ML20195J294

Forwards Safety Evaluation Re First & Second 10-year Interval Inservice Insp Request for Relief

ML20195J294
Person / Time
Site:	Beaver Valley
Issue date:	11/12/1998
From:	Capra R NRC (Affiliation Not Assigned)
To:	Cross J DUQUESNE LIGHT CO.
Shared Package
ML20195J299	List: ML20195J294 ML20195J313
References
TAC-MA0182, TAC-MA0183, TAC-MA182, TAC-MA183, NUDOCS 9811240234
Download: ML20195J294 (4)

Text

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November 12, 1998 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), FIRST AND SECOND 10-YEAR INTERVAL INSERVICE INSPECTION (ISI) REQUESTS FOR RELIEF (TAC NOS, MA0182 AND MA0183)

Dear Mr. Cross:

By letter dated November 24,1997, as supplemented May 12,1998, Duquesne Light Company (DLC) submitted six requests for relief from the ISI requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Two of these requests are applicable to BVPS-1, two are applicable to BVPS-2, and two are applicable to both BVPS-1 and BVPS-2. The May 12,1998, letter provided revisions to one of the requests applicable to BVPS-1 and one of the requests applicable to 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 November 24,1997 and May 12,1998, requests for relief. As described in the enclosed safety evaluation (SE), the NRC staff adopts the INEEL conclusions and recommendations presented in the technical letter report (TLR), which is attached to the SE. For requests for relief BV1-RV-AUG-1 and BV2-RV-AUG-1, the NRC 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 altematives are authorized pursuant to the Code of Federal Reoulations (CFR),10 CFR 50.55a(a)(3)(ii).

For requests for relief BV1.RV-WELDS and BV2 B1.11-1, the NRC staff concluded that the ASME Code examination requirements are impractical. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), DLC's requests for relief are granted. The reliefs and attematives imposed are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest giving due consideration to the burden upon the licensee that /

could result if the requirements were imposed on the facility.

Two requests for relief, BV3-lWA 1, Revision 1 and BV3-lWA-2, Revision 1, were included iri the November 24,1997, submittal for reference purposes only. These requests for relief are applicable to both BVPS-1 and BVPS-2 Revision 0 of these requests for relief for Class 1 systems was addressed in our SE dated October 8,1997 (TAC Nos. M98253 and M98254).

Revision 1 of these requjsts for relief reflects additional statements made in DLC's response

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! J. Cross  ;

i. l to our request for additional information (RAl) dated August 29,1997. Based on DLC's response to the RAI and our October 8,1997, SE, we have concluded that no additional evaluation was  :

n warranted. Therefore, DLC's proposed altemative as approved in our October 8,1997, SE  !

remains valid and is authorized for Class 1 systems for the current interval.

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Sincerely, l

! /s/ l 4 Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation J

Docket Nos. 50-334 and 50-412 Enciosure: Safety Evaluation  ;

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' PUBLIC' PDI-2 Reading JZwolinski .

RCapra DBrinkman MO'Brien GHatchett TMcLellan GBagchi GHill(2) oGC ACRS 8McCabe THarris (E-Mail SE)

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J. Cross 1 4

' to our request for additional information (RAl) dated August 29,1997. Based on DLC's response to the RAI and our October 8,1997, SE, we have concluded that no additional evaluation was warranted. Therefore, DLC's proposed alternative as approved in our October 8,1997, SE remains valid and is authorized for Class 1 systems for the current interval.

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Sincerely, M +a..C y

Robert A. Capra, Director Project Directorate 1-2 i Division of Reactor Projects - t/11 l Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosure:

Safety Evaluation <

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J. E. Cross Beaver Valley Power Station, Units 1 & 2 Duquesne Light Company 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) 1 Duquesne Light Company Mayor of the Borough of 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 I 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, WV 25305 Resident inspector Director, Utilities Department U.S. Nuclear Regulatory Commission i Public Utilities Commission Post Office Box 298 1 180 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 ATTN: S. C. Jain, Senior Vice President Ohio '5PA-DERR Nuclear Services (BV-A)

ATTN: Zack A. Clayton Post Office Box 1049 Mr. J. A. Hultz, Manager Columbus, OH 43266-0149 Projects & Support Services First Energy Dr. Judith Johnsrud 76 South Main Street National Energy Committee Akron, OH 44308 Sierra Club 433 Orlando Avenue State College, PA 16803 Duquesne Light Company Beaver Valley Power Station PO Box 4 Shippingport, PA 15077 ATTN: Kevin L. Ostrowski, Division Vice President, Nuclear Operations Group and Plant Manager (BV-SOSB-7) _