ML20134J512

Forwards RAI Re Plant 960930 Request 192 for Change to TS 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & CS, TS 15.3.7, Acs,Air Recirculation Fan Coolers,Cs & TS 15.5.2, Containment, for Plant Units 1 & 2

ML20134J512
Person / Time
Site:	Point Beach
Issue date:	11/13/1996
From:	Gundrum L NRC (Affiliation Not Assigned)
To:	Link R WISCONSIN ELECTRIC POWER CO.
References
TAC-M96741, TAC-M96742, NUDOCS 9611150246
Download: ML20134J512 (4)

Text

.

November 13, 1996 Distribution i Docket file WLong PUBLIC JHannon Mr. Robert E. Link, Vice President PD3-1 Reading ACRS  !

Nuclear Power Department JRoe JCaldwell, RIII l Wisconsin Electric Power Company OGC EAdensam (E)

'231 West Michigan Street, Room P379 JMcCormick-Barger, RIII Milwaukee, WI 53201

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION CHANGE REQUEST 192 - POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 l (TAC NOS. M96741 and M96742) i

Dear Mr. Link:

On September 30, 1996, Change Request,192 was submitted. This change requests changes to Technical Specification (TS) 15.3.3, " Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coclers, and  ;

Containment Spray," TS 15.3.7, " Auxiliary Cooling Systems, Air Recir:ulation l 1'

Fan Coolers, and Containment Spray," and TS 15.5.2, " Containment." As discussed with your staff on November 8, 1996,'the staff determined that additional information is required. Please. respond to' the enclosed request for additional information (RAI)' by November 26, 1996. If you have any l questions, please contact me at (301) 415-1380.

Sincerely, 1 M e Linda-L. Gundrum,. Project Manager Project Di~ectorate r 111-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosure:

RAI DFO \[\

cc w/ encl: See next page DOCUMENT NAME: G:\WPDOCS\PTBEACH\PTB96741.RAI To receive a copy of this document, Indicate in the boz: "C" = Copy without enclosuras *E" = Copy with enclosures "N" = No copy 0FFICE PD31:PM lE PD31:LA glE PD31:PD I) l t NAME LGundrum (M CJamerson (Ij/ JHannon 5 (

DATE 11/t1/96 11/ r2./96 // 11/p/96 0FFICIAL RECORD COPY 1liOOG7 ~

9611150246 961113 PDR ADOCK 05000266 h h ,

F PDR

1. Mroq p *a UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 3086Mo01 o% ***/ Novenber 13, 1996 Mr. Robert E. Link, Vice President Nuclear Power Department Wisconsin Electric Power Company  ;

231 West Michigan Street, Room P379 j Milwaukee, WI 53201 l

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION CHANGE REQUEST 102 - POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M96741 and M96742)

Dear Mr. Link:

On September 30, 1996, Change Request 192 was submitted. This change requests changes to Technical Specification (TS) 15.3.3, " Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray," TS 15.3.7, " Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray," and TS 15.5.2, " Containment." As I discussed with your staff on November 8, 1996, the staff determined that additional information is required. Please respond to the enclosed request for additional information (RAI) by November 26, 1996. If you have any questions, please contact me at (301) 415-1380. i Sincerely, Linda L. Gundrum, Project Manager Project Directorate 111-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosure:

RAI cc w/ encl: See next page

Mr. Robert E. Link, Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company Unit Nos. I and 2 cc:

Ernest L. Blake, Jr.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Mr. Scott A. Patulski, General Manager Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road  !

Two Rivers, Wisconsin 54241 j Mr. Ken Duveneck  !

Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Namew lM6

e 4

REQUEST FOR ADDITIONAL INFORMATION ON CHANGE REQUEST 192 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 The following questions relate to Attachment 3 of Wisconsin Electric Power Company's September 30, 1996, application to amend Technical Specification (TS) 15.3.3, " Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray," TS 15.3.7, " Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray," and TS

. 15.5.2, " Containment."

1. Attachment 3 indicates that Westinghouse performed a new post-LOCA containment pressure and temperature analysis in 1996. Do the mass and energy boundary conditions and the containment response model for the 1996 4 analysis reflect any and all post-Operating License plant modifications that might affect the containment pressure and temperature response to a loss-of-coolant accident? Will the 1996 analysis be incorporated into the i

Final Safety Analysis Report as the new analysis of record?

2. Have secondary system breaks reflecting Bulletin 80-04, " Analysis of a ,

i Pressurized Water Reactor Main Steam Line Break with Containment Feedwater l 9

Addition," 10 CFR 50.49 limitations, and any applicable plant ,

modifications been considered in the new analyses?  !

l l

3. In switching to use of American Nuclear Society Standard 5.1-1979 decay '

heat, has a two-sigma uncertainty margin been added? l l

4. Explain how the 25 percent air cooler capacity reduction is implemented in the containment response model (e.g., reduction in overall heat transfer '

coefficient: reduction in water flow?). Explain why the method properly l reflects the new service water system conditions. I

, 5. One of the changes described in Attachment 3 is the use of a value of 33 F for " injection water cooling by the residual heat removal (RHR) heat

exchanger." Please clarify the use of the 33*F value. (Does the containment model not continuously compute the injection water conditions

, using a simplified primary system model?)

6. Please explain reliance on the RHR and component cooling water (CCW) systems for containment heat removal (when are the systems placed in service as assumed in the analysis.) Please describe the CCW system's ability to withstand a single failure based on current TS.

1 ENCLOSURE l

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