ML20216C290

From kanterella
Jump to navigation Jump to search

Refers to from Dl Which Identified Apparent Inconsistency Between NRC SE ( ) for BVPS-1 & BVPS-2 Re Implementation of ATWS Rule.Forwards RAI Re Applicability of W Technical Bulletin ESBU-TB-08
ML20216C290
Person / Time
Site: Beaver Valley
Issue date: 05/07/1998
From: Brinkman D
NRC (Affiliation Not Assigned)
To: Cross J
DUQUESNE LIGHT CO.
References
TAC-MA0715, TAC-MA0716, TAC-MA715, TAC-MA716, NUDOCS 9805190190
Download: ML20216C290 (3)


Text

May 7, 1998

, Mr. J. E. Cross '

Prcsidsnt-Grantrttion Group Duqucins Light Comp 1ny

. Post Office Box 4 Shippingport, PA 15077

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING DUQUESNE LIGHT COMPANY'S (DLC) COMMENTS ON NRC'S SAFETY EVALUATION (SE)

CONCERNING BEAVER VALLEY POWER STATION, UNIT NOS.1 AND 2 (BVPS-1 AND BVPS-2), IMPLEMENTATION OF THE ANTICIPATED TRANSIENT WITHOUT SCRAM (ATSW) RULE (TAC NOS. MA0715 AND MA0716)

Dear Mr. Cross:

By [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|letter dated January 5,1998]], DLC identified an apparent inconsistency between the Nuclear Regulatory Commission (NRC) SE (dated May 31,1988) for BVPS-1 and BVPS-2 concerning implementation of the ATWS rule and the design of the ATWS Mitigating System Actuation Circuitry (AMSAC) subm tted by DLC to meet the criteria of 10 CFR 50.62. The NRC staff has begun its review of DLC's [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|January 5,1998, letter]], but has determined that the following additional information is required for us to complete our review.

1. DLC's [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|January 5,1998, letter]] stated that Westinghouse had recently reconfirmed, in Westinghouse Technical Bulletin ESBU-TB-08, that an in2ial condition of 50% reactor power would be acceptable. Please inform us whether DLC has determined if Westinghouse Technical Bulletin ESBU-TB-08 is applicable to BVPS-1 and BVPS-2 and if it is acceptable.
2. DLC's [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|January 5,1998, letter]] also stated that a review of data from the l'ast startup of BVPS-1 and BVPS-2 indicated a discrepancy of about 3% between reactor power and turbine load at 40% reactor power. Please provide additionalinformation regarding other instances of noted discrepancies between reactor power and turbine load during other startups.

Please provide a response to this RAI within 60 days of receipt of this letter to enable us to complete our review in a timely manner, if you have any questions regarding this RAI, please contact me at (301) 415-1409.

Sincerely,

/s/

Donald S. Brinkman, Senior Project Manager i Project Directorate'l-2 .

Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket Nos. 50-334/50-412 1

cc: See next page f5Qf DISTRIBUTION Docket File DBrinkman MShuaibi PUBLIC MO'Brien MEvans, RGN-l PDI-2 Reading OGC JZwolinski ACRS l RCapra TCollins /

OFFICE PDI-2/PM A // 'PDfMk SRXB/BC , PDI-2/D NAME DBrinkma rb .Mb'B TCollins RCapra F DATE t/ /11/98 98 // /2/f/98 5 / 14 / 9 8 OFFIC'5'L RECORD COPY \~ '

fIf(p6 - ,

waiuCMT NAMF RV0715.RAI -

~

' W-

'~

,_ ,l fO'@ V 9805190190 980507 ~' 't ' '

PDR ADOCK 05000334 P PDR 3

I k2 Kf f;

g "

UNITED STATES E NUCLEAR REGULATORY COMMISSION E WASHINGTON, D.C. 206 shoo 1

% ,,,* May 7, 1998 l Mr. J. E. Cross i President-Generation Group Duquesne Light Company Post Office Box 4 Shippingport, PA 15077

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING DUQUESNE LIGHT COMPANY'S (DLC) COMMENTS ON NRC'S SAFETY EVALUATION (SE)

CONCERNING BEAVER VALLEY POWER STATION, UNIT NOS.1 AND 2 (BVPS-1 AND BVPS-2), IMPLEMENTATION OF THE ANTICIPATED TRANSIENT WITHOUT SCRAM (ATSW) RULE (TAC NOS MA0715 AND MA0716)

Dear Mr. Cross:

By [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|letter dated January 5,1998]], DLC identified an apparent inconsistency between the Nuclear Regulatory Commission (NRC) SE (dated May 31,1988) for BVPS-1 and BVPS-2 conceming

implementation of the ATWS rule and the design of the ATWS Mitigating System Actuation 1 l Circuitry (AMSAC) submitted by DLC to meet the criteria of 10 CFR 50.62. The NRC staff has i

begun its review of DLC's [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|January 5,1998, letter]], but has determined that the following 1 additional information is required for us to complete our review. ,

, 1. DLC's [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|January 5,1998, letter]] stated that Westinghouse had recently reconfirmed, in Westinghouse Technical Bulletin ESBU-TB-08, that an initial condition of 50% reactor power ]

would be acceptable. Please inform us whether DLC has determined if Westinghouse '

Technical Bulletin ESBU-TB-08 is applicable to BVPS-1 and BVPS-2 and if it is acceptable.

2. DLC's [[letter::L-97-065, Discusses Inconsistency Between NRC SER Supplied to Util on Implementation of ATWS Rule & Design of ATWS AMSAC Submitted by Util,Per 10CFR50.62|January 5,1998, letter]] also stated that a review of data from the last startup of BVPS-1 and BVPS-2 indicated a discrepancy of about 3% between reactor power and turbine load at 40% reactor power. Please provide additionalinformation regarding other instances of noted discrepancies between reactor power and turbine load during other startups.

Please provide a response to this RAI within 60 days of receipt of this letter to enable us to complete our review in a timely manner.

If you have any questions regarding this RAI, please contact me at (301) 415-1409.

Sincerely, I. b Donald S. Brinkman, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects -l/ll Office of Nuclear Reactor Regulation Docket Nos. 50-334/50-412 cc: See next page

~ _ _ _

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

l 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 l

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

Duquesne Light Company Mayor of the Borrough of Beaver Valley Power Station Shippingport l PO Box 4 Post Office Box 3 Shippingport, PA 15077 Shippirigport, 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, WVA 25305 Resident Inspector Director, Utilities Department 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 ATTN: S. C. Jain, Vice President Ohio EPA-DERR Nuclear Services (BV-A)

ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 i

Duquesne Ught Company Beaver Valley Power Station PO Box 4 Shippingport, PA 15077 ATTN: R. L. Grand, Divisien Vice President, Nuclear Operations Group l and Plant Manager (BV-SOSB-7)

____