IR 05000272/1986016

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Insp Repts 50-272/86-16 & 50-311/86-16 on 860519-23.No Violation Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,Part 21 Rept on Asco Valves & Inservice Insp Activities
ML18092B199
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/05/1986
From: Mcbrearty R, Wiggins J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18092B198 List:
References
50-272-86-16, 50-311-86-16, NUDOCS 8606260264
Download: ML18092B199 (6)


Text

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No /86-16 50-311/86-16 Docket No ___ 3_1_1_. --

License Nos. DPR-70

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Priority ---

Licensee:

Public Service Electric and Gas Company P. 0. Box 236 Hancocks Bridge, New Jersey 08038 Facility Name:

Salem Nuclear Generating Station Units 1 & 2 Inspection At:

Hancocks Bridge, New Jersey Inspection Conducted:

May 19-23, 1986


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"ef, Materials & Processes Category _C_

' da'le Inspection Summary:

Inspection on May 19-23, 1986 (Combined Report Nos. 50-272/

86-16 and 50-311/86-16).

Areas Inspected:

Routine, unannounced inspection by one regional based inspector of licensee action on previous inspection findings; Part 21 report on ASCO valves; Inservice Inspection activities including Q.A. involvement and eddy current examination results of steam generator tubing examination Results:

No violations were identifie I

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  • DETAILS Persons Contacted Public Service Electric & Gas Company W. Denlinger, Quality Assurance Engineer D. Dodson, Licensing Engineer
  • R. Dulee, Principal Engineer-Quality Assurance
  • L. Lake, Inservice Inspection Engineer
  • L. K. Miller, Assistant General Manager-Salem Operations D. Perkins, Manager Station Quality Assurance W. Freston, ISI Supervisor U.S. Nuclear Regulatory Commission
  • T. J. Kenny, Senior Resident Inspector
  • Indicates those present at the exit meetin Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (272/84-22-01): Licensee review of ISI dat The inspector reviewed documents which verified that all ISI data associated with the 1984 refueling outage were reviewed by the license Addition-ally, the inspector was provided with documentation which indicated that the 1986 refueling outage data were reviewed in accordance with Station Review Procedure M31-Q-047, Revision 0 entitled 11 Review of SwRI NOE Sheets.

The procedure provides a list of attributes to be examined and requires that the reviewer must be certified as a Level II or Level III in the method under revie Based on the above this item is considered close (Closed) Unresolved Item (311/84-45-01): Licensee review of ISI dat The inspector reviewed documents which verified that the subject ISI data were reviewed by the license The review was done in accordance with a pro-gram in which the licensee has established attributes which the Level II or Level III reviewer must consider regarding the data under revie Based on the above this item is considered close.

Inservice Inspection (ISI) Nondestructive Examination (NOE) Procedure Review The inspector reviewed nondestructive examination procedures to ascertain compliance with ASME Code and regulatory requirement *.;:.:.:._,

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The following procedures which were used during the 1986 Unit 2 refueling outage were included in the inspector's review:

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0 SwRI-NDT-200-1 Revision 68, "Solvent Removable Liquid Penetrant Color Contrast Examination" SwRI-NDT-600-3, Revision 62, "Manual Ultrasonic Examination of Pressure Piping Welds" SwRI-NDT-600-16, Revision 29, "Manual Ultrasonic Examination of Vessel Support Skirt Attachment Welds" SwRI-NDT-800-104, Revision 0, "Inner Surface Examination of The Access Holes in Pressure Retaining Studs Two-Inches and Greater In Diameter" No violations were identifie.2 Review of Nondestructive Examination (NOE) Data The inspector selected for review data representing ultrasonic examinations which were performed during the 1986 refueling outage at Unit The review was done to ascertain compliancs with appli-cable ASME Code and regulatory reqi.;irements, and with licensee commitment Data representing the following welds were included in the inspector's review:

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Pressurizer weld number 1-PZR-IVS, lower head to skirt weld Pressurizer Relief weld number 6-PR-1104-3, 6 11 diameter elbow to elbow weld Reactor Coolant System weld number 31-RC-1130-3, 31 11 diameter elbow to pipe weld Reactor Coolant System weld number 29-RC-1130-3, 29 11 diameter pipe to pipe weld Reactor Coolant Pump #14 studs Ultrasonic indications which were detected in the welds were evaluated by a qualified SWRI individua The evaluation process consisted of plotting the indication location, comparing the data to preservice inspection results, and the use of supplemental exami-nation technique All data were subsequently reviewed by the licen-se No violations were identifie *

4 Review of Steam Generator Tubing Eddy Current Examination Data Documentation and data associated with eddy current examination of number 11 steam generator tubes were reviewed by the inspector to ascertain compliance with Technical Specification and regulatory requirement A total of 419 tubes were examined which is approximately 12% of the tubes in the generato Eight peripheral tubes (included in the 419 total) were examined to verify that foreign materials which were found in the generator did not damage the tube wall Also included in the sample were tubes with indications identified during the 1982 inspectio Full length examinations (tube sheet to tube sheet) were done on 375 tubes, and 44 tubes were examined to the U-bend on the hot leg sid All examinations were conducted from the hot leg sid No tubes were found to require removal from service, and 10 previ-ously installed plugs were found to be intac The examinations were performed by Westinghouse Electric Corporation personnel who were qualified in the eddy current examination metho No violations were identifie.4 NOE Personnel Qualification/Certification Records The inspector selected for review records of SwRI personnel who performed ultrasonic examinations at Salem Unit 1 during the 1986 refueling outag The inspector found that the personnel were pro-perly qualified in accordance with SNT-TC-lA, the governing documen In addition the records indicated that the personnel had current examinations for visual acuit No violations were identifie.

In Core Flux Thimble Tubes - Eddy Current Examination The inspector reviewed documentation associated with the eddy current examination of the subject thimble tubes to ascertain that the examina-tions were done by qualified personnel and that the results were evaluated by qualified individual All the tubes (58) were examined using the MIZ-12 system by PSE&G Research and Testing Laboratory personne The records indicated that the exami-nations were properly conducted, and the results were evaluated by quali-fied personne Additionally, the final report was reviewed by a Level III individua No violations were identified.

5 Quality Assurance (Q.A) Involvement With !SI The inspector interviewed Q.A. personnel and reviewed surveillance reports to ascertain that the site Q.A. group actively participated in IS!

activitie Reports of surveillance done during the period from April 1, 1986 to May 1, 1986 included Q.A. coverage of SwRI activities and of the eddy current examination of steam generator tubes which was done by Westinghouse per-sonne The inspector found that critical examination attributes were considered, follow-up was done when it was required, and that the results were clearly documente No violations were identifie.

Request For Relief From ASME Section XI Requirements The licensee has requested relief from the ASME Code Section XI, 1974 Edition through Summer 1975 Addenda requirements regarding hydrostatic test pressure for 22 ASME Class 2 and Class 3 pumps in each unit. Arti-cles IWC-5200 and IWD-5200 require the hydrostatic test pressure to be 1.25 and 1.10 times the design pressure respectively, but the requirements do not address the different pressure ratings on the suction and discharge side of pumps, nor what is to be used as a boundary interfac The licensee has proposed the following clarification of the requirement as an alternate to the requirement as stated in the 1974 Edition of Sec-tion XI:

11Where the respective system primary pressure ratings on the suction and discharge sides of system pumps differ, the system test boundary shall be divided into two separate boundaries (such as suction side and discharge side test boundaries).

In the case of positive dis-placement pumps, the boundary interface shall be considered as the pum In the case of centrifugal pumps, the boundary interface shall be the first shutoff valve on the discharge side of the pump.

The above is included in the 1977, 1980 and 1983 Edition of Section XI and has been approved by the NRC in reference in 10 CFR 50.55 The inspector did a walkdown of the piping associated with the following pumps subject to the relief request:

Number 11 Containment Spray Pump - ASME Class 3

Number 11 Charging Safety Injection Pump - ASME Class 2

Number 11 Auxiliary Feed Pump - ASME Class 3

The walkdown was done to confirm the length of piping which would be tested at the lower test pressure as requested by the license The inspector found that the piping was as stated by the licensee and no problems were identifie.

Automatic Switch Company (ASCO) Valves (Part 21 Report)

The Automatic Switch Company of Florham Park, New Jersey, advised the NRC and the licensee by letter dated March 31, 1986, of a problem regarding 20 nuclear valves which were shipped to Public Service Electric and Gas Compan Certain internal parts of the valves, serial numbers 86157Nl-20, were lapped in order to reduce seat leakag This lapping reduced or elimi-nated nickel plating in certain areas which could lead to greater than allowable seat leakage and shifting problems before the valves attain their qualified lif ASCO has requested the return of the valves for examination and rebuilding as applicabl The valves have not been installed and the inspector was advised that the licensee plans to return them to ASC This item will remain open pending the return of the valves to ASCO (272/86-88-01), (311/86-88-01). Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)

at the conclusion of the inspection on May 23, 198 The inspector summarized the purpose and the scope of the inspection and the finding At no time during this inspection was written material provided by the inspector to the licensee.