ML18095A497

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Forwards Vol 1 to Spring 1990 NDE of Selected Class 1 & Class 2 Components of Salem Generating Station,Unit 2, Re Inservice Insp Activities at Facility,Per Tech Spec Section 4.0.5 & ASME Code Section Xi,Article IWA-6220(b)
ML18095A497
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/24/1990
From: Labruna S
Public Service Enterprise Group
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NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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ML18095A498 List:
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NLR-N90187, NUDOCS 9010030216
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  • Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President

-Nuclear Operations SEP 2 4 1990 NLR-N90187 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

NINETY DAY REPORT FOR INSERVICE INSPECTION ACTIVITIES PERFORMED DURING THE FIFTH REFUELING OUTAGE SALEM GENERATING STATION -UNIT NO. 2. DOCKET NO. 50-311 Public Service Electric & Gas Company (PSE&G) hereby provides in the enclosures to this letter, the Ninety (90) Day Report for Inservice Inspection (ISI) activities conducted at Salem Unit 2 during the fifth refueling outage. This report is submitted in accordance with Section 4.0.5 of Appendix A to the Technical Specifications for Salem unit 2 and Article IWA-6220(b) of Section XI of the ASME Boiler and Pressure Vessel Code. This submittal consists of Form NIS-1, "Owners Data Report for Inservice Inspection" and Volume 1 of the 11 1990 Inservice Examination of Selected Components at Salem Generating Station, Unit 2 11 , prepared by Southwest Research Institute.

Should there be any questions with regard to this submittal, please do not hesitate to contact us. Enclosures

. -----\ 9010030216 900924 PDR ADOCK 05000311 Q PNU Sincerely,

..

  • Document Control Desk NLR-N90187 C Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector 2 Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief
  • SEP 2 4 1990 New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel J. Mossa New Jersey Department of Labor and Industry PO Box 1503, Labor & Industry Building Trenton, NJ 08625 ENCLOSURE 1 OWNERS DATA REPORT FOR INSERVICE INSPECTION
  • FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTORS 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. Owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Date 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 8. This report is for the first examination conducted in the third inspection period which ends October 13, 1991. The first inspection interval is from October 13, 1981, to October 13, 1991. 9. Components inspected:

COMPONENTS OR APPURTENANCE

  1. 2 Reactor Vessel #21 steam Generator
  1. 22 Steam Generator
  1. 23 Steam Generator
  1. 24 steam Generator Pressurizer MANUFACTURER OR INSTALLER Combustion Engineering Westinghouse Tampa Div. P.O. Box 19218 Tampa, FL 33616 II II II II II II Delta Southern MANUFACTURER OR INSTALLER SER. NO. 67201 Head 67101 Vessel 1201 1202 1004 1204 1211 Page 1 of 18 STATION OR PROVINCE NUMBER N/A N/A N/A N/A N/A N/A NATIONAL BOARD NO. 20765 68-43 68-44 68-11 68-52 68-48

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  • 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. 3. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038 Plant Unit 2 4. 5. Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 9. Components Inspected (cont'd).

COMPONENTS OR APPURTENANCE Chemical Volume & Control Piping System Containment Spray Piping System Mains team Piping Sys. Pressurizer Relief Piping Sys. Reactor Coolant Piping Sys. Residual Heat Removal Piping Sys. Steam Gen. Feed Piping System Safety Injection Piping Sys

  • MANUFACTURER MANUFACTURER OR INSTALLER OR INSTALLER SER. NO. 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 UE&C N/A UE&C N/A UE&C N/A UE&C N/A Page 2 of 18 STATION OR PROVINCE NUMBER N/A N/A N/A N/A N/A N/A N/A N/A NATIONAL BOARD NO. N/A N/A N/A N/A N/A N/A N/A N/A

  • FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTION 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. Owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Date 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 10. Abstracts of Examinations:

1.0 This report also contains augmented examinations

11. 1.0 required by Salem Technical Specifications and Regulatory Guides, Circulars, 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 according to Tech. Spec. paragraph number followed by applicable NRC circulars and bulletins.

Examination Summary Technical Specification 4.0.5 -ASME XI The examinations conducted during this outage completed the required number of examinations for the first examination of the third inspection period as shown in the 10 year long term inspection plan. Page 3 of 18

  • 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 1.1 ISI Examination Southwest Research Institute (SwRI) under the direction of the Salem ISI Group conducted seventy-three (73) ultrasonic, fifty-nine (59) liquid penetrant, nine (9) magnetic particle, and four (4) visual examinations on the Main steam, Residual Heat Removal, Reactor Coolant, Chemical and Volume Control, Steam Generator Feedwater, Safety Injection, and Containment Spray Systems. The following nonconformances were reported by SWRI: 1.1.1 Remote visual (VT) of the RPV with the core barrel in place, ASME Section XI examination category B-N-1, revealed numerous linear and irregular indications.

An attempt to confirm the most significant indication with UT yielded inconclusive results. Fracture mechanics sis was performed by PSE&G and Westinghouse assuming the worst case (through-wall) and the core barrel was allowed to operate through another refueling cycle. The areas will be examined during the 6th refueling/lo year ISI outage. 1.1.2 During the UT examination of 24MS167 valve bolting, ASME Section XI examination category C-D, a heavy deposit of yellow plastic like substance was noted on the valve body. PSE&G will correct this problem during a subsequent refueling outage . Page 4 of 18 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. Owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Date 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 1.1.3 PT examination of 22 RCP Flywheel in accordance with Reg. Guide 1.14 revealed numerous tions in the keyway areas. An evaluation was performed by Westinghouse Engineering and the indications were determined to be nonrelevant and conditions of original manufacture (See section 7.0 for more detail). No other reportable indications were observed during the examinations.

1.2 Visual Examinations of Supports 1.2.1 Contract personnel under the direction of the Salem ISI Group conducted visual examinations on two (2) Nuclear Class o, forty (40) Nuclear Class I, thirty-three (33) Nuclear Class II and two hundred and fifty-two (252) Nuclear Class III supports.

Several discrepancies were found, i.e. wrong spring settings, rust, loose bolts, etc. ciency report and/or work orders were generated to document and correct all discrepancies noted. Page 5 of 18 FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTION 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Data 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 1.3 Ten Year ISI Hydrostatic Test Program During the 5th Refueling outage of Salem Unit 2 a total of forty-three (43) hydrostatic tests were performed.

These tests were required as per ASME Section XI Ten Year Hydrostatic Testing. These tests were performed on the Auxiliary Feed, Component Cooling, Charging and Volume Control, Demineralized Water, Fire Protection, Main Steam, Station Air, Spent Fuel, Safety Injection, Sampling and Ventilation systems. This brings the total number of Ten Year Hydrostatic Tests to three (63) out of a predicted 125. 1.4 Service Pressure Leak Exams 1.4.1 As required by ASME Section XI, service pressure leak exams were performed by the Salem ISI Group on the following systems: Reactor Coolant, Containment Spray, Residual Heat Removal, Safety Injection, Reactor Coolant Sample, Waste Drain Liquid, Chemical and Volume Control (Operations), Pressurizer Relief Piping, Spent Fuel Cooling, Service Water, Fire tion, Component Cooling, Auxiliary Feed, eralized Water (Restricted), steam Generator Blowdown, and Chemical and Volume Control (water recovery).

None of the above listed systems exhibited any excessive leakage. Their was however, some minor mechanical leakage (eg. valve packing, etc.) for which work orders were written to correct. Page 6 of 18

  • 1. 2. 3. 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTION 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 owner's Certificate of Authorization (if required)

N/A. Commercial Service Data 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 2.0 Technical Specification 4.4.6.0 -Steam Generator Tube Eddy current Inspection.

2.1 The original eddy current examination scope is detailed below: 2.1.1 Twelve (12%) percent Tech. Spec. examination in #23 Steam Generator.

2.1.2 A non-tech spec. sample of eight hundred and eleven (811) tubes conducted in #23 S/G to try and comply with EPRI's recommended guidelines of conducting 100% examination of all the steam generator tubes over a period of six (6) years. This sample represented an additional 25% of this generator.

2.1.3 Examine all previous indications in the remaining steam generators

(#'s 21, 22 and 24)

  • 2.1.4 Perform a 10% sample (330 tubes) of the sheet region of #24 Steam Generator using a motorized rotating pancake probe to look for industry concerns from tube expansion by the WESTEX method. This sample was concentrated in the kidney region because of the high ty of indications due to sludge buildup. 2.1.5 Examine five (5) tubes with previous indications in the hot leg support plate region using both a bobbin and motorized pancake probe. This was performed to address an industry concern with through wall cracking occurring at the support plate that may not be identified with the bobbin probe inspection . Page 7 of 18
  • 1. 2. 3. 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTION 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Data 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 2.2 Tech. Spec. examinations in No. 23 Steam Generator revealed no pluggable indications.

In the non-tech.

spec. sample there were tubes with indications of cold leg thinning and/or anti-vibration bar wear which exceeded the Tech Spec. plugging limit. Based on these examination results and in complying with EPRI lines of examining the area's of concern, the tion plan was expanded to include 100% of all the tubes in #23 Steam Generator between Rows 20 and 46. This expansion program showed more evidence of cold leg thinning and/or AVB wear therefore additional tions were performed to include all the tubes down through row 6 to ensure the indications were only occurring in the higher row tubes. Examinations of the lower row tubes showed no evidence of these tions. The examinations were also expanded into #21 S/G to include all the tubes between Rows 30 and 46 and the tubes between Columns 30 through 70 on Rows 28 and 29. The same type of indications were also being found in the higher row tubes of #21 S/G, so the decision was made to examine all the tubes in #22 S/G between Rows 28 through 46 (except for the periphery tubes which were inspected during the previous outage) and in #24 S/G all the tubes between rows 28 through 46 and the periphery tubes, three columns deep, between rows 6 through 19. The examinations in #22 and #24 Steam Generators showed that this same condition was also occurring in the higher row tubes. All tubes exceeding the tech. spec. limit of 40% degradation of nominal tube thickness were mechanically plugged with verification performed by PSE&G personnel.

Page 8 of 18 FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTION 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. Owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Data 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 2.3 In addition to the eddy current inspections, the Row 2 tubes in all four (4) Steam Generators were U-bend heat treated. Eddy current was performed in the U-bend region to verify the proper heat affected zone had been achieved.

NOTE: All the row one (1) tubes in all four (4) Steam Generators are currently plugged. 2.4 Results of the examinations are as follows: Steam Extent of No. of Tubes Generator Exam. Inspected Tubes with Indications (3) < 20% 20-39% > 40% 21 22 23 24 Full Length U-Bend Verify Full Length U-Bend Verify Full Length U-Bend Verify Full Length U-Bend Verify Tubesheet Support Plate Sub-Total Full Length U-Bend Verify Tube sheet Support Plate Total 940 95 (*) 896 94 2801 94 1142 94 330 5 5779 377 330 5 6491 20 N/A 6 N/A 46 N/A 14 N/A 0 0 86 N/A 0 0 86 19 N/A 10 N/A 40 N/A 15 N/A 0 0 84 N/A 0 0 84

  • One tube in Row 3 was heat treated inadvertently.

Page 9 of 18 6 N/A 3 N/A 11 N/A 20 N/A 0 0 40 N/A 0 0 40

  • 1. 2. 3. 4. 5. 6. 7. FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTION 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Data 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 2.5 Some of the other S/G work for this outage included installing a plug-in-plug (PIP) fix for the Inconel 600 plug material which was identified as having a bad heat number. This fix .was applied to all the Row 1 hot leg plugs between columns 6 and 90 in all four (4) steam generators, except for eight (8) tubes previously tified as leaking or having a high potential to leak in #24 S/G. These plugs were manually pulled and a new Inconel 690 plug installed.

Some of the Row 1 tubes were unable to have a PIP installed so the existing plugs were removed and replaced with new Inconel 690 plugs. 2.6 Current Status of the Steam Generators At this time the total number of tubes plugged in the Salem Unit 2 Steam Generators are as follows: Generator

  1. 21 22 23 24 Tubes Plugged 102 100 111 111 NOTE: In the Steam Generator's 21-24, the first five (5) and the last Five (5) tubes in row 1 were mechanically plugged because of a generic wearing problem on the tubes, due to the vibration of the tube lane blocking device. The remaining tubes in Row 1 were plugged because there was evidence in two (2) of the steam generators of the onset of stress corrosion cracking in the u-bend area. Page 10 of 18
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  • 1. 2. 3. 4. 5. 6. 7. 11. 3.0 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. Examination Summary {Cont'd) Technical Specification 4.6.1.2d, Containment Type "B" {Penetrations) and Type "C" (Valves) Leak Rate Testing. 3.1 Summary The PSE&G Research Corp. under the field supervision of the Salem ISI group, conducted seventy (70) Type "B" tests and one hundred thirteen {113) type "C" tests. The results of this testing revealed several Type "C" valves exceeding the recommended leak rate acceptance criteria, which were reworked to an acceptable tion . A total as found leakage rate of 29,796.0 SCCM was measured through all type "B" and "C" containment penetrations.

After corrective maintenance, a total as left leakage of 25,258.4 SCCM was measured through all type "B" and "C" penetrations.

In addition to the above tests the Leak Rate Test for 21, 22, 23 and 24GB4's was performed to satisfy the Field Directive S-C-R700-MFD-288, Leak Rate Test Program for the Steam Generator Blowdown Isolation Valves {GB4) Units 1 and 2, Salem Station. Results of the test were satisfactory.

4.0 Technical Specification 4.6.1.3b Elevation 100 1 and 130 1 Airlock Leak Rate Tests 4.1 Summary The PSE&G Research Corporation under the supervision of the Salem ISI performed leak rate tests and door lock checks on the 100' and 130 1 Airlocks.

The present leakage is 2618 SCCM . Page 11 of 18

  • 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. Owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Date 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through
11. Examination Summary {Cont'd) 5.0 Technical Specification 4.7.9.(a) "Visual Inspection of Hydraulic and Mechanical Snubbers" 5.1 Summary Contract personnel under the direction of the Salem ISI Group conducted visual examinations on twenty four (24) hydraulic and one hundred twelve {112) mechanical snubbers.

No discrepancies were found that would effect operability.

However, several minor indications were found such as minor rust and attachment ends having washers missing, and union leaks (hydraulic snubbers).

All discrepancies were corrected.

6.0 Technical Specification 4.7.9 (c) "Functional Testing of Selected Hydraulic and Mechanical Snubbers" 6.1 Summary -Hydraulic Snubbers Technical Specification 4.7.9 requires functional testing on 10% of the total number of installed hydraulic snubbers, during each plant refueling outage. In addition, all snubbers which failed their previous functional test shall also be functionally tested. Hydraulic snubber in-place functional testing was performed by WYLE Laboratories using the WYLE API Hydraulic Snubber Test System. The results of these tests revealed the following:

-One (1) 200 kip main steam isolation valve {MSIV) hydraulic snubber "as-found" test acceptable.

-Four (4) 1000 kip steam generator

{S/G) hydraulic snubbers (two (2) from required sample and two (2) from a previous failures) were "as-found" tested. The test results were acceptable . Page 12 of 18

  • 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. Examination Summary (Cont'd) 6.2 Summary -Mechanical Snubbers Technical Specification 4.7.9 requires functional testing on 10% of the total number of installed mechanical snubbers, during each Plant Refueling outage. In addition, for each snubber that does not meet the acceptance criteria an additional 10% of the mechanical snubbers shall be functionally tested. The mechanical snubber tests were performed on-site by PSE&G personnel utilizing the WYLE Model 150 Snubber Testing Machine. -The initial (10%) sample of mechanical snubbers functionally tested consisted of: two (2) PSA-1, five (5) PSA-3, and two (2) PSA-10 for a total of nine (9) snubbers.

In addition to the initial sample all the PSA-1/4's (nineteen (19)) and PSA-1/2's (three (3)) were functionally tested. NOTE: All PSA-1/4 1 s and the 1/2's are tested each refueling outage due to their failure rate from previous outages. Due to the fact that they are tested each refueling outage, they are not considered in the count for the 10% Technical Specifications' sample. Due to a test failure identified on a PSA-10 snubber during the initial sample, a Second 10% sample was selected for testing

  • Page 13 of 18
  • 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. Examination Summary (Cont'd) -The Second (10%) sample of mechanical snubbers consisted of two (2) PSA-1, four (4) PSA-3 and three (3)PSA-10 for a total number of nine (9) snubbers.

Due to a test failure identified on a PSA-3 snubber during the Second sample, a Third 10% sample was selected for testing. -The Third (10%) sample of mechanical snubbers consisted of: one (1) PSA-1, four (4) PSA-3 and four (4) Psa-10 for a total of nine (9) snubbers.

All snubbers from the third sample were tested satisfactory, thus no additional testing was required.

The mechanical snubbers which failed functional testing were removed from service and replaced in kind. An engineering evaluation was performed on the failed mechanical snubbers and it was mined that the degraded components would not have adversely affected system operation.

7.0 Technical Specification 4.4.11.1 Reactor Coolant Pump Flywheel Examination 7.1 summary Southwest Research Institute (SwRI) performed ultrasonic examinations (UT) of the top sides only on 12 Reactor Coolant Pump flywheel (#12 RCP motor is currently stalled in #22 RCP location) and the Spare Reactor Coolant Pump Flywheel, serial no.# 01, which is ly installed in #23 Reactor Coolant Pump location.

No reportable indications were observed . Page 14 of 18

  • 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 E Hancock's Bridge, N.J. 08038 Plant Unit 2 Owner's Certificate of Authorization (if required)

N/A. Commercial Service Date 10/13/81.

National Board Number for Unit N/A. Examination Dates: 4/1/90 through 6/24/90. Examination Summary (Cont'd) SwRI also performed surface examinations (PT & MT) of all exposed surfaces and a complete ultrasonic tions (UT) of 22 Reactor Coolant Pump Flywheel at the Westinghouse facility in Cheswick, Pennsylvania.

The PT examinations revealed twenty (21) groups of recordable indications in the three (3) keyway areas. A deficiency report was generated to document the examination sults. An evaluation report was performed by house Engineering and it was determined the indications were nonrelevant and were conditions of original facture. No additional indications were noted. NOTE: These indications were also observed during the 1983 examination of this flywheel.

Per tion of the 1983 deficiency report the tions were determined to nonrelevant.

ry grinding revealed depth of no more than 1/16 11 and the indications were not detected by UT. 8.0 Special Examinations 8.1 NRC Circular 76-06 and NRC Bulletin 79-17 commitment to examine and/or flush stainless steel lines containing stagnant borated water. As part of the ISI program, SwRI performed ultrasonic examinations on eleven (11) piping welds covered by this circular.

There were no adverse findings in the nations. Quarterly chemistry samples were taken by the PSE&G Chemistry Department and the results transmitted to the Salem ISI Group as required by Chemistry Procedure CH-3. 5. 060. During the past 18 months, this program tified a few nonconformances.

The nonconforming piping was flushed and the situation corrected.

This was verified by additional sample analysis . Page 15 of 18 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Date 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 8.2 NRC Bulletin 82-02 "Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of Power Plants. Visual (VT) and Magnetic Particle (MT) exams were performed on all four (4) Steam Generator primary manway bolts. No reportable indications were observed.

All bolts were then lubricated with a thin coating of Felpro N5000 lubricant and reinstalled.

The Reactor Coolant Pump Main flange bolting was visually examined in place. No reportable indications were observed.

8.3 NRC Bulletin No. 88-08, "Thermal Stresses in Piping Connected to Reactor Coolant Systems", sixteen (16) 1.5-inch Safety Injection, and two (2) 2-inch and two (2) 3-inch Chemical and Volume Control welds were examined with UT and PT. No reportable indications were noted. 8.4 NRC Bulletin 88-11 "Pressurizer Surge Line Thermal Stratification", all four (4) welds on the 14 inch pressurizer surge line were examined with UT. No cordable indications were noted. 8.5 NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants", measurements were taken at seventy three (73) locations to identify possible pipe corrosion/erosion.

Other than insignificant thinning noted in a few areas, no other conditions were observed.

Page 16 of 18 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 E Hancock's Bridge, N.J. 08038 3. Plant Unit 2 4. owner's Certificate of Authorization (if required)

N/A. 5. Commercial Service Date 10/13/81.

6. National Board Number for Unit N/A. 7. Examination Dates: 4/1/90 through 6/24/90. 11. Examination Summary (Cont'd) 9.o-summary NuReg 0578 -TMI Lessons Learned -Perform Service Pressure Leak Exams on systems outside Containment, and take Corrective Actions necessary to reduce leakage as low as possible on systems likely to contain Radioactive liquids in the event of an incident.

The Salem ISI Group performed Service Pressure Leak Exams on the Safety Injection, Chemical Volume and Control, Residual Heat Removal and Containment Spray systems. In addition, PSE&G Research Corp. under the direction of the Salem ISI Group conducted the Waste Gas System Integrated Leak Rate test in accordance with ISI Procedure M9-ILP-WG-1.

There were no adverse findings in the examinations or tests conducted relative to this bulletin.

Page 17 of 18 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. Certificate of Authorization No. (if applicable)

NR-36 Expiration Date 10-03-91 Date 17 4-@.J= ' 19 'lo Signed PSE&G Owner 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 Report during the period 4/1/90 to 6/24/90 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 tions 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.

Date -t:t-l7 I 19 90 --"'------'-----

Factory Mutual System Commissions

,,. n AJ:f J7.J r National Board, State, Province and No. Page 18 of 18 ENCLOSURE 2 1990 INSERVICE EXAMINATION OF SELECTED COMPONENTS AT SALEM GENERATING STATION -UNIT 2

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