no.) d: Construction Code ASME DF&V 1968 N/A ANSI B31. 7 1969 B.ilitio{fl970 Add. (addenda)

6.Section XI 1983 SUnuner 83 (edition) (addenda)

N/A (other) N/A (Code Case(s)) 1987 (year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

S83 (addenda)

N/A (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1968 N/A *ASME DP&V/ANSI B31. 7 1969 F.d. 1970 Add. (edition) (addenda) (Code Case(s)) 9. Design responsibilities

10. '!'ests conducted:

hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _

ascription of work Replaced valve bolting. (use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks:

__

_________

..........

_______ _ 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 __ _ I 7 c. Date I .. _ e:;; ::i PSE&G Co. -Nuclear Dept. / /

Signed _____________

Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by 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.

9-. Factocy Mutual Engr. Assn. Date J /-Li-, 19 q) . Signed Cm' f.t/ (. lr, A<:* CommissionsN 8

t./ LJ A AJ'J ? 'Z 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. 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

.......

.__ __

.......

_____ _ (name) Foot of Buttonwood Rood, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwood.

Road, Hancocks Bridge, NJ 08038 (address) (repair organization's P.O. no., job. no.,etc.)

3. Name, address and identification of nuclear power plant __ _...S..,al.....,,em

...... _.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 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 ... ......_ __

......

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 (edition) (addenda) 1970 (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A *ANSI B31. 7 fW E-Spec 4GM42FBH(edition) (addenda) (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NGP psi Code Case(s) __

escription of work Replar-ed valve lx>lting.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:

_

________

.........

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 __ _ I I PSE&G Co. -Nuclear Dept. Date -JT 19,__f__Z::_.

Signed _____________

_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual 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 Assn.

_\_, 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 ........

.... c_.-e'"'--E'-"-'-l

-"'ect ..... _.r_1 .....

c._._ ... &--"'C..;:i,..,..s"-'C._n._.....__-__.Nl....._.1c......,.l

_..e..._oa

...

.... 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

...

______ _ Foot of Buttonwaad Rood 1 Hanccx:ks Bridge, ID 08038 4. System _

... -a ..... ct......._..._n

.... r_,,eoo.......,..,,,.l

..... a ..... n ..........

...

5. a: Component repaired, modified or replaced -l ... FS .......

...

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: S83 1983 (edition) (addenda) (Code Case(s)) N/A N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME DP&V/ANSI B31. 7 1969 Ed. 1970 Add. *1968 (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

_____ _ 11. Description of work Replace stem and valve bolting. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ _....,w..._o

..... :r:,...,k__._O.t..1.rd-'-"'e"'r--;#lf-*

.... 4 .... l_,7"""9'------------...,De="-f

...... i.._c ....

_N..,.,f-l""A.___

_______ _ 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, * (repair organization) (title) Date /-I y PSE&G Co. -Nuclear Dept. / / ./ ,

Signed_______________

..-7 (authorized representative)

Principal Engr. 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.

Date )-0 , 1 {lj__. Signed£,vm.J;../

'z.

CommissionsNJ (f1 t/ Y:)./ J( 4AJ 12} 9 / / . Facto:ry Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6

. FORM NR*1 REPORT OF REPAIR 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 II 5. a: Component repaired, modified or replaced 13SW58 b: Name of manufacturer Ma.sonellian International c: Identifying nos. N-00113-40-3 N/A ASME Draft (ili!&Vsel966 F.d. Mqm'arlia7..G.J Add. d: Construction Code ANSI B31. 7 1969 N/A 6.Section XI (edition) 1983 (addenda)

Inc. N/A Uurisdictional no.) summer 83 (edition) (addenda)

N/A 1974 (other) (year built) N/A II (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications.

or replacements were made: 1983 S83 N/A

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: (edition)

1969 (addenda)

N/A (addenda) (Code Case(s)) N/A (Code Case(s)) PS*ANES&GI B31. 7 /ASME Draft P&V 1968 Ed. Mar 1970 Add. (edition)

9. Design responsibilities

10. Tests conducted:

hydrostatic O pneumatic O design pressure O **pressure NOP psi Code Case(s) __

______ _ 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: _

________

-'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 __ _ Date L/" -3 () PSE&G co. -Nuclear Dept. 19,_!j_3__.

Signed ________________

_ Principal Engr. (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 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 o* P'OV;nce 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 c ...

C.r-<&llf--\Qlsaa;_.c

... _,-=--.it;"'4:fu_.c

...

... (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

.........

...

.....

.......

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 ... in ... 1k._ _____________________________

_ b: Name of manufacturer .Jos. Oa.t & Sons, Inc:. c: Identifying nos. 1781 2A 374 N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)

Ourisdictional no.) (other) d: Construction Code As.ME III Class C 1968 N/A N/A ANSI B31. 7 1969 Add. (addenda) (Code Case(s)) 6.Section XI 1983 SUmmer 83 (edition) (addenda)

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1 983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1 969 *ANSI B31. 7 /ASME III Class C 1968 (edition) 1969 (year built) (Code Class) N/A (C9de Case(s)) 883 (addenda) (Code Case(s)) 1970 (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)_ .....

11. Description of work Repl aero bolt j ng wj th 1 J?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, , (repair organization) (title) PSE&G eo.-Nuclear Dept. / // *

Date// -3o 19,____£:1__.

Signed ________________ _.,. (authorized representative)

Principal Engr. 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

__ 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:

b: Name of manufacturer

__

c: Identifying nos. 78704 N/A (Nat'l.Bd.No.)

d: Construction Code (edition)

6.Section XI 1983 N/A Ourisdictional no.) N/A (addenda)

SUrrurer 83 (edition) (addenda)

N/A (other) N/A (Code Case(s)) 7. Applicable edition of ASME Cade Section XI under which repairs. modifications.

or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications.

or replacements were made: *676241 PSE&G *N E-Spec (edition) 1968 (year built) (Code Class) N/A (Code Case(s)) 883

__ _ (addenda) (Code N/A N/A (addenda) (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

pressure O pressure ____ psi Code Case(s) _________

_ 11. Description of work p ---------------------------------------------(use of addrnonai sheet\S) or 1s accep:able ,f properiy 1dent.f*ed) "

W o :r k Orde:r #. 920713003 Eeficiency RepJ:rt #. N;'A 12.Remarks:

____

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 94 Certificate of Authorization no. ta use the "N R" stamp expires ' . 19 ----(repair organization) (authorized representa:>Ve)

(11!le) PSE&G Co.-Nuclear Dept. /J., -/!-A Prµicipal Engr.

19,..!13__.

Signed________________

V -/lt1'rt-1ru J}g_4,.J, I CERTIFICATE OF INSPECTION I, the undersigned, holding a issued by The National Board of of competency issued by the province of Y and employed cf have inspected the repair, modification or replacement described in this report on J"v1-1c 7 . 19 93 and state that to the best of 1'1Y knowledge and belief. this repair. modification or replacement has been made in accordance with Section XI of the ASME Cade and the National Board rules as defined 1n the publication NB-102, current edition. By signing this certificate.

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 Engr. Assn. Date '. 7 . ig---2..1.__

Signed

12. 1<?...,,._,, Commissions NlJ 7980 NI 8 s ;;:r PA-z z'--"o"-4-.'---_

.... 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

__

_____________________________________

_ c: Identifying nos. 78704 N/A N/A (Nat'l.Bd.No.)

Ourisdictional no.) d: Construction Code (edition)

6.Section XI 1983 N/A (addenda)

SUmroer 83 (ed1:ion) (addenda)

N/A (other) NIA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs. modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *76241 E-Spec (edition) 1968 (year built) I (Code Class) N/A (Code Case(s)) 883 (accendai (Code Case(s)) N/A N/A (addenda) (Code Case(s)) PSE&G 9. Design responsibilities

ik.,.,kt--------'l"'q()AEpr--------------'llil<f/,.,"i'!A.----------

10. Tests .co.nducted:

pressure O pressure ____ psi Code Case(s) _________

_ 11 Description of work ---------------------------------------------

(use of add1t1onal sheet(s) or is acceptaoie if properly

Work OI:de:r #: 900715077 Ikficie11cy Repo:t t #: N;'A 12.Remarks:

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 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.

Engr. (repair organ,zat!on) representative; CERTIFICATE OF INSPECTION I, the undersigned, holding a issued by The National Board of of competency issued by the province of Y and employed by ____________

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 Engr. Assn. Date 6 -2 . 19_&__ Signed wdka..

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229.

FORM NR*1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1

......... (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

...

... e ..... rn ....... t_i ...

.... 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 ....

...... mip ....... .__-__.M'L1.._'

n..._.i_..f_.1

.... aw....._-'Or

............

i ...... f_i ... c .... ...... -\,( .... Ccmp .........

...__T.._D

........ _.1_..CVE....,._.u2

....... 0y.) ____ _ b: Name of manufacturer Pacific Pump Inc. c: Identifying nos. 45603 N/A (mfr's. serial no.) (Nat'l.Bd.No.)

d: Construction Code W E Spec 6771.25 (edition)

6.Section XI 1983 N/A (addenda)

N/A Gurisdictional no.) (edition) (addenda)

N/A (other) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A 1970 (year built) (Code Class) N/A (Code Case(s)) S83 ....

__ _ (addenda) (Code Case(s)) 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

'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 __ _ a PSE&G Co. -Nuclear Dept. Date j( -"2.3' 19,--1...i._.

Signed _______________

_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by ' Co of MA have inspected the repair, modification or replacement described in this report on , 19 9...J.., and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in an.y manner for any personal injury or a loss of any kind arising from or connected with this inspection. , ;_ Facto:cy Mutual, Engr. Assn. Date 11/ZI , Signed Commissions Z.-ofl:, 11..);s(JJ .J ,,LJT<C..?/

1 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION OR INSTALLATION OF REPLACEMENT(S) TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS

Pa e 1 of 1 *ork performed by --wl?1 ... Llb ....... l ... i ... c....-...s

...

.......... ,l. ...

c ... e--.E ... 1 ... ect ...............

r .... i ... c__..,&,___.,.Ga,..is

.............

C ... o .....

.... a ... r-.De ...... p+'"-t---..... c ... JP.....____,#ff"S

..... 9.,_,3..._-__._J

.... 5 ... 0 _____ _ (name) (repair organization's P.O. no., job. no.,etc.)

Foot of Bn:ttonwood Road, Hancocks Bridge, NT 08038 (address) (name) Foot of B11ttonwood Raad, Hanax:ks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant __ .... S ... a .... l"""em...wL.....L:Nt

.....

.. e .........

r__,.C"...i=!.,...,n...,e

.. :ra ....... u.t .... iu.ng-"!f.....JS...,...ta......,.t_i._.o...,n.....___..U

.... n.._i'"'t..._JJ:#

...

Foot of Bi rttor1wood Road, Hancccks Bridge, NT 08038 4. System Cbemi 03] Va] ume Contra] (OTC) Nuclear Class II

____ _ 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 (edition)

S83 (addenda) (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *¥! E-Spec 677125 *N;/A N/A (edition) ( addenda) (Code Case(s)) 9. Design responsibilities

--l::L:l..l::.l:ll!""--------------------__:_--------------------

10. Tests conducted:

hydrostatic IX pneumatic D design pressure D** pressure 3550 psi Code

_____ _ 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, ,

I 3 PSE&G Co. -Nuclear Dept. / / t? -Date I -J..

19,_fil_.

Signed _______________ . 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.

1 , /.. f Facto:ry Mutual. Engr. Assn.

19 . Signed Commissions A

A./1Os1.J jv'.:J '/.JI (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)JS TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l 1 orkpertormedby

__

........

.......

..........

...._ __

......

_____ (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

...

... a ..

FCX>t of Bnttanwoad Road, Hancxx=:ks Bridge, NT 08038 4. System Safety Injec+/-i on Nuclear C1ass II 5. a: Component repaired, modified or replaced

____________________________

_ b: Name of manufacturer

--..v..i::..u::u.i.--------------------------------------

c: Identifying nos. 1 540 WA (mfr's. serial no.) (Nat'l.Bd.No.)

d: Construction Code W E-Spec 676258 ANSI B31.7 1969 Add. Qurisdictional no.) (addenda) (Code Case(s)) 6.Section XI 1983 __ .._$1 ... nmne ............

r...._8..._.3

_________

_ (edition) (addenda) 1988 (year built) (Code Class) WA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

S83 .....,1'{.,__./A......__

__ (addenda) 1970 (Code Case(s)) *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7JN E-Spec 676258 (edition) (addenda) (Code Case(s)) 9. Design responsibilities

--'.:..t.!.IOlll!.sr....

_______________________________________

_ 10.

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:

_

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, ,

PSE&G eo.-Nuclear Dept. t? .t?; Date II-3 d 19,_£3_. Signed ________________ -<-* :..4..,,.1 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 3 c> , 19 lj>J and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or or a loss of any kind arising from or connected with this inspection.

I .,,Facto:r:y Mutual Engr. Assn. Date / / 3 o , Signed Commissions f".4 2 VI HS IS' 0° £'.5 / 1 (Inspector) . (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 r==._......_._

..............

===========*-*-**-------

/ . ' FORM NR*1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork perfonned by pnhl j c Service El ectri c & C-.as Ca -Nucl ear D?pt. OTP #593-181 (name) (repair organization's P .0. no., job. no.,etc.)

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 __

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 ...

b: Name of manufacturer Boc:kwel 1 -Fdwams c: Identifying nos. N/A N/A (mfr's. serial no.) (Nari.ad.No.)

d: Construction Code WE-Spec 677264 ANSI B31. 7 1969 H!Jiitioffi970 Add. NIA ' (addenda)

N/A N/A Ourisdictional no.) (other) N/A (Code Case(s)) 6.Section XI 1 983 _ ___.Siu.u.1!IDileW1.L=.ir__.8u.3J.-

_________

_ (edition) (addenda) 1968 (year built) (Code Class) WA (Code Case(s)) S83 =.;N,_,,/A=----

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 677264 *1969 (addenda) 1970 (Code Case(s)) NIA (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 Replaced.

valve with valve of new design. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ ___,w,...o

.... r ...

.............

e ... r ........ #,,..:-.-9._3

.... 0 .... 7 ... .... l_,_7_,5'-----------

.... De..-...f

... i .... c .... i ""'e._.n.._.cy*-B"'"'eqpaleAeC.Ji+......._

.... ...........

______ _ 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 __ _ Date I -I Cf 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 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.

Date /-, Signed tnrYV "L* Commission&<t/tfi[9'L(/lJ/l MLJ 7 :J 9 / /)

Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 p;;..---'"=;;;;;;;;;====;;:;;;;;;;;;;;;;;==:-....------..;;:=:==========-*------**-

*---------

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:

serial No. Nat' 1. Bd. Jurist No. original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class ID of Replacement:

Name of Manufacturer:

AFX-55 N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Replacement Const. Code: *ASME III 1989 Code Cases:N/A 1993 Yes Year Built ASME Code Stamp'd.?

Edition NLA_ Addenda, Code Class A._ *ANSI B31.7 1969 Ed.t970 Add. ==============================================================================

of Component Replaced:

of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?

Addenda, Code Class _

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class ------------------------------------------------------------------------------

ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist No. acement Const. Code: Code Cases: __ _ Other Year Built Edition ASME Code Stamp'd.?

Addenda Code Class ' -==============================================================================

-".* ..... FORM NR*1 REPORT OF REPAIR 0 MODIFICATION$

OR INSTALLATION OF REPLACEMENT(S)

D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 *o.rk performed by Puhl i c Service El ectri c & C..as C.O. -Nucl ear Dept. CJP =#S93-J 82 (name) (repair organization's P .0. no., job. no.,etc.)

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 ...

... sta ..... ""t""1""'

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

... mnneuw.i=l"'L....-'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 (edition) (addenda) 1970 (Code Case(s)) *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 677264 (edition) (addenda) (Code Case(s)) 9. Design responsibilities

--'J.O!.IL.:l.lll!Ol...

_______________________________________

_ 10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NOF psi Code

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:

_

......

__________ .De .......

......

.....

Desi..gn Change Package #: lEP--2309 Pkg. 2 See attached pages for Description of Replacement.

- stem Inservice Test '11

Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19-=9'-4=---

Date /-/ y PSE&G Co. -Nuclear Dept. /J / / 19,---i.t.-.

Signed ____________

,;-</44<* dd+-4' 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 rules as defined in the NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date /-)_' . 1'U...]_.

Signe c. Commissions/J&f"ff$f:£'/l/

,4 tJ1,?7,i *,.*:--o*,_.:.,*

_ C/ J r-/ Factory Mutual Engr. Assn. * (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) , .. **/ ..

may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229 * ..

1:_ NB-81 Rev.6 Page of FORM NR-1 A'rl'ACHMENT Code Job Package No.: S93-182 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 2. owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 3. Location:

Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Safety Injection Nuclear Class:

-==============================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class __ ID of Replacement:

____________________

_ Name of Manufacturer:

Edward Valve Inc.

AFX-54 N/A N/A 1993

________ _ 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

________________

ANSI B31.7 1969 Ed.1970 Add. ==============================================================================

of Component Replaced:

of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class Other Year B,uilt Edition ASME Code Stamp'd.?

Addenda, Code Class _ ==============================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No* Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist No. acement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class __ Other Year Built Edition ASME Code Stamp'd.?

Addenda, Code Class _ ==============================================================================

...... ; -FORM NR*1 REPORT OF REPAIR D MODIFICATION INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of 2 ork performed by publ i c Service El ectri c & C..as Co. -Nucl ear Dept. CIP :/tS93-183 (name) (repair organization's P.O. no., job. no.,etc.)

Foot of Buttonwocd Rood, Hanr.ac;ks Bridge, N.J 08038 (address) (name) Foot of Buttonwcxxl Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant __ _.S..,al .....

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._.7_V.,._,a

... l_Vi_._,,,e,__

____________________________

_ b: Name of manufacturer Backwel 1 -Fdwarrls c: Identifying nos. N/A N/A (mfr's. serial no.) (Narl.Bd.No.)

d: Construction Code WE-Spec: 677264 ANSI B31. 7 1969 MUtioaJ970 Add. 6.Section XI 1983 (addenda)

N/A (jurisdictional no.) $J TIT1IT!f>r 8 3 (edition) (addenda)

N/A 1968 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

S83

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 *ANSI B31. 7 /N E-Spec 677264 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities

-"'"""'""&G"""'------------------------------------------

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NoP psi Code

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:

.......

........

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_. __ .....

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:

============================================================================== ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class ID of Replacement:

Name of Manufacturer:

Edward Valve Inc.

AFX-53 N/A N/A Serial No. Nat'l. Bd. Jurist-No.

Other Replacement Const. Code: *ASME III 1989 Code Cases:N/A 1993 Year Built ASME Code Stamp'd.?

Edition NLA__ Addenda, Code Class 1._ *ANSI B31.7 1969 Ed.1970 Add. ==============================================================================

ID of Component Replaced: .illlllllllif of Manufacturer: Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. .Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp.' d. ? Addenda, Code Class _

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class ------------------------------------------------------------------------------

ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist No. acement Const. Code: Other Year Built Edition ASME Code Stamp'd.?

Addenda, Code Class _

r:;=======----*----* . -* .. FORM NR-1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT($)

0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 ork performed by pnbl i c Send cp El ec+/-ri c & C'..as Co -Nuclear Dept. CIP f593-184 (name) (repair organization's P .0. no., job. no.,etc.)

Foot of Buttonw'ood Road, Hancocks Bri dgeJ NI 08038 (address) (name) Foot of ruttonwood.

Rbad, Hancocks Eri.dqe. NJ 08038 (address)

3. Name, address and identification of nuclear power plant __ _.s..,a ....... l...,em....._

.... Nu....,c.,..l

... e,,..;:i.,....,r._,,Gen..,.,, ....

...

... s...,,ta......,t.,.1..,'

..... #_,.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 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 (edition) 583

__ (addenda) 1970 (Code Case(s)) *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/.N E-Spec 677264 (edition) (addenda) (Code Case(s)) 9. Design responsibilities

____ -,-------------------------------------

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NOP psi Code

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=----(title). (repair organization) 7 (authorized representative)

Principal Engr. Date i-J 4 PSE&G Co.-Nuclear Dept.

Signed _______________

_ 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, 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 / -J.G , 1 Signe

£:(/ '{. kM ........-*

Commissions

!i/fSf?'/

Ct! t1 11J.f f 1} r,1, / q / / n Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Page _L of _L FORM NR-1 ATTACHMENT Code Job Package No.: S93-184 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location:

Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. system: Safety Injection Nuclear Class:

==================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class ID of Replacement:

Name of Manufacturer:

AFX-52 .N/A N/A 1993 Serial No. Nat'l. Bd. Jurist No. Other Replacement Const. Code: *ASME III 1989 Year Built ASME Code Stamp'd.?

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. Original Const. Code: Code Cases: ---ID of Replacement:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?

Addenda, Code Class _ ==============================================================================

ID of Component Replaced:

Name of Manufacturer:

Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement:

Name of Manufacturer:

'al No. Nat'l. Bd. Jurist N6. acement Const. Code: Other Year Built ASME Code Stamp'd.?

Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.?

Addenda, Code Class _ ==============================================================================

FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 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 (name) Foot of Buttonwood Road, Hancxx:ks Bridge, NT 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

CJP #893-190 (repair organization's P .0. no., job. no.,etc.)

3. Name, address and identification of nuclear power plant __ __.S..,a .... l ...

.... l ..

______ _ Foot of l311ttonwood Road, Hanc.cx:ks Bridge, NT 08038 4. System Fuel Transfer system Nuclear Class II b: Name of manufacturer

_ __,Wt.,.e=s

.... t ...

.... ... 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 (edition) 883 (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 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:

___

__________

.........

........ 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 __ _ (repair organization) (title) Date i '2 -l ,c, PSE&G Co. -Nuclear Dept. / I'/ 19,2..:l._.

Signed______________ ,dd'-4.L,, _. (authorized representative)

Principal Engr. 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 7 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 DOR INSTALLATION OF 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 3. Name, address and identification of nuclear power plant Foot of Buttonwood Road, Hancocks 4. System Reactor Coolant (address)

Salem Nuclear Generating Station Bridge, NJ 08038 Unit #1 Nuclear Class I b: Name of manufacturer 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 WA ANSI B31. 7 1969 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) 1970 (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A *ANSI B31. 7 JN E-Spec 676258 (edition) (addenda) (Code Case(s)) 9. Design responsibilities

_,,,_PS=E=&G'""'-----------------------------------------

10. Tests conducted:

hydrostatic D pneumatic D design pressure O **Pressure NDP psi Code escription of work Replaced stem. (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:

_

_________

.......

_______ _ 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 __ _ Date j -i l( PSE&G Co.-Nuclear Dept. 19,_f_£_.

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 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.

Date /-I Y Signed l

CommissionsNP sfJ9t/ f./l/!I ,A.),I?Z?

n 1 I c::-/ Facto;ry Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper 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

........

...... (name) (repair organization's P.O. no .. job. no .. etc.) Foot of Buttonwood.

Road. Hancc:x:::ks 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 Reactor Coolant Nuclear Class I 5. a: Component repaired, modified or replaced 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

__ _ 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 676258 (edition)

1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities

-=PSc=E=&G=-----------------------------------------

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NOP psi Code 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'-&-:

....

...

....

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 ----Date / -t.{ PSE&G Co.-Nuclear Dept.

Signed _______________

_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by 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.

C/-Facto:ry Mutual Engr. Assn. Date )-/ <( , 1Af. Signed 6'--'tU!-/

t:;, {J---: Commissionsfo1'/ftfV ft/A /lI.DJJ (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 ork performed by --=Pub=-==1=1='

ce=--=El=ectr==-=1=*

{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 II

__

b: Name of manufacturer I.TI' Grinnell c: Identifying nos. 085936 N/A N/A N/A

___ _ {mfr's. serial no.) (Narl.Bd.No.)

Uurisdictional no.) (other) d: Construction Code W E-Spec E676281 1970 N/A ANSI B31. 7 1969 (edition) (addenda) (Code Case(s)) 6.Section XI 1983 --=SUnnner===-_,,8,_,,3'-----------(edition) (addenda)

{year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83

__ 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI E-Spec 676281 (edition)

1969 (edition) (addenda) 1970 {addenda) (Code Case(s)) N/A (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) __

_____ _ 11. Description of work Replaced bonnet stud. (use of additional sheet{s) or sketch{ es) is acceptable if properly identified)

12. Remarks: __

_______

______ _ 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 __ _ o PSE&G Co. -Nuclear Dept. Date/ '1 19, f..7. 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.

Date q. 7,/{ , 1ill__. SignedtVJ1\h,/

£.u Commissionslll/d )fqt/'!dJA

&if i 23 9 L. Factory Mutual Engr. Assn. (Inspector)

{Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR !$] MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS f Pa e 1 o 1 orkpertormedby

........

.......

........

__

_____ _ (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 ..... a ........ ] .... em...,..._...Nt.........,1c

... ] ...

.... e ....... ra ....... t_1 ...

o..,,n....__,_U.,.n

... 1.._'

Foot of BirttonwC>CX'l Road, HanCXX"!ks Bridge, NT 08038 4. System steam C..enerator Feedwater Nuclear Class II b: Name of manufacturer

_

c: Identifying nos. PSJC-70 N/i\ (Narl.Bd.No.)

d: Construction Code 71 -61 64/70-6497 ANSI B31. 7 1969 E@lfitioi].970 Add. 6.Section XI 1983 Ourisdictional no.) (addenda)

Srnmner 83 (edition) (addenda) (other) (Code Case(s)) 1969 (year built) (Code Class) WA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) 883 ......

__ (addenda) 1970 (Code Case(s)) N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *PS Spec 71-6164/70-6497

1969 (edition) (addenda) (Code Case(s)) 9. Design responsibilities

__..........,""""'"'....__----------------------------------------

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure Nop psi Code Case(s) __

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---_..,., .........

..,...,,.

.......

.........

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, ,

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, Date 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 a loss of any kind arising from or connected with this inspection.

/ c;,J / . ( / /1 . , Assn. ,.:, ** / . 1d:z__. Signed l.

4-,,t:._/'

Commissions/\)ffe1'/

j

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 (name) Foot of Buttonwood.

Road, Hancocks Bridge, NJ 08038 CJP #S93-218 (repair organization's P.O. no., job. no.,etc.) (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 b: Name of manufacturer Paci fj c Sci entj fj c c: Identifying nos. 330 J:\IA N/A N/A __ (mfr's. serial no.) {Nat'l.Bd.No.)

Qurisdictional no.) d: Construction Code P8 Spec 73-6402 ANSI B31. 7 1969 F.ti<1itio!lJ970 Add. (addenda)

6.Section XI 1983 Srnmner 83 (edition) (addenda) (other) N/A (Code Case(s)) (year built) I (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

S83

__ _ 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 F,d, 1970 Add. *1974 (edition) (addenda) 876 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure N/A psi Code Case(s) __

______ _ 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: __

....

_________

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 __ _ Date / :J -6 PSE&G eo.-Nuclear Dept. 19, '13 . Signed _______________

_ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION

_I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by 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 I J.. "'f" , 1 dl__. Signed .pvzr<-? . .t*/ Z, l-oYL. Commissions/4/

/J 5'f9t./ f/f)rf /t/f" l ? 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)

)(I TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e 1 of 1 (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

....

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 ANSI B31. 7 1969 l?ti}tionU-970 Add. (addenda) 1/2 / N24 7 6.Section XI 1983

_________

_ (edition) (addenda) (Code Class) NIA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 (edition)

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 Replaced transition tubes assemblies. (use of additional sheet(s) or sketch(es) is acceptable if properly identified)

12. Remarks: _

....

.... 1 ... 5"--_________

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. 3 6 to use the "N R" stamp expires Oct. 3 , , 19-"-9-"4

__ _ Date 2. -f PSE&G Co.-Nuclear 19,_.tj:'._.

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 f /) .. -:2] , 19 and state that to the I best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date } -2 ( , 1u.:1._.

{..

Commissions I]//} 5°f"?'i' J)/ A /u 1::J f'J?

c: , / . (,-/ ,J Factory Mutual Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1° REPORT OF REPAIR 0 MODIFICATION 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. (name) Foot of Buti:anwpcrl Roodq HaDCXX'!ks Bridge, NI 08038 CJP #593-221 (repair organization's P .0. no., job. no.,etc.) (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant __

""t'--"#'-=l=----------

Foot of Buttonwood Road, Hancocks Bridge, NI 08038 4. System Demin Water Nuclear Class II 5.a:

b: Name of manufacturer c: Identifying nos.

...

N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) (jurisdictional no.) d: Construction Code ASME Sec III 1971 1971 (edition) (addenda)

6.Section XI 1983 Smnmer 83 (edition) (addenda) (other) None (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME Sec. III/B31.7 1969 Fd. 1970 Add. *1971 (edition) 1988 (year built) (Code Class} N/A (Code Case(s)) S83N ,,_,,/.._,,A_,,__

__ (addenda) 1971 (addenda) (Code Case(s N/A (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

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 ....

..... 1_.1"'2.u6'-----------De..,......_f .... j c ....... i ______ _ 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 __ _ (repair organization) (title) PSE&G Co. -Nuclear Dept. / / / Date Io-"J...L 19,__z:_:l__. Signed ________________ " (authorized representative) Principal E:n¥. 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 Signed 71f;t) l * &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 ___ (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.

__ 2_0_0 ___________________________ b: Name of manufacturer _ c: Identifying nos. N/A N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) d: Construction Code ANSI B31. 7 1969 6. Section XI (edition) 1983 Uurisdictional no.) 1970 (addenda) summer 83 (edition) (addenda) (other) N/A (Code Case(s)) 1983 (year built) II (Code Class) N-416 (Code Case(s)) S83 N-416 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: -----(edition)

1969 (edition) (addenda) (Code Case(s)) 1970 N-416 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31. 7 -----(addenda) (Code Case(s)) 9. Design responsibilities

-=PS=E=.:&G=-----------------------------------------

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NOP psi Code 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:

__________ 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 __ _ Date -? *-( 1 f, PSE&G Co. -Nuclear Dept. 19, 9 7' . Signed _______________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance CO of MA have inspected the repair, modification or replacement described in this report on J ,., 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. 1d.!l_. Signed/J1U:,/ 'z. Commissions;u'/{jr/£/J.V;.J /J,17/J .. / I n Factory.. Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 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 (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 ___ S__,a_l_em

__ Foot of-Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Steam Nuclear Class II 5.a: b: Name of manufacturer Fisher c: Identifying nos. 5725449 N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) d: Construction Code ASME Sec. III ....

6. Section XI (edition) 1983 (edition) (addenda)

Summer 83 (addenda) N/A 1975 (other) (year built) N/A (Code Case(s}) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME Sec. III (edition)

1971 (edition) (addenda)

S/72 (addenda) (Code Case(s)) N/A (Code Case(s}) 9. Design responsibilities _PS_E_&G _________________________________________ _ 10. Tests conducted: hydrostatic D pneumatic D design pressure D **pressure NOP psi Code 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: __ _________ _______ _ 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. Date J -lf 19,_f_!f_.

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 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_/_. t . l-<> 3 ( (<(ttl( T/Ll' fl &-Fl l 2 . 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=* ___ ____ _ (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 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 ANSI B31. 7 1969 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 S83 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *197 4 *ASME III/ANSI B31. 7 1969 Ed. 1970 Add. (edition) (addenda)

S70 (addenda) (Code Case(s)) 1644-4 (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) _ 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: _

________ ..... ....... '---""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 __ /-cl, 9 L.I PSE&G co.-Nuclear Dept. _Engr. Date _ 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 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. Date /-/7 , 1&__. Signed -u,. .... / (_,, UJ_ Commissions N'.6 S '6' [tf £1.!#/ A.)]) 7 J 1_j , ; < / Fgctory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l orkpertormedby ...... __ _____ _ (name) (repair organization's P.O. no., job. no.,etc.) Foot of 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 Foat of B11ttonwood Road, Hanmcks Bridge; NI 08038 4. System Steam C"-.enerator Feedwat.er Nuclear Class I b: Name of manufacturer Pacific Scienti fie c: Identifying nos. 445 N/A N/A (mfr's. serial no.) (Narl.Bd.No.)

Qurisdictional no.) d: Construction Code PS Spec 73-6402 N/ll ASME III 74 W75, MS! B31. 7 1969 M.en<!J!970 Add. N/A (other) 1644-4 (Code Case(s)) 6. Section XI 1983 _ __.$1"1UJlDllTl8ww ...... r___._8.._3,__ ________ _ (edition) (addenda)

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *197 4 *ASME III/ANSI B31. 7 1969 Fd. 1970 Add. (edition) 1976 (year built) (Code Class) WA (Code Case(s)) 883 (addenda) (Code Case(s)) S76 (addenda) (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure N/A psi Code _____ _ 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=---- Date I 2

9
PSE&G Co. -Nuclear Dept. t1 / / 19,_ll_. 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 //' 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 Foot of Buttonwood Road. Hancocks Bridge, N.J 08038 4. System Reactor Coolant Nuclear Class I 5.a:

b: Name of manufacturer Paci fj c Sci entj fj c c: Identifying nos. l l l NjA (mfr's. serial no.) (Narl.Bd.No.) Qurisdictional no.) d: Construction Code PS Spec 73-6402 N,IA ASME III 1974 B31. 7 1969afhlall970 Add. N/A (other) 1644-4 (Code Case(s)) 6. Section XI J 983 __ _..Sl.........,mnneww ...... r.........._8,__3..__ ________ _ (edition) (addenda) 1968 (year built) 1979 (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: (edition)

1974 (addenda) 16Sliiie Case(s))

1644-4 *ASME III (edition) (addenda) (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure O **Pressure N/A psi 11. Description of work Replaced snubber serial #11 with snubber serial # Code 3903. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ __.W .....

___.9 .... 3c..LJ_.J_._D .... 2...,,,0=4"-'J.__ _________ ....,De,,_.,f__.j_..c ..... i ..... e ... n ..... cy..q,... .... ..... A.__ _______ _ 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 __ _ Date J 1--b . 3 PSE&G Co. -Nuclear Dept. Principal Engr. 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 / /-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 modification or replacement in 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 ' 1 g_j_]__, Signed { 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 II 5. a: Component repaired, modified or replaced b: Name of manufacturer Fi sher Valve -J?SE&G Support c: Identifying nos. None None (mfr's. serial no.) (Nafl.Bd.No.)

Qurisdictional no.) d: Construction Code J?SE&G Spec 69-644"'5..___ ..... ANSI B31. 7 1969 ElicUtio!IJ970 Add. (addenda) (other) None (Code Case(s)) 6. Section XI 1983 _ __.$1 ....... nnme .......... r..__ ..... a ..... 3.._ ________ _ (edition) (addenda) 1972 (year built) II (Code Class) WA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 N=./<-=A=----

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/PSE&G Spec 69-6445 *1969 (addenda) 1970 (Code Case(s)) N/A (edition) (addenda) (Code Case(s)) 9. Design responsibilities

--=PSE==&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: __ _________ ......... _______ _ 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. / / / *-Date //

2-L.. 19,1L_. Signed _________________

Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /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 a loss of any kind arising from or connected with this inspection. Factory Mutual Engr. Assn. Date , 19 Cf J . Signed Commissions 2. 0 S'Z:, .J1 ,g (' / A.J..T * (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 II b: Name of manufacturer

__ .._._..,.,_.........._ ____________________________________ _ c: Identifying nos. 11319 Nil>, JVA JVA 1988 I (mfr's. serial no.) (Na!'l.Bd.No.) Qurisdictional no.) (other) (year built) d: Construction Code WE-Spec 676368 JVA 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 (edition) (addenda) 1970 (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A *ANSI B31. 7 fi-1 E-Spec 676368 (edition) (addenda) (Code Case(s)) 9. responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NGP psi Code

11. Description of work Replaced flange to valve OOlting. (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:

_ __________ ........ 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. / ; Date // -J 6 19, Y 3 . Signed _______________ , Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by 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 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 orkperformedby Blhl ic Service Electric & r..as Co. -Nuclear Dept. (name) (address) (name) Foot of Buttonwood Roa.d, Hancocks Bridge, NJ 08038 (address)

CJP jS93-240 (repair organization's P .0. no., job. no.,etc.)

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 .... 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,,.8._.7-'V. ... hl ..... Vi .... b: Name of manufacturer Anchor Dar] i ng c: Identifying nos. 1156669 WA (mfr's. serial no.) (Narl.Bd.No.) d: Construction Code W E-Spec 676258 ANSI B31. 7 1969 Add. (addenda) Gurisdictional no.) (other) WA (Code Case(s)) 6. Section XI 1983 _ __,$1_....IIIDI!E?wu=-r__.8 .... 3..__ _________ _ (edition) (addenda) 1970 (year built) (Code Class) WA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 .._,,N/.._..A....._ __ 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 676258 *1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NDP psi Code

11. Description of work Replace valve bolting. (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:

_ ....... ......... ie ....... 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'-----(repair organization) (title) PSE&G Co. -Nuclear Dept. # / / Date (1--13 19,___u_. Signed______________

..,, (authorized representative)

Principal Engr. 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 Commissions & Jt.) 1 l.3S ( .s / (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 ........ ....... ... ....... ...... .......... (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

.. -a..,r'--'Genera;"""" ....... ... t .... ,..i.,,,o .. n,,___,U ... 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 b: Name of manufacturer --""A ... l .... ........ _._D ... i_.v.......,/'""C .... a ....... J..,w ... n .... rt._....b....,__ ____________________________ _ c: Identifying nos. 70/A627-3 N/A (mfr's. serial no.) d: Construction Code ANSI B31 . 7 (edition) (Nat'l.Bd.No.) 1969 N/A (addenda) N/A Uurisdictional no.) (other) N/A (Code Case(s)) 6. Section XI 1983 __ .._$1 ... 11llJDE? ..... ... 8-..3.__ ________ _ (edition) (addenda) 1987 (year built) (Code Class) N/A (Code Case(s)) 883 __ 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7 *1969 (addenda)

N/A (Code Case(s)) NIA . (edition) (addenda) (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure O **pressure NjA psi Code Case(s) __ ______ _ 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 Dept.

Signed ______________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwr:L t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I -1 J , 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.

Date /-( L , 1U1__. Signeduy-= z:.., Commissions

J rb-1'/ Ij/)/f 1l): :J3 2 -? ("/ a,/ .C-/ .. Jact:o:ry Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR*1 REPORT OF REPAIR 0 MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S)Kl TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l

......... ...... _____ _ (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 __

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-.... 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 (edition) 883 ""-11'{,_,/A..,,_ __ (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

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure WA psi Code 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, , p Principal Engr. PSE&G Co.-Nuclear Dept. Date J -I'-( 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 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. Date / ,-I y ' Signed*t.h/' z_, Uv"--Commissions Nb" J 't9'/ j:,,.J /I /l)Jf7} r.i, I / / 11 *** Mutual Engr. Assn. (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..,'

____ _ (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 Safety Injection Nuclear Class I 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 (edition) (addenda) 1970 (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A *ANSI B31. 7 fi-1 E-Spec G676241 (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) __ _____ _ 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

..... 3_..J_....o .... o"'2 ...... o,_,7_,,4.__ _________ ..... IA= ....... f .... i .... c ..... i .... e .... n .... cyq-_..R.,.e-;1po:""'-rt.......__:jf,,.__,_: 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/ PSE&G co. -Nuclear Dept. 19,_L____,L_.

Signed _______________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by 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 /-/<{ , 1M. Signed: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

1CJ ....

____ _ (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 Foot of Buttonwood Road, Hancocks Bridge, ID oso::rn 4. System Reactor Coolant 5. a: Component repaired, modified or replaced P..ressurizer

-Manwa.y Cover -lRCElO Upjt ;jfJ Nuclear Class I b: c: Identifying nos. 1011 *i8-7 (mfr's. serial no.) (Narl.Bd.No.) d: Construction Code AS.ME III 19*i5 ANSI B31. 7 1969 Add. 6. Section XI 1983 N/A uurisdictional no.) Wl9*i5 (addenda) SUmmer 83 (edition) (addenda) N/A 1970 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 883 N/A 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) (addenda) (Code Case(s)) *See Attachment

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: * (edition) (addenda) (Code Case(s)) 9. Design responsibilities

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 1 9 ,-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 New Jersey and employed by Arkwri gbt Mubml Insurance 1f , of MA have inspected the repair, modification or replacement described in this report on / -I 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 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/. {. a C-Omm1,,1oo#l!tfit;/:J'lJv!fJJ" /Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1 ATTACHMENT Page _L of _L Code Job Package No.: 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. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class ID of Replacement: Pressurizer Manway Cover Name of Manufacturer: C42744 N/A N/A 1987 =N=o;.__ ________ Serial No. Nat'l. Bd. Jurist No. Other Replacement Const. Code: ASME III 1983 Year Built ASME Code Stamp'd.? 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. Original Const. Code: Code Cases: ---ID of Replacement: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Other Year Built Edition ASME Code Starnp'd.? Addenda, Code Class _ ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement: Name of Manufacturer: Nat'l. Bd. Jurist No. acement Const. Code: Other Year Built ASME Code starnp'd.? Edition Addenda, Code Class Other Year Built ASME Code Starnp'd.? 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. (name) Foot of Buttonwood Road, Hancocks Bridge, m 08038 (address)

2. Owner Public Service Electric anC! Gas Co. {name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 {address)

CJP #S93 260 (repair organization's P .0. no., job. no.,etc.)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Upjt #J Foot of Buttonwood Road, Hancocks Bridge, ID 08038 4. System Reactor Coolant N'11clear Class II 5. a: Component repaired, modified or replaced Pressurizer Relief Tank-Flanges-lRCEll b: Name of c: Identifying nos. Ir-10662 61420 {mfr's. serial no.) (Nat'l.Bd.No.)

d: Construction Code ASME III 1968 ANSI B31. 7 1969 Add. 6. Section XI 1983 {edition) N/A uurisdictional no.) N/A (addenda) (addenda) N/A 1969 {other) {year built) N/A (G) 2 (Code Case(s)) {Code Class) N/A {Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1989 *ASME III/ANSI B31. 7 1969 Ed. 1970 Add. (edition) 883 N,rl=A---(addendaJ (Code Case{s)) 89 NIA {bode Case{s)) (addenda)

9. Design responsibilities

_____________________________________ _ 10. Tests conducted: hydrostatic D pneumatic D design pressure °** pressure NOP psi Code

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 3 1 , ? Principal Engr. Date !-I 4 19 ,--2._L. Signed __ PS_E_&G __ c_o_._-_N_u_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 ___ ot MA have inspected the repair, modification or replacement described in this repart*an and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Bciard rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner tor any personal injury or property damage or a loss of any kind arising from or connected with this inspection. .... __ , 1u.i__. 'L* CommissionsN[frCjl/ WI/ Jl,t[f/} /,I , I i* /' I 11 :i;;as:::t;o:cy J1q.tual Engr..., . Assn. * (Inspector) (Natl.Bd.No.{including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR*1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S)fe:j TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by ___ _ (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

__ __ era __ t_o_r ________________________ _ b: Name of manufacturer Westinghouse c: Identifying nos. 1203 68-51 N/A (mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) d: Construction Code ASME Sec. III 196=5 __

6. Section XI (edition) 1983 (addenda)

SUrrnner 83 (edition) (addenda) 1971 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 (addenda) S66 (Code Case(s)) N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME Sec. III *1965 (edition) (addenda) (Code Case(s)) 9. Design responsibilities __ PSE __ &G ________________________________________ _ 10. Tests conducted: hydrostatic D pneumatic D design pressure D *l'fressure N/A psi Code Case(s) __ 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 ..... 1...,' ......... 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, , Date I -J Cf 4 v PSE&G Co. -Nuclear Dept. / / /

19,_L_f-*

Signed __________ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on II ' 19 L and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. C / )1utual Assn. Date /-J.Y-'1,jL. 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 II

__ ___________________________ _ b: Name of manufacturer __ ....:Al==-=O'-L--'CO==------------------------------------- c: Identifying nos. 70/A627-3 N/A N/A (rnfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) d: Construction Code WE-Spec __ N/A ANSI B31. 7 1969 Add. (addenda) (Code Case(s)) 6. Section XI 1983 SUrmner 83 (edition) (addenda)

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: N/A 1983 1970 (year built) II (Code Class) N/A (Code Case(s)) 883

__ (edition) (addenda) 1970 (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 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) __ _____ _ 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=* ______ _ 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. / / / Date __ /_-_i __ Signed ___________ -'-----*' Principal Engr. (repair organization) (authorized representative) (title). CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by 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 { , Signed/.vrl1J.v: (. Commissions/'Jfitrc/t./ fl///1 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 b: Name of manufacturer

____________________________________ _ c: Identifying nos. N55100-03-0045 N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) (other) d: Construction Code ASME III 1968 w 1977 1440 ANSI B31. 7 1969 Add. (addenda) (Code Case(s)) 6. Section XI 1983 Summer 83 (edition) (addenda)

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1968 *ASME III/ANSI B31. 7 1969 F.d. 1970 Add.(editionJ 1989 (year built) (Code Class) N/A (Code Case(s)) 883 N,rili\..,__

__ (addenda) (Code Case(s)) wzo __ _ (addenda) (Code Case(s)) 9. Design responsibilities

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" , __ _ I I n ;; ct PSE&G Co.-Nuclear Principal Engr. Date -/ 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 ___ 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/ (. 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 (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 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: *ASME Sec. III *1977 (edition) wzq (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....._ __ I. c.L .::::; ;. PSE&G Co. -Nuclear Dept. / / -'-Principal Engr. Date 2 -u 19,___L:,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 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 (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 c: Identifying nos. 843 694 N/A N/A _ ___,,l._,,9""6'-'7

____ _ (mfr's. serial no.) (Narl.Bd.No.) Qurisdictional no.) d: Construction Code ASME Sect. VIII 1967 ANSI B31. 7 1969 Eihtioi!)970 Add. (addenda)

6. Section XI 1983 SUrnrner 83 (edition) (addenda) (other) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME Sec. VIII/ANSI B31. 7 1969 &l.. 1970 Add. *1967 (edition) (year built) II (Code Class) N/A (Code Case(s)) S83 -'-N_,_/A

__ _ (addenda) (Code Case(s)) N/A N/A (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:

c=1=* 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 __ _ Date / -if PSE&G Co. -NucleaLr Dept. / P / 19,4-. 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 / -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 Signed*
Commissions Nil s;fqt( t/I/ /I /l/J.? 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 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 (edition) 883 __ _ (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

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 , __ _ PSE&G Co -Nuclear Dept / / / ,;? * / Principal Engr. 2 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 ___ ....... 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 b: Name of manufacturer Masoneilan International Inc. c: Identifying nos. N-00113-39-5 N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.)

Ourisdictional no.) d: Construction Code ASME Draft P&V

6. Section XI (edition) 1983 (edition) (addenda)

SUmrrer 83 (addenda) 1977 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 (edition)

1968 (edition) (addenda) (Code Case(s)) M/70 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME Draft P&V (addenda) (Code Case(s)) 9. Design responsibilities

---'PSE-'-""'"&G"--'-----------------------------------------

10. Tests conducted:

hydrostatic D pneumatic D design pressure D *'ressure N/A psi Code Case(s) __ '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: _

..... l..,0..,2....,0,,..2 ..... 2....,0.._.8..__ ________ __.De...,....f._j._.c ..... i .... e ... ncy......,;l'--'B""'e-1pa ......... ..... AO>--______ _ Design Qiange Package #: N/A Rev. N/A See attached pages for Description of Replacement. N/A ** stem Inservice Test

N08f.NC1'

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair. modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ Date i-I PSE&G Co.-Nuclear Dept. Signed _______________ _ ,</!a2A-* Principal Engr I (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 ,,_.// , 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.

Date__,_f_*-__._/ __ , 1<fL!l_. Signed c.. fd CommissionsJ\/IJ cff</ µ,4 a c I .

Assn. . (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION 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. (name) Foot of B11ttonwcxx1 Road, Hanc-0eks Bridge, NI 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NI 08038 (address)

CJP :f/:893-287 (repair organization's P .0. no., job. no.,etc.)

3. Name, address and identification of nuclear power plant __ _..S""al ..... em""""'..__..Nu......,c

... _____ _ Foot of B11ttonwcxx1 Road, Hanc-0eks Bridge, NI 08038 4. System Reactor Coolant Nuclear Class I 5. a: Component repaired, modified or replaced 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 III NF 1 974 W76 1644-1l1644-5 __ ANSI B31. 7 1969 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)

1974 (edition) (addenda) (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 Ed. 1970 Add. S70 164.....,4,_--=4

__ _ (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: ___ ...... __________ ........ 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, ,

__ _ PSE&G Co.-Nuclear Dept. Date I 2--G 19, ?' 3 . Signed ________________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by 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. Date ,. J Signed LI Lt,..yL--Commissions/l'//.Jrlf we/;/ 11.F[J'J7 , 2 _G.--, C / 1 Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR*1 REPORT OF REPAIR D 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

.... 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: Nameofmanufacrurer_--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 WA (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A (addenda)

N/A (Code Case(s)) 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 psi Code 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 ... ... 08'""0 .... 5 .... l .... l .... 6.,__ ________ _,ne........_f._1 ...

c_i ... e ..... n .... cy""'f--"""B

.... ........ 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. Date /2-/{ { / . Facto:ry Mutual Engr_. Assn. , 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 Page of Code Job Package No.: PS92040 ..

'

of ____________ N/A N/A N/A 1972 7:**_: Serial No. Nat'l. Bd. Jurist No. Other Year Built . ASME:;;c**

): Original Const. Code: Spec.69-6445 Rev.9Edition N/A Code Cases: N /A *

- .... .

.

ID of Replacement: lA-CVCG-902 .

Name of Manufacturer:

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. Original Const. Code: Code Cases: ---Other Year Edition--""'"! Name of Manufacturer: ial No. Nat'l. Bd. Jurist No. lacement Const. Code: Code Cases: ---Other ============================================== ' FORM NR*1 REPORT OF REPAIR D 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

_____________________________ _ b: Name of manufacturer c: Identifying nos. -N .... .. (mfr's. serial no.) N/A (Nat'l.Bd.No.) N/A Qurisdictional no.) d: Construction Code Spec 69-6430 :Rev-. (edition) (addenda)

6. Section XI 1983 (edition) (addenda) (other) N/A (Code Case(s)) 1974 (year built) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1 983 (edition)

$83 (addenda) (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *S-C-MBX>-MI:s-043 N;f A (edition) ( addenda) (Code Case(s)) 9. Design responsibilities -&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)

12. Remarks:

..... :--7796'2'd0e-80..,,5dcl=-1=-7+------------.De......,f0=1..,..* ... 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, ,

Date/ 2

3 c;.., PSE&G Co.-Nuclear Dept. 11 / / * / 19,___L,,,2__.

Signed __________ <"4.<A6-' 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. I Factory....,Mutual Engr. Assn. Date I 2. I Y . 19 '/ J . Signed b_ f Commissions p 4 2-0-5 f:1 .lj I 0 J I J tUT If 3 / r (Inspector) (Natl.Bd.No.(including endorsements)state or province and rfU!l;ber) 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. Chemical Volume Control Nuclear Class:

==================================================================

ID of Component Replaced: Name of Manufacturer: PSE&G N/A N/A N/A 1980 Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: Spec 69-6445 Rev9 Edition N/A Addenda, Code Class J.I__ Code Cases: N/A ------------------------------------------------------------------------------ ID of Replacement: Name of Manufacturer: PSE&G N/A N/A N/A N/A 1993 Serial No. Nat'l .. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? 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. ginal Const. Code: Code Cases: ---ID of Replacement: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Replacement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.? Addenda, Code Class ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class ID of Replacement: Name of Manufacturer: Serial No. Cases: Nat'l. Bd. Jurist No. Const. Code: ---Other Year Built Edition ASME Code Stamp'd.? Addenda, Code Class _ * ============================================================================== 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) (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 II 5. a:

__ 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 III 1971 S/1971 N/A ANSI B31. 7 1969 Add. (addenda) (Code Case(s)) (Code Class) 6. Section XI 1983 SUmrner 83 N/A (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 (addenda) S71 (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1971 N/A *ASME III/ANSI B31. 7 1969 Ed. 1970 Add. (edition) (addenda) (Code Case(s)) 9. Design responsibilities _PS==E=-=&G:=.. ______________________________________ _ 10. Tests conducted: hydrostatic D pneumatic D design pressure D ** pressure NOP psi Code Case(s) _ _.N""/_.A""------- Description of work Replaced stem assembly and bolting on Replace stem assembly (use of additional sheet(s) or sketch( es) is acceptable if properly identified) on Stem install to match new soft seats. 12. Remarks: _ _,Wi"-'o,,..r,,_,k"-'Ord"""'""er"""----l#r...i:L__o9,,,,.2"'0.c.4,..2..,1 ... ________ _______ _ Design Change Package #: lEC-3170 Pkg. 1 See attached for Description of Replacement. N/A ** stem Inservice T

Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 1g3::......::4

__ _ PSE&G Co.-Nuclear Dept. Date i L. -:2.. c 19, '13 . Signed. _______________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on /I*-2 1< , 19 '?:I and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National d rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ssed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 1 C---'--., Facto:ry Mutual_ Engr. Assn. Date j 2 *-J f'J , 19 9J . Signed Commissions 4 2 oS' {::> /f/ l Jf',J I J /(./_r :/ J / (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*Bl Rev 6 <1 _.-.--'/-FORM NR-1 REPORT OF REPAIR D MODIFICATION DOR INSTALLATION OF REPLACEMENT(S):g(

TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS * .. ,. **, 0'.
Page *1.* of 2 ork performed by --=Pub=-===1==1=*

_ (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (repair organization's P.O. no., job. no.,etc.) (address) 2.0wner __ Pub __ l_i_c_Serv __ i_ce __ E_l_ectr __ i_c_and __ Gas __ Co_. ________________________ (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. system Generator Blowdown Nuclear Class II

__ ____ s ___________ _ b: Name of manufacturer Masoneillian c: Identifying nos. See Attch. N/A (mfr's. serial no.) (Narl.Bd.No.) d: Construction Code ANSI B31. 7 6. Section XI (edition) 1983 N/A Uurisdictional no.) 1969 (addenda) Slllmner 83 (edition) (addenda) (other) None N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *N/A *ANSI B31. 7 /ASME Sec. III 1971 -Slllmner 71 (edition) 1974 (year built) 2 (Code Class) N/A (Code Case(s)) S83

__ (addenda) 1969 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities _PS __ E_&G ________________________________________ _ 10. Tests conducted: hydrostatic O pneumatic O design pressure O pressure ** psi Code

11. Description of work Replace GB4 valve internals IAW DCP lEC-3226-01. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: __ Wi"'"""o=r=k=--Ord==er=-_#u...:....:

_,9""'3"""'0,,_,2,,_,0"""3'""1=2=3'--- ________ Design Change Package #: lEC-3226 Rev. 01 See attached pages for Description of Replacement.

- NOP Temp. Nor CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NA" stamp expires Oct. 3, , 19_9_4 __ _ PSE&G Co. -Nuclear Dept. I .P iJ

-23 19,__2J::'Signed ______________ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co . of MA have inspected the repair, modification or replacement described in* this report on 2 -Zh , 19zj q and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacemen.t described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date 2-"Jfr . 1{/_:J__. ,

Commissionsl\/tJ)f7'{

..J.'1/1.:/ A.JcJJ7J * , I < / , Mutual Assn. . (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The Nation al Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 I Page _.L of _.L FORM NR-1 ATTACHMENT Code Job Package No.: PS93045 by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 System: Generator Blowdown Nuclear Class: 2 '============================================================================= i/ID of Component Replaced: ______________ _ JName of Manufacturer: /:;; N2/N001301-l N/A N/A N/A -=1=9_,_7_.4'---- Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: ANSI B31.7 Edition 1969 Addenda, Code Code Cases: N/A ID of Replacement: 12GB4 Valve Internals Name of Manufacturer: Masoneillan N2/N001301-2 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? original Const. Code: ANSI B31.7 Edition 1969_ Addenda, Code Code Cases: N/A ASME Sec. III 1971 -Summer 71 ============================================================================== ID of Component Replaced: ______________ _ e of Manufacturer: Masoneillan -=-==-==-=====.::::.= ______________________ _ 001301-3 N/A =N_/=A'---- N/A 1974 al No. Nat'l. Bd. Jurist No. Other Year_B_u_i_l_t ASME Original Const. Code: ANSI B31.7 Edition 1969_ Addenda, Code Cases : _ N /A_ ID of Replacement: 12GB4 Valve Internals Code Stamp'd.? Code Class Name of Manufacturer: Masoneillan -=-==="-=====-=-===----------------------- N 2/N00130 l -4 N/A N/A *---Serial No. Nat'l. Bd. Jurist No. Original Const. Code: ANSI B31.7 Code Cases: N/A ASME Sec. III N/A 0ther Year Built ASME Code Stamp'd.? Edition 1969_ Addenda, Code Class 1971 -Summer 71 ============================================================================== ID of component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? . "' Code: Edition Addenda, code class li'al No. Nat'l. Bd. Jurist No. Other Year Built ASME Code acement Const. Code: Edi ti on Addenda Code Class.?§:. ' :* * .. : > '( -:: .,r

Cases : .. * ....... ,

.... 't ______ ................................ ... 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 ... __ (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

______ _ Foot of Buttonwood RoadJ Hancocks Bridge, NJ 08038 4. System Reactor Coolant Nuclear Class I b: Name of manufacturer ... o .... ... l! ... 11,..c .... c: Identifying nos. 6910-95001-J 64-J N/A N/A (mfr's. serial no.) (Narl.Bd.No.) ourisdictional no.) d: Construction Code W E-Spec E676270 ___ N...,,-F-/=A.__ __ _ ANSI B31. 7 1969 Eticiitio!J..l970 Add. (addenda)

6. Section XI ]983 SJ.nnmer 83 (edition) (addenda)

N/A (other) WA (Code Case(s)) 1969 (year built) I (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 __ _ (addenda) 1970 (Code Case(s)) B. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *1969 N/A *ANSI B31. 7 ITfi E-Spec E-676270 (edition) (addenda) (Code Case(s)) 9: Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure NOP psi Code Case(s) _ Replaced. valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks: __ _________ ........ ______ -'----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 __ _ Date ( 2 w PSE&G Co. -Nuclear Dept. 19,__'__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 Arkwriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on f *-f I , 19 L/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. (/ £: -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 Page l of l (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 __ __ ______ _ 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 (mfr's. serial no.) (Nat'l.Bd.No.) aurisdictional no.) d: Construction Code W E-Spec E676270 __ ANSI B31. 7 1969 E'$ditioa.J970 Add. (addenda)

6. Section XI 1983 Surrrrner 83 (edition) (addenda)

N/A (other) N/A (Code Case(s)) 1969 (year built) I (Code Class) NIA . (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 =Nr-=/A=------(edition)

1969 (edition) (addenda) 1970 (Code Case(s)) N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E Spec E676270 (addenda) (Code Case(s)) 9. Design responsibilities

_PS_E_&_G ________________________________________ _ 10. Tests conducted: hydrostatic O pneumatic O design pressure O **pressure NOP psi Code Case(s) __ _____ _ Replaced valve bolting and valve internal with materials of new (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks:

_________ Desiqn Change Package #: lEC-3219 Pkg. 1 See attached pages for Description of Replacement. N/A **Svstem Inservice Test NOP Temn. NOT CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires act. 3, , 19_9_4 __ _ Date rJ-I 2 f' PSE&G Co.-Nuclear Dept. Signed _______________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwrioht Mutual Insurance Co of lYIA have inspected the repair, modification or replacement described in this report on / -if , 19 q l/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be 1n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date , 1g_jj__. Signed ( M?'\.Zt/ Commissions Mz '1'1 JN if JV J f7] 1-{ c 1* -/ Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION [gl OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l *orkpertormedby ........ ...... ___ ........ ____ (name) (repair organization's P.O. no., job. no.,etc.) Foot of ButtonwOCJd Road, Hancocks Bridge: NI 08038 (address) (name) Foot of Buttonwood Road, Hanccx::::ks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant ___

t=---'#'-=1=---------- Foot of Buttonwood Road: Hancocks Bridge, NJ 08038 4. System Reactor Coolant Nuclear Class II 5. b: Name of manufacturer ---=--= ...... c: Identifying nos. __.N;-¥-/A=-----(mfr's. serial no.) (Nat'l.Bd.No.) d: Construction Code J?S Spec 69-6445 SGS/M-FD-1

6. Section XI (edition) 1983 N/A aurisdictional no.) NIA J (addenda)

SJ l!JD1Jffr 83 (edition) (addenda) N;/A 1976 (other) (year built) N/A (Code Case(s)) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 (edition) (addenda) N/A (Code Case(s)) *NIA N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *PS Spec S-C-MBJO-MIE-043 (edition) (addenda) (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure WA psi Code Modified pressurizer piping supports. (use of additional sheet(s) or sketch( es) is acceptable if properly identified) N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ _ PSE&G co.-Nuclear Dept. Date i2 -8' 19, Cf-3 . Signed ________________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION _I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on 2. O 06C. , 19 lf .3 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National ed or implied, concerning the repair, modification o e I cement described in this report. Furthermore, neither the Inspector nor his employer shall be -ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, any manner for any personal o e ge or a ss f any k" d arising from or connected with this inspection.

Facto:ry Mutual Engr. Assn. Date zo Dec...' 19 Q 3. Signed Commissions N8 ll.2o :;i. r A) ,4 (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l rk performed by Pnblic Service El ec:tri c & Gas co -Nuclear Dept GIP #PS93-055 (name) (repair organization's P.O. no., job. no.,etc.)

M'oat of But+om,zoaj Raad, Hancacks Bridge, NT 08038 (address) (name) Foot of Buttonwood Road. Hancocks Bridge. NJ 08038 (address)

3. Name, address and identification of nuclear power plant __ ..,S.,,a ...

Foat of Buttonwocx] Road, Hancacks Bridge, NI 08038 4. System Reactor Cool ant Nuclear Class I 5. a: Component repaired, modified or replaced PR!' Pipe Spcxlls Sl-RC-3220 and Sl-RC-3222 b: Name of man.ufacturer _ c: Identifying.nos. -N-+/ .. (mfr's. serial no.) N/A (Nat'l.Bd.No.) d: Construction Code ANSI B31 7 1969 ANSI B31.1 1967 (edition)

6. Section XI 1983 (edition) 1970 (addenda)

N/A 1974 Uurisdictional no.) (other) (year built) N/A (Code Case(s)) (Code Class) simrrner 83 N/A (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883 N._,,/c...:A-=----(edition)

1969 (edition) (addenda) 1970 (Code Case(s)) N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/ANSI B31.l 1967 (addenda) (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D** pressure NOP psi Code

11. Description of work Modi fj ed pressurizer relief tank small bore piping. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ _..w ..... o ...

........... Ord ............ ..... 3 ..... 0 .... l .... 2-..6 .... l .... 5 .... 0..,._ ________ e .... n ..... Desi gn Change Package j: JEC-3219 Pkg. 1 See attached. pages for Description of Replacement. N/A **SVstem Inservice Test Ti=>mn. NOT CERTIRCATEOFCOMPLIANCE Wffcertify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME *code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , __ _ Date f-2 c; u PSE&G Co.-Nuclear Dept. d / / , 19,______L_,L.. Signed ____________ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by -the state or province of New Jersey and employed by Ark.wriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / *-// , 19.&-/ l/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, *d or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be ny manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date /.-1 I , 1g_j{_. Signed

Commissions

,1.fF J8"1 Y J:iUIJ A.ff ?7 3

e, q { ; Facto:cy Mutual EngJ::. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR*1 REPORT OF REPAIR 0 MODIFICATION-q]

OR INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Pa e l of l ork performed by _ _...Pub ........ ... ice,,.,,.'-""'E .... l.,.ectr""'""" ...... i""c"--"&.__,,Gas ...... .._,Co""""'

.____ _

.... l..___ (name) (repair organization's P.O. no., job. no.,etc.) Foot of Buttonwood Road. Hancocks Bridge. NJ 08038 (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Control Air Nuclear Class II 5.a:

b: Name of manufacturer __ Mu..tt. ..... .... l,.,,,e..__ __________________________________ _ c: Identifying nos. N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) d: Construction Code B31.1 1967/B31. 7 1969 None 6. Section XI (edition) 1983 (edition) (addenda) Summer 83 (addenda) {other) None N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.l/B31.

7 1969 *1967 (edition) 1974 (year built) (Code Class) N/A (Code Case(s)) S83 {addenda) N/A (addenda) (Code Case{s)) None {Code Case{s)) 9. Design responsibilities --=PS=-=E=&G=-----------------------------------------

10. Tests conducted:

hydrostatic D pneumatic [){ design pressure O **pressure 142 psi Code

11. Description of work Added break flanges to pipe spool piece 1CA2310. (use of additional sheet{s) or sketch( es) is acceptable if properly identified) 12.Remarks:

_ _________ Design Change Package #: lEC-3150-1 Rev. o See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , e'1 I/ PSE&G Co. -Nuclear Dept. Date ') -'"'2-L Signed _______________ _ Principal Engr. {repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance of MA have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication N B-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date ) J J f , 1rfL.!___. Signed 7. Lo-/.__ Commissions/i)fi,!)(C/{ L/V/i ,A)\LJ 7 J . '"'* ,/ ,.,,,-* / Factory Mutual Engr. Assn. {Inspector) {Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 REPORT OF REPAIR 0 MODIFICATION INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of l ork performed by Public Service Electric & Gas Co. -Nuclear Dept. (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) CJP #PS93-073 (repair organization's P .0. no., job. no.,etc.)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 4. system Chemical & Volume Control system Nuclear Class II 5.

__ er _________________________ b: Name of manufacturer _ =h=o_,,,us=e:...._ _______________________________ _ c: Identifying nos. None N/A N/A N/A __ (mfr's. serial no.} (Nat'l.Bd.No.} Qurisdictional no.) d: Construction Code ANSI B31. 7 1969 1970 ANSI B31.1 1967 (edition) (addenda)

6. Section XI 1983 S1.nnmer 83 (edition) (addenda) (other) None (Code Case(s)} (year built} II (Code Class} N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

S83 N_/_A __ _ (addenda) 1970 (Code Case(s)} *1969 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/ANSI B31.l 1967 (edition) (addenda) (Code Case(s)) 9. Design responsibilities PSE&G ------------------------------------------

10. Tests conducted:

hydrostatic

f;! pneumatic D design pressure O** pressure 170 psi Code escription of work Removal of boric acid blender no longer needed in chemical and (use of additional sheet(s) or sketch( es) is acceptable if properly identified) volume control syst:m and re-installation of piping. 12. Remarks: _

_________ ...... Design Change Package #: lEC-3254 Rev. O See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 1 , 193_4 __ _ Date ( * ( l( PSE&G Co. -Nuclear Dept. I / fl 19,__l,i_. Signed _____________

Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwriqht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on I/, 7 , 1 gCO and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date/.--),) CommissionsN/)""'t9l/ '£;J/t tJf?ZJ / -. ; -/ Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rev 6 FORM NR-1 REPORT OF REPAIR D MODIFICATION 0 OR INSTALLATION OF REPLACEMENT(S) ill TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 1 *rk performed by Public Service Electric & Gas Co. -Nuclear Dept. CJP #PS93-074 (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, NJ 08038 4. System Chemical & Volune Control System Nuclear Class II 5. a:

__ 7_2_Co_n_tro __ ________________________ _ b: Name of manufacturer Copes Vulcan c: Identifying nos. 6910-95001-187-1 N/A N/A N/A 1971 (mfr's. serial no.) (Nat'l.Bd.No.) uurisdictional no.) (other) d: Construction Code ANSI B31. 7 1969 1970 N/A fl E-Spec 676270 (edition) (addenda) (Code Case(s)) 6. Section XI 1983 (edition) (addenda) (year built) (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/N E-Spec 676270 (edition)

1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) None (Code Case(s)) 9. Design responsibilities

__ PS_E_&G ________________________________________ _ 10. Tests conducted: hydrostatic [JX pneumatic D design pressure O *"'Pressure 170 psi Code

11. Description of work Replace existing lC'i/172 valve internals in accordance with lEC-3254 (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

Packa: e 1 and re lacernent of bolt' and nuts r revision 1 lEC-3254.

12. Remarks: _ _..W,,,,o,,,,,r,,_...k.._,,,O<<>rd,_,,,,,,,er,,,.,,__....J#w:.___.9""""3....,0....,6

.... 1 ... 8 .... l ... 3.._.3..__ ________ ..... m_..cy"-'l-- ..... R,,,.e.,..po ........... ...... n_...n__.,.e'"'----------- Desiqn Change Package #: lEC-3254 Rev. o See attached pages for Description of Replacement.

- NA T
90°F CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3 / . 19_9_4 __ Date /j' ,,; PSE&G Co. -Nuclear Dept. / / /

Signed ______________ Principal Engr. (repair organization) v (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwright Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on / /-1-, 19 tf} and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date J ...-Z-) , 19 . Signed t** Commissions N IJ J f1t./ /ttf/1 /!) ;/f 7} I / q_i_ k / tf F51ct01:y Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 -,# FORM NR-1 REPORT OF REPAIR 0 MODIFICATION INSTALLATION OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page l of 2 ork performed by _ _,Pub=-==-=l::.:1::..:' c=----=S::...;erv==-"-'1=-* ce=-=---=El=ectr=-=-=1=-* ___ _ (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 (address) 2.owner __ Pub __ l_i_c_S_erv __ i_ce __ E_l_ectr __ i_c_and __ Gas __ co_. ________________________ _ (name) Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwocxi Road, Hancocks Bridge, ID 08038 4. System Main Steam Nuclear Class II 5. a: Component repaired, modified or replaced 1.MSE57, 1.MSE58, 1MSE59, 1.MSE60 COndensate Chambers b: Name of manufacturer COnnex Pipe Systems c: Identifying nos. See Attachment N/A (mfr's. serial no.) (Nat'l.Bd.No.)

d: Construction Code See Attachment

6. Section XI (edition) 1983 N/A Ourisdictional no.) N/A (addenda)

Sl..nmner 83 (edition) (addenda) (other) N/A (Code Case(s)) N/A 1993 (year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 S83 (edition) (addenda) 1989 (Code Case(s)) *1989 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 F.d. 1970 Add. (edition) (addenda) (Code Case(s)) 9. Design responsibilities _PS __ E_&G ________________________________________ _ 10. Tests conducted: hydrostatic [JC pneumatic D design pressure D *-J;:iressure 1400psi Code Case(s)_--=N'-"/'-'A=-------- escription of work Installed new condensate chambers for #11 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _

_.N;LI.J/O...OA....__ ______ _ Design Change Package #: lEC-3256 Pkq. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_4 __ _ Date { -a-c1 PSE&G co.-Nuclear Dept. / / / .... Signed ____________ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on -I , 199 '( and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication N B-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. C / .I __. _ Facto:cy Assn. Date / *-1-'{ , 19-5....!L._. Signed./ t

Commissions

J{) f1'it 1AJ;1 /UJ J J J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 r -Page _2_ of _2_ FORM NR-1 ATTACHMENT Code Job Package No.: PS93075

Work performed by: 2. Owner: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Public Service Electric & Gas Co. 3. Location:

Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Nuclear Class:

==================================================================

ID of Component Replacement: 1MSE57 Condensate Chamber Name of Manufacturer: ___ ___________________ ___, 43471 N/A N/A N/A 1993 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: ___ ________________ _ 434 72 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. *code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add ASME Code Stamp'd.? Addenda, Code Class L ============================================================================== ID of Component Replaced: Name of Manufacturer: 'al No. Nat'l. Bd. Jurist No. ginal Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Code Cases: ---ID of Replacement: 1MSE59 Condensate Chamber Name of Manufacturer: 4 3 4 7 3 N /A N /A N /A S er i al No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stci.mp'd.? Addenda, Code Class L ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial.No. Nat'l. Bd .. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Clas$ Code Cases: ________ _ ID of Replacement: 1MSE60 Condensate Chamber Name of Manufacturer: Connex Pipe System 43474 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built No ASME Code Stamp'd.? acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .6.._ Cases:N/A ANSI B31.7 1969 Ed. 1970 Add ============================================================================== . ' _______ ..--£.,, ___ ----* ---**------------------------* -" * * * -: ** FORM NR-1 REPORT OF REPAIR D OR INSTALLATION OF REPLACEMENT(S) D TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS Page 1 of 2 (name) (repair organization's P .0. no., job. no.,etc.) Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038 (address) (name) Foot of Buttonwcxxi Road, Hancocks Bridge, NJ 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System Main Stearn Nuclear Class II b: Name of manufacturer Pipe Systems c: Identifying nos. See Attachment N/A (mfr's. serial no.) (Narl.Bd.No.)

d: Construction Code See Attachment

6. Section XI (edition) 1983 (edition)

N/A Ourisdictional no.) N/A (addenda) SUrnmer 83 (addenda) N/A 1993 (other) (year built) N/A (Code Case(s)) (Code Class) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 883

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 Ed. 1970 Add. (edition)

1989 (edition) (addenda) 1989 (Code Case(s)) N/A (addenda) (Code Case(s)) 9. Design responsibilities

_______________________________________ _ 10. Tests conducted: hydrostatic [){ pneumatic D design pressure D **pressure 1400psi Code Case(s) _ __,,N""/'-'A,_,,__ _____ _ escription of work Installed new chambers for #12 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: _ __,_,W=o,.,r...,k'--"'O""'rd"""""'er""-..il#

..... .... i ...... c,...j ______ _ Change Package #: lEC-3256 Pkq. 1 See attached pages for of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 19_9_.1_. __ _ Date 1= "2---<( o ffiE&G Co. -Nuclear Dept. 19,_r__z:::_. Signed ______________ _ Principal Engr. (repair organization) (authorized representative) (title) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors, and certificate of competency issued by the state or province of New Jersey and employed by Arkwri t Mutual Co of MA have inspected the repair, modification or replacement described in this report on /-/ f , 191 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date J-J_tf . 19-l.i_. Signed {. Commissions NE ) (9'/ UA fC.!V 1J a LI / 1 Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Page __L of __L FORM NR-1 ATTACHMENT Code Job Package No.: PS93076 Work performed by: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Owner: Public Service Electric & Gas co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Main Steam Nuclear Class: -=I=I..__ __ _ ============================================================================== ID of Component Replacement: 1MSE61 Condensate Chamber Name of Manufacturer: ________________ _ 43471 N/A N/A N/A 1993 ___________ _ Se.rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class Code Cases: N/A ANSI B31.7 1969 Ed. 1970 Add ID of Replacement: 1MSE62 Condensate Chamber Name of Manufacturer: ________________ _ 43472 N/A N/A N/A __ Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.? Addenda, Code Class ============================================================================== ID of Component Replaced: e of Manufacturer: 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: ________________ 43473 N/A N/A. N/A 1993. __ _ Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.? Addenda, Code Class ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code stamp'd.? Edition Addenda, Code Class Code Cases: --- ID of Replacement: 1MSE64 Condensate Chamber Name of Manufacturer: _____________ 43474 N/A N/A N/A ial No. Nat'l. Bd. Jurist No. Other Year Built lacement Const. Code: ASME III 1989 Edition 1989 e Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.? Addenda, Code Class a_ ============================================================================== -:-.. 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. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) Public Sei:vice Electric and Gas Co. (name) Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 (address) CJP #PS93-077 (repair organization's P.O. no., job. no.,etc.)

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: __

__ E_6_6 .... __ __ __ ___________ _ b: Name of manufacturer Connex Pipe Systems c: Identifying nos. See Attachment N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda) SUrnmer 83 (edition) (addenda) (other) N/A N/A {Code Case(s)) 1993 (year built) II (Code Class) NIA (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 __ (addenda) 1989 (Code Case(s)) *1989 N/A 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31.7 1969 Ed. 1970 Add. (edition) (addenda) (Code Case(s)) 9. Design responsibilities --=PS=-=E=-=-&G'-=-------------------------------------------

10. Tests conducted:

hydrostatic pneumatic D design pressure D** pressure 1400 psi Code .... 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:

_________ 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. Date /-2-j , Signed lArvl--Commissions NB fr1{ J:ttJ/.} 1UJ ]7 J . / , Facto:ry Mutual EfBr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 Work performed by: 2. Owner: 3. Location:

4. System: Main Steam FORM Page _L of __,L *:

Package No.: PS93077 ;;. .< :._: .. -Public service Nuclear Dept. Foot of Buttonwood Road-Hancbcks 1 Bridge, NJ 08038 Public Service Electric'&; Gas>;co. Foot of Buttonwood Road',.-:Hanccicks Bridge, NJ 08038 Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Nuclear Class:

==================================================================

ID of Component Replacement: 1MSE65 Condensate Chamber Name of Manufacturer: Connex Pipe System 43471 N/A _____ 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: 43472 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.? Addenda, Code Class .2._ ID of Component Replaced: 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 Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.? Addenda, Code Class ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Code Cases: ---ID of Replacement: 1MSE68 Condensate Chamber Name of Manufacturer: 43474 N/A N/A N/A ial No. Nat'l. Bd. Jurist No. Other Year Built No 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 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 II b: Name of manufacturer Connex Pipe Systems c: Identifying nos. See Attachment N/A N/A {mfr's. serial no.) {Narl.Bd.No.)

Uurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 {addenda) SUrrnner 83 {edition) {addenda) {other) N/A N/A {Code Case{s)) 1993 (year built) II (Code Class) N/A {Code Case{s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 {edition) S83

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ASME III/ANSI B31. 7 1969 F.d. 1970 Add. *1989 (addenda) 1989 {Code Case{s)) N/A (edition)

{addenda) {Code Case{s)) 9. Design responsibilities _PS_E_&G _________________________________________ _ 10. Tests conducted: hydrostatic (8: pneumatic D design pressure D **pressure 1400 psi Code scription of work Installed new condensate chambers for #14 rnain steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks:

_________ De..,,,.,_f..._1...,' c,,..1...,' ..... 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 __ _ PSE&G Co. -Nuclear Dept. # p-/ -.... Date /-'2---Lr 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 and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National rules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, sed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be e in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ,c; / Facto:ry Mutual Assn. Date r-J. 'i ' 1 M_. Signed L twL-Commissions

Jp f"f<ft/ f .UJtf 4Il 1J (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.s FORM NR-1 ATTACHMENT Code Job Package No.: PS93078 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 3. Location:

Salem Nuclear Generating station .,,; .. Foot of Buttonwood Road, Hancocks Bridge, NJ' 08038. 4. System: Main Steam Nuclear Class: II ==============================================================================* ID of Component Replacement: 1MSE69 Condensate Chamber Name of Manufacturer: ________________ _ 43471 N/A N/A N/A 1993 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: ________________ _ 43472 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No ASME Code Stamp'd.? Addenda, Code Class .a_ ============================================================================== ID of Component Replaced: 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: ________________ _ 43473 N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ASME III 1989 Edition 1989 Code Cases:N/A ANSI B31.7 1969 Ed. 1970 Add No *------,,---,------- AS ME Code Stamp'd.? Addenda, Code Class .a_ ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.? Editibn Addenda, Code Class Code Cases: ---ID of Replacement: 1MSE72 Condensate Chamber Name of Manufacturer: 43474 N/A N/A N/A ' al No. Nat'l. Bd. Jurist No. Other Year Built No ASME Code Stamp'd.? acement Const. Code: ASME III 1989 Edition 1989 Addenda, Code Class .a_ Cases:N/A ANSI B31.7 1969 Ed. 1970 Add ============================================================================== FORM NR-1 REPORT OF REPAIR D 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 c: Identifying nos. N/A N/A N/A N/A ---=1=-9=-93=--------(mfr's. serial no.) (Nat'l.Bd.No.)

Uurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda) summer 83 (edition) (addenda) (other) N/A (Code Case(s)) (year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 __ _ 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B3l.7/PS Spec S-C-MBCX:>-MLB-043, 1985 *1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities _PS __ E_&G _________________________________________ _ 10. Tests conducted: hydrostatic D pneumatic D design pressure D ** pressure N/A psi Code

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:

.... c=1=' ...... Desiqn Change Package #: lEC-3256 Pkg. 1 See attached pages for Description of Replacement. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, . 199_4 __ _ Date /-3 9 PSE&G Co. -Nuclear Dept. 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 //-// , 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. Date /-J'.-'J , 1M. Signed*tvnui. __ Commissionsµ/Jfl1t/MJA t</J)J} 9 -/ /1 Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB-81 Rev.6 FORM NR-1 ATTACHMENT Page _L of _L Code Job Package No.: PS93079 Work performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 System: Main Stearn Nuclear Class: II 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 erial No. Nat'l. Bd. Jurist No. Other Year Built . eplacernent Const. Code: ANSI B31. 7 1969 Edition 1970 ;/Code Cases :N/A PS Spec S-C-MBOO-MDS-043 1985 No *----------- AS ME Code Starnp'd.? Addenda, Code Class II

Yfif ID of Component Replaced

1(\> e of Manufacturer: ,-,,_.,, f*:/ 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 Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code PS Spec S-C-MBOO-MDS-043 1985 No , ... ,,.*. Serial No. Nat'l. Bd. Original Const. Code: Jurist No. Other Year Built ASME Edition Addenda,<C9.g: Code Cases: ----.

....... J., ..

Name of Manufacturer: ial No. Nat'l. Bd. Jurist No. lacernent Const. Code: e Cases: ----Other -' 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 __ (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 II 5.a:

___ b: Name of manufacturer ___ PS_E_&G _____________________________________ _ c: Identifying nos. ____ _ N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) Qurisdictional no.) (other) d: Construction Code See Attachment N/A N/A (edition) 1983 (addenda) (Code Case(s)) 6. Section XI SUrmner 83 (edition) (addenda)

7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: 1983 (edition)

1969 *ANSI B31. 7 /PS Spec S-C-MB'.JO-Mffi-043 1 1985 (edition) 1993 (year built) II (Code Class) NIA (Code Case(s)) S83 .....:N=-:../,_,,A=---(addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities

__ PS_E_&G ______________________________________ _ 10. Tests conducted: hydrostatic D pneumatic D design pressure O *"'Pressure N/A psi Code Case(s) __ _____ _ 11. Description of work Installed for condensate pots on #12 main steam header. (use of additional sheet(s) or sketch( es) is acceptable if properly identified)

12. Remarks: __

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 ----Date j-3 PSE&G Co.-Nuclear Dept. t1 pt ;;; . 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 //-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. {. 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 ' FORM NR-1 ATTACHMENT Page _A_ of _A_ Code Job Package No.! PS93080 Work performed by: Public Service Electric & Gas co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 2. Owner: Public Service Electric & Gas Co. Foot of Buttonwood Road, Han cocks Bridge, NJ 08038 3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Main Steam Nuclear Class: II ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code stamp'd.? Edition Addenda, Code Class Code Cases: ---ID of Replacement: lC-MSG-2534 A&B Supports Name of Manufacturer: N/A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code stamp 'd. ?* Addenda, Code Class II ============================================================================== of Component Replaced: of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Code Cases: ---ID of Replacement: lC-MSG-2535 A&B Supports Name of Manufacturer: N/A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code Stamp'd.? Addenda, Code Class II ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of* Replacement: Name of Manufacturer: 'al No. Nat'l. Bd. Jurist No. acement Const. Code: Code Cases: ---Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.? Addenda, Code Class FORM NR-1 REPORT OF REPAIR D 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

_ 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.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda) SUrnmer 83 (edition) (addenda) (other) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/PS Spec S-C-MBJO-MD3-043, 1985 *1969 (edition) (year built) II (Code Class) N/A (Code Case(s)) S83 N_,,/_A __ _ (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities

_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:

______ _ 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 ----.... Principal Engr. Date /-)' PSE&G Co.-Nuclear Dept. 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 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: II ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code 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 Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code Stamp'd.? Addenda, Code Class II ============================================================================== ID of Component Replaced: of Manufacturer: Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.? 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__ Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No AS ME Code Stamp'd.? Addenda, Code Class II ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Code Cases: ---ID of Replacement: Name of Manufacturer: 1 No. Nat'l. Bd. Jurist No. cement Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class _ Cases: ---==============================================================================

-t ; b :::: FORM NR-1 REPORT OF REPAIR D 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 II 5. a: Component repaired, modified or replaced 1C-MSG-2564A&B, 1C-MSG-2565A&B SUpports b: Name of manufacturer

_ __.PS--=E=&G""'---------------------------------------- c: Identifying nos. N/A N/A N/A N/A ___ _ (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) d: Construction Code See Attachment N/A 6. Section XI (edition) 1983 (addenda) SUrnrner 83 (edition) (addenda) (other) N/A (Code Case(s)) (year built) II (Code Class) N/A (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition) S83 =NL-'/A=-=-----

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *ANSI B31.7/PS Spec S-C-MB'.X>-MI:S-043, 1985 *1969 (edition) (addenda) 1970 (addenda) (Code Case(s)) N/A (Code Case(s)) 9. Design responsibilities

-=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 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:

c""1"" ______ _ 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 __ _ Date I -;J 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 Arkwriaht Mutual Insurance Co of MA have inspected the repair, modification or replacement described in this report on , 19'J} and state that to the best of my knowledge and belief, this repair, modification or replacement has been made in accordance with Section XI of the ASME Code and the National *ules as defined in the publication NB-102, current edition. By signing this certificate, neither the Inspector nor his employer makes any warranty, ed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be n any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. . / / " Factory Mutual Engr. Assn. Date I -2 if ' 19q '-/ . Signed rt.4./ '2--Commissions N8 sr ft-/ f°N ;4 rv:JJ?.J (Inspector) (Natl.Bd .No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*81 Rev.6 FORM NR-1 ATTACHMENT Page __L of __L Code Job Package No.: PS93082 performed by: Public Service Electric & Gas Co., Nuclear Dept. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 2. Owner: Public Service Electric & Gas co. Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 3. Location: Salem Nuclear Generating Station Foot of Buttonwood Road, Hancocks Bridge, NJ 08038 4. System: Main Steam Nuclear Class: II ============================================================================== ID of Component Replaced: __ Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code 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 Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No ASME Code Stamp'd.? Addenda, Code Class II ============================================================================== rial No. Nat'l. Bd. Jurist No. Other Year Built ASME Code Stamp'd.? Original Code: Edition Addenda, Code Class Code Cases: ---ID of Replacement: lC-MSG-2565 A&B Supports Name of Manufacturer: PSE&G ___ _ N/A N/A N/A N/A Serial No. Nat'l. Bd. Jurist No. Other Year Built Replacement Const. Code: ANSI B31.7 1969 Edition 1970 Code Cases:N/A PS Spec S-C-MBOO-MDS-043 1985 No AS ME Code Stamp'd.? Addenda, Code Class II ============================================================================== ID of Component Replaced: Name of Manufacturer: Serial No. Nat'l. Bd. Jurist No. Original Const. Code! Code Cases: ---ID of Replacement: Name of Manufacturer: Nat'l. Bd. Jurist No. Const. Code: Other Year Built ASME Code Stamp'd.? Edition Addenda, Code Class Other Year Built Edition ASME Code Stamp'd.? Addenda, Code Class _ ============================================================================== --- ..............

FORM NR-1 REPORT OF REPAIR 0 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 b: Name of manufacturer In..c:;t.al 1 ed by J?SE&G c: Identifying nos. N/A N/A N/A Iruat,al led 1975 (mfr's. serial no.) (Nat'l.Bd.No.)

Ourisdictional no.) (other) (year built) d: Construction Code Specification 69-6445-1974 None 6. Section XI (edition) 1983 (addenda) SUnuner 83 (edition) (addenda) (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (Code Class) N/A (Code Case(s)) S83 (edition) (addenda) (Code Case(s)) 8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *Spec 696445 1974 *See BelOW'._,_,_ ___ None (edition) (addenda) (Code Case(s)) 9. Design responsibilities ________________________________________ _ 10. Tests conducted: hydrostatic D pneumatic D design pressure D** pressure N/A psi Code escription of work M.o:lify pipe support C-RWS-5 (use of additional sheet(s) or sketch(es) is acceptable if properly identified) 12.Remarks: _________ _______ _ 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. / / / :. Date ]' -;+.£ 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 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.

') ,..,.... Date J ,. 2) , 1rflL_. Signed * '7 ..,,,L--Commissions;\J,55%-i'f £v ;l ,if) 5 73 / (,_ Factory Mutual Engr. Assn. (Inspector) (Natl.Bd.No.(including or province and This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. 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. (name)
Foot of Buttonwood Road, Hancocks Bridge, NT 08038 CJP #PS93-088 Rev.a (repair organization's P.O. no., job. no.,etc.) (address) (name) Foot of Buttonwood Road, Hancocks Bridge, NT 08038 (address)

3. Name, address and identification of nuclear power plant Salem Nuclear Generating Station Unit #1 Foot of Buttonwood Road, Hancocks Bridge, NT 08038 4. System Control Air Nuclear Class II b: Name of manufacturer

_____________________________________ _ c: Identifying nos. N/A N/A N/A (mfr's. serial no.) (Nat'l.Bd.No.) Uurisdictional no.) d: Construction Code 69-6445/SG-SMFD-1 WA 6. Section XI (edition) 1983 (addenda) SUrnmer 83 (edition) (addenda) (other) None (Code Case(s)) 7. Applicable edition of ASME Code Section XI under which repairs, modifications, or replacements were made: 1983 (edition)

8. Applicable edition of Construction Code under which repairs, modifications, or replacements were made: *NIA *S-C--MB:X>-MCS-043 (edition) 1974 (year built) II (Code Class) :t{/A (Code Case(s)) S83 (addenda)

N/A (addenda) (Code Case(s)) None (Code Case(s)) 9. Design responsibilities

10. Tests conducted:

hydrostatic D pneumatic D design pressure D **pressure N/A psi Code Case(s) __

11. Description of work Replace 2 nuts on pipe support #P-CrAG-660.

(use of additional sheet(s) or sketch( es) is acceptable if properly identified) 12.Remarks:

__ _________ Design Change Package #: lEC-3150-1 Rev. O See attached pages for Description of Replacement. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and the repair, modification or replacement of the items described above conforms to Section XI of the ASME Code and the National Board rules as defined in the publication NB-102, current edition. Certificate of Authorization no. 36 to use the "NR" stamp expires Oct. 3, , 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, 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. Date J -2 ) , 1 sh_. Signed "l,. l-c_J.__- '/ J._,4/ A 11153 7 l . c,, 1 9 c.* / .. Fc:cto:ry Mutual Assn. 1 (Inspector) (Natl.Bd.No.(including endorsements)state or province and number) This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Avenue, Columbus, OH 43229. NB*B1 Rev.6}}

ML18100B034

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY