ML20217J522

Forwards SE Re Licensee & 970829 Suppl Requesting Relief from 10-yr ISI Requirements of Section XI of ASME Code.Util Should Follow All Provisions in Code Case N-509,w/ Limitations Issued in Reg Guide 1.147

ML20217J522
Person / Time
Site:	Beaver Valley
Issue date:	10/08/1997
From:	Stolz J NRC (Affiliation Not Assigned)
To:	Cross J DUQUESNE LIGHT CO.
Shared Package
ML20217J526	List: ML20217J522 ML20217J531
References
RTR-REGGD-01.147, RTR-REGGD-1.147 TAC-M98253, TAC-M98254, NUDOCS 9710210164
Download: ML20217J522 (4)

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, s NUCLEAR REGULATORY COMMISSION y $ t WASHINGTON, D.C. 20666-0001

\ # October 8, 1997 Mr. J. E. Cross '

President - Generation Group Duquesne Light Company Post Office Box 4 Shippingport, PA 15077

SUBJECT:

SAFETY EVALUATION OF BEAVER VALLEY POWER STATION, UNIT NOS 1 AND 2 (BVPS-1 AND BVPS-2), 10-YEAR INSERVICE INSPECTION (ISI) RELIEF REQUESTS (TAC NOS M98253 AND M98254)

Dear Mr. Cross:

By letter dated March 25, 1997, as supplemented August 29, 1997, Duquesne Light Company (DLC) submitted eight requests for relief from the ISI requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Three of these requests are applicable to BVPS-1, three are applicable to BVPS-2, and two are applicable to both BVPS-1 and BVPS-2.

The U.S. Nuclear Regulatory Commission (NRC) staff with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has reviewed and evaluated DLC's March 25 and August 29, 1997, requests for relief. As described in the attached safety evaluation (SE), the staff adopts the INEEL conclusions and recommendations presented in i the technical letter report (TLR), which is attached to the SE. For requests for relief BVI-83.120-2 and BV3-IWA-2, the NRC staff concluded that imposing the Code requirements on DLC results in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Therefore, DLC's proposed alternatives are authorized pursuant to the Code of Federal Reaulations (CFR),10 CFR 50.55a(a)(3)(ii). In addition, pursuant to i

10 CFR 50.55a(a)(3)(ii), DLC's proposed alternative, which is contained in request for relief BV3-IWA-1 is authorized for Class 1 bolted connections, but for Class 2 systems, the frequencies proposed for insulation removal have not been found acceptable by the NRC staff. Therefore, DLC's proposed alternative for the Class 2 systems is denied.

For request for relief BV2-D2.20-1, the NRC staff concluded that DLC's proposed alternative provides an acceptable level of quality and safety. l Therefore, pursuant to 10 CFR 50.55a(a)(3)(1), DLC's proposed alternative is authorized for Class 3 integrally-welded attachments. Use of alternatives contained in Code Case N-509 are authorized for the first interval or until such time as the Code Case is published in a future revision of Regulatory Guide 1.147. At that time, if the licensee intends to continue to implement this code case for Class 3 items, the licensee should follow all provisions in Code Case N-509, with limitations issued in Regulatory Guide 1.147, if any.

For requests for relief BVl-B9.31-2 and BV2-83.110-2, the NRC staff concluded that the ASME Code examination requirements are impractical. Therefore, 9710210164 971008 gD[ g So"

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, J. Cross .

pursuant to 10 CFR 50.55a(g)(6)(1), DLC's request for relief is granted. The reliefs and alternatives imposed are authorized by law and will not endanger life or property or the comen defense and security and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

Recuests for relief BVl-RV-WELDS and BV2-Bl.ll-1 were submitted to DLC to adcress limited ASME Code examination coverage for reactor vessel welds.

However, DLC has yet to fulfill the augmented examination requirements found in 10 CFR 50.55a(g)(6)(ii)(A) for welds that were not essentially 100%

examined. Therefore, the NRC staff concluded that evaluation of these requests are to be deferred until such time as DLC has satisfied the regulations by submitting an alternative to the augmented examination for reactor pressure vessel welds where essentially 100% volumetric coverage was not obtained.

Sincerely, Joh8 F. S[oTz, Y e[fift Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l

l Docket Nos. 50-334 and 50-412

Enclosure:

Safety Evaluation l

cc w/ encl: See next page DISTRIBUTION Docket File TMcLellan PUBLIC GBagcht PDI-2 Reading ACRS BBoger GHill (4)

JStolz THarris (E-Mail SE)

DBrinkman PEselgroth, RGN-1 M0'Brien BMcCabe OGC OFFICE PDI-2/PM A ff PQl-2/LA%Y OGh [dr PDI-2/DM NAME DBrinkma$frb N'Brien j NffH JStolz DATE /t /7 /97 t o / r)fg7 fgf)'jg7 ;pf gfg7 0FFICIAL RECORD COPY DOCUMENT NAME: BV98253 REL 1

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J. Cross 4 pursuant to 10 CFR 50.55a(g)(6)(i), DLC's request for relief is granted. The reliefs and alternatives imposed are authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest given due consideration to the burden upon the licensee that

could result if the requirements were impcsed on the facility.

Requests for relief BVl-RV-WELDS and BV2-Bl.11-1 were submitted to DLC to address limited ASME Code examination coverage for reactor vessel welds.

i However, DLC has yet to fulfill the augmented examination requirements found in 10 CFR 50.55a(g)(6)(ii)(A) for welds that were not essentially 100%

examined. Therefore, the NRC staff concluded that evaluation of these 1

requests are to be deferred until such time as DLC has satisfied the regulations by submitting an alternative to the augmented examination for i' reactor pressure vessel welds where essentially 100% volumetric coverage was not obtained.

Sincerely.

John F. Stolz, Director

, Proj t Directorate I-2 Division of Reactor Proj<ets - I/II l Office of Nuclear Reacta Regulation Docket Nos. 50-334 and 50-412

Enclosure:

Safety Evaluation

cc w/ encl

See next page i

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1 1

• J.-E. Cross Beaver Valley Power Station Duquesne Light Company- Units 1 & 2 cc: '

Jay E. Silberg, Esquire __

Bureau of Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW. Environmental Resources Washington, DC 20037 . ATTN: Michael P. Murphy Post Office Box 2063

' Director-Safety and Licensing Harrisburg, PA 17120 Department (BV-A)

Duquesne Light Company Mayor of the Borrough of 4

Beaver Valley Power Station Shippingport PO Box 4 Post Office Box 3 Shippingport, PA 15077 Shippingport, PA 15077 Commissioner Roy M. Smith -

Regional Administrator, Region 1 West Virginia Department of Labor -

U.S. Nuclear Regulatory Commission Building 3, Room 319 475 Allendale Road-Capitol Complex King of Prussia, PA 19406 Charleston, WVA 25305 Resident Inspector Director, Utilities Departinent U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573

' Director, Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport, PA 15077 Ohio EPA-DERP,-

ATTN: S. C. Jain, Vice President ATTN: Zack'A. Clayton -NuclearServices-(BV-A)

-Post Office Box 1049 Columbus, OH 43266-0149 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Duquesne Light Company Beaver. Valley Power Station

.P0 Box 4 Shippingport, PA _15077 ATTN: .R. L. Grand, Division Vice - - -

President,. Nuclear Operations Group and P1 ant Manager (BV-50SB-7)

____d