ML20217C674

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Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr
ML20217C674
Person / Time
Site: Beaver Valley
Issue date: 10/08/1999
From: Dan Collins
NRC (Affiliation Not Assigned)
To: Cross J
DUQUESNE LIGHT CO.
References
GL-96-06, TAC-M96777, TAC-M96778, NUDOCS 9910130315
Download: ML20217C674 (5)


Text

  • Mr. J. E. Cross October 8, 1999 Pr:sid:nt-G:n: ration Group Duqu:sn3 Light Compiny Post Offica Box 4 Shippingport, PA 15077

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAl) REGARDING THE RESPONSE TO GENERIC LETTER (GL) 96-06, BEAVER VALLEY POWER STATION, UNIT NOS.1 AND 2 (BVPS-1 AND BVPS-2)(TAC NOS. M96777 AND M96778)

Dear Mr. Cross:

By letter dated January 28,1997, the Duquesne Light Company (DLC) submitted a response to GL 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated September 30,1996. By letters dated June 30,1998, February 2, ,

and' June 2,1999, DLC submitted responses to a Nuclear Regulatory Commission (NRC)

Request for Additional Information (RAl), and supplemental n1 formation regarding DLC's review of thermal overpressure protection for BVPS-2 containment penetrations.

On July 28,1999, a conference call was conducted between members of the NRC staff and DLC to discuss the additional information provided in your February 2, and June 2,1999, letters. The NRC staff has identified one area where additionalinformation is needed in order i for the staff to complete the review of DLC's response to GL 96-06. The required information is detailed in the enclosed RAl. Although this question is specific to the BVPS-2 response, it is also applicable to BVPS-1. Therefore, please address the question in the context of both BVP. S-1 and BVPS-2.

The NRC requests that you provide your response to the enclosed RAI within 60 days of receipt of this letter. This was discussed with Mr. J. Maracek of your staff, and was established as a mutually agreeable timetable for your response. If circumstances result in the need to revise the target date, please call me at the earliest opportunity.

Should you have any questions regarding this request, please Sincerely, Original signed by:

Daniel S. Collins, Project Manager, Section 1 9910130315 991008 Project Directorate i PDR ADOCK 05000334 Division of Licensing Project Management P PDR Office of Nuclear Reactor Regulation i

Docket Nos. 50-334 and 50-412 l

Enclosure:

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Mr. J. E. Cross Octobe" 8, 1999 l t Pr:sid:nt G:n: ration Group

) Duqu:sna Light Company I 'I i Post Office Box 4 Shippingport, PA 15077 l i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAl) REGARDING THE RESPONSE TO GENERIC LETTER (GL) 96-06, BEAVER VALLEY POWER l STATION, UNIT NOS.1 AND 2 (BVPS-1 AND BVPS-2) (TAC NOS. M96777 AND l

l M96778)

Dear Mr. Cross:

i 1

\

By letter dated January 28,1997, the Duquesne Light Company (DLC) submitted a response to j GL 96-06, " Assurance of Equipment Operability and Containment integrity During Design-Basis Accident Conditions," dated September 30,1996. By letters dated June 30,1998, February 2, and June 2,1999, DLC submitted responses to a Nuclear Regulatory Commission (NRC)

Request for Additional Information (RAl), and supplementalinformation regarding DLC's review  ;

of thermal overpressure protection for BVPS-2 containment penetrations. l l

On July 28,1999, a conference call was conducted between members of the NRC staff and DLC to discuss the additional information provided in your February 2, and June 2,1999, letters. The NRC staff has identified one area where additionalinformation is needed in order for the staff to complete the review of DLC's response to GL 96-06. The required information is detailed in the enclosed RAl. Although this question is specific to the BVPS-2 response, it is also applicable to BVPS-1. Therefore, please address the question in the context of both l BVPS-1 and BVPS-2. l The NRC requests that you provide your response to the enclosed RAI within 60 days of receipt of this letter. This was discussed with Mr. J. Maracek of your staff, and was established as a mutually agreeable timetable for your response, if circumstances result in the need to revise the target date, please call me at the earliest opportunity.

Should you have any questions regarding this request, please Sincerely, Original signed by:

Daniel S. Collins, Project Manager, Section 1 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosure:

RAI cc w/ encl: See next page DISTRIBUTION:

Docket File MO'Brien ACRS PUBLIC DCollins MEvans, RGN 1 PDl-1 r/f OGC SBlack E. Adensam (e-mail)

JTatum GHammer SBajwa DTerao OFFICE PD!-1/PM PDI-2/LA EMEB/SC PDI-1/D m NAME DC IIns:Icc MO'Brien GT-staa .,

SBajwa h I

6M a w.ny N DATE /w / V/99 _/ /99 /c /7 /99 y $ /[/99 OFFICIAL RECORD COPY DOCUMENT NAME: G:\PDl-1\ Beaver 1&2\GL96-06 RAl.wpd

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NUCLEAR REGULATORY COMMISSION

. 't WASHINGTON. D.C. 20555-0001 vetober 8,1999

= Mr. J. E. Cross President-Generation Group Duquesne Light Company

. Post Office Box 4 Shippingport, PA 15077

SUBJECT:

REQUEST FOR ADDIT'ONAL INFORMATION'(RAl) REGARDING THE RESPONSE TO GENERIC LETTER (GL) 96-06, BEAVER VALLEY POWER STATION, UNIT NOS.1 AND 2 (BVPS-1 AND BVPS-2)(TAC NOS. M96777 AND M96778)

Dear Mr. Cross:

By letter dated January 28,1997, the Duquesne Light Company (DLC) submitted a response to GL 96-06, " Assurance of Equipment Operability and Containment integrity During Design-Basis Accident Conditions," dated September 30,1996. By letters dated June 30,1998, February 2, and June 2,1999, DLC submitted responses to a Nuclear Regulatory Commission (NRC)

Request for AdditionalInformation (RAI), and supplementalinformation regarding DLC's review of thermai overpressure protection for BVPS-2 containment penetrations.

On July 28,1999, a conferehce call was conducted between members of the NRC staff and DLC to discuss the additionalinformation provided in your February 2, and June 2,1999, letters. The NRC staff has identified one area where additionalinformation is needed in order for the staff to complete the review of DLC's response to GL 96-06. The required information is detailed in the enclosed RAl. Although this question is specific to the BVPS-2 response, it is also applicable to BVPS-1. Therefore, please address the question in the context of both BVPS-1 and BVPS-2.

The NRC requests that you provide your response to the enclosed RAI within 60 days of receipt of this letter.' This was discussed with Mr. J. Maracek of your staff, arid was establshed as 1 mutually agreeable timetable for your response. If circumstances result in the ne.d to revise the target date, please call me at the earliest opportunity.

Should you have any questions regarding this request, please contact me at (301) 415-1427.

Sincerely, ,

yk ! $~, 00 Daniel S. Collins, Project Manager, Section 1 j Project Directorate I  ;

Division of Licensing Project Management  ;

Office of Nuclear Reactor Flegulation Docket Nos. 50-334 and 50-412

Enclosure:

RAI ,

cc'w/ encl: See next page 3

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.. g Beaver Valley Power Station, Units 1 and 2 Jay E. Silberg, Esquire Duquesne Light Company Shaw, Pittman, Potts & Trowbridge Beaver Valley Power Station 2300 N Street, NW. PO Box 4 Washington, DC 20037 Shippingport, PA 15077 ATTN: Kevin L. Ostrowski, Division Vice Duquesne Light Company President, Nuclear Operations Group Safety and Licensing Department and Plant Manager (BV-SOSB-7)

Mark S. Ackerman, Manager (2 Copies)

Beaver Valley Power Station Bureau of Radiation Protection PO Box 4, BV-A Pennsylvania Department of Shippingport, PA 15077 Environmental Protection ATTN: Michael P. Murphy Commissioner Roy M. Smith Post Office Box 2063 West Virginia Department of Labor Harrisburg, PA 17120 Building 3, Room 319 Capitol Complex Mayor of the Borough of Charleston,WV 25305 Shippingport Post Office Box 3 Director, Utilities Department Shippingport, PA 15077 Public Utilities Commission 180 East Broad Street Regional Administrator, Region I Columbus, OH 43266-0573 U.S. Nuclear Regulatory Commission 475 Allendale Road Director, Pennsylvania Emergency King of Prussia, PA 19406 Management Agency Post Office Box 3321 Resident Inspector Harrisburg, PA 17105-3321 U.S. Nuclear Regulatory Commission Post Office Box 298 Ohio EPA-DERR Shippingport, PA 15077 ATTN: Zack A. Clayton Post Office Box 1049 Duquesne Light Company Columbus, OH 43266-0149 Beaver Valley Power Station PO Box 4  !

Dr. Judith Johnsrud Shippingport, PA 15077 {

National Energy Committee ATTN: S. C. Jain, Senior Vice President j Sierra Club Nuclear Services (BV A) 433 Orlando Avenue State College, PA 16803 Mr. J. A. Hultz, Manager Projects & Support Services Duquesne Light Company First Energy Beaver Valley Power Station 76 South Main Street J. J. Maracek Akron, OH 44308 P. O. Box 4, BV-A Shippingport, PA 160'u

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REQUEST FOR ADDITIONAL INFORMATION (RAI)

REGARDING RESPONSE TO GENERIC LETTER (GL) 96-06 BEAVER VALLEY POWER STATION. UNIT NOS.1 AND 2 DOCKET NOS. 50-334 AND 50-412 The Nuclear Regulatory Commission staff has been reviewing DLC's letter dated June 2,1999, which submitted the executive summary from the Beaver Valley Power Station, Unit No. 2 (BVPS-2), Containment Penetrations Overpressure Protection Analysis. Section 4.4 of the report discusses penetrations associated with the reactor vessellevelinstrumentation system (RVLIS). This discussion notes that, in the event of a loss-of-coolant accident (LOCA), the six penetrations associated with the RVLIS will be protected from overpressurization of the tubing j and hydraulic isolator located outside containment by failure of the high volume sensor bellows. l The staff notes that, while such a bellows failure may protect the penetration from overpressurization, it would likely result in the RVLIS being inopeictie. Please provide detailed information regarding how inoperability of the RVLIS following a design basis LOCA is accounted for in the BVPS-2 licensing basis and emergency operating procedures.

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l 4

Enclosure

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