ML20212D577

Discusses Review of Response to GL 88-20,suppl 4,requesting All Licensees to Perform Ipeee.Ser,Ter & Supplemental TER Encl

ML20212D577
Person / Time
Site:	Point Beach
Issue date:	09/15/1999
From:	Wetzel B NRC (Affiliation Not Assigned)
To:	Sellman M WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20212D580	List: ML20212D577 ML20212D596 ML20212D641 ML20212D678
References
RTR-NUREG-1407 GL-88-20, TAC-M83661, TAC-M83662, NUDOCS 9909240015
Download: ML20212D577 (4)

Text

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g i UNITED STATES g

o j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30eeMm01 September 15, 1999 Mr. Michael B. Sellman Senior Vice President and Chief Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee,WI 53201

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - REVIEW OF INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE) SUBMITTAL (TAC NOS. M83661 AND M83662)

Dear Mr. Sellman:

On June 30,1995, Wisconsin Electric Power Company (the licensee) submitted its response to Generic Letter (GL) 88-20, Supplement 4, which requested all licensees to perform individual plant examinations of external events (IPEEE) (1) to identify plant-specific vulnerabilities to severe accidents, and (2) to report the results to the Nuclear Regulatory Commission (NRC),

together with any licensee-determined improvements and corrective actions. The NRC staff's review findings on the Point Beach Nuclear Plant, Units 1 and 2, IPEEE submittal are summarized in the enclosed Staff Evaluation Report (SER). Attached to the SER is a Technical Evaluation Report (TER) and its supplement prepared by the NRC's contractor. Energy Research Inc. (ERI).

The NRC staff performed a " Step 1" review, which examined the IPEEE submittal and the licensee's response to a staff request for additional information (RAl). This review focused on the completeness and " reasonableness" of the IPEEE considering the design and operation of Point Beach. On the basis of this review and further review by a senior review board (SRB), the NRC staff concluded that the aspects of high winds, floods, transportation, and other external

- events were adequately addressed. The SRB consisted of NRC staff from the Office of Nuclear Regulatory Research (RES) and the Office of Nuclear Reactor Regulation (NRR), and RES consultants (Sandia National Laboratories), with probabilistic risk assessment expertise for external events. The seismic and fire IPEEE needed a supplemental review because of

. specific concerns related to the seismic analyses (e.g., seismic capacity estimates, resolution of reported anomalies and outliers, and relay chatter issue) and fire analyses (e.g., potential for loss of offsite power due to fire, modeling of oil-filled transformers in the cable spreading room, f

and the analysis of hot shorts). For a detailed discussion of these concerns, see Section 3 of the TER (Attachment 1 to the SER).

/

, in March 1998, the NRC staff sent a supplemental request for additionalinformation to the licensee that focused on the seismic and fire concerns identified during the Step 1 review. The licensee submitted its response to this RAI in July 1998 and a followup response in /Ok f

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December 1998.. Based on the review of the licensee's response to this RAl, ERI comp!eted the supplement to its TER in March 1999.

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M.B. Sellman The licensee estimated a seismic core damage frequency (CDF) of 1.4E 5/ reactor year (RY) using the 1989 seismic hazard curves developed by the Electric Power Research institute

. (EPRI), and a CDF of 1.3 E-5/RY using the 1993 seismic hazard curves developed by Lawrence Livermore National Laboratory. The licensee also estimated the plant seismic capacity, in terms of high confidence of low probability of failure (HCLPF) value, as 0.16g PGA with operator actions and random (nonseismic) failures included, or 0.25g PGA with these actions and failures excluded.

The licensee estimated a fire CDF of about 5.1E-5/RY in its IPEEE submittal. The licensee also estimated that the CDF due to intamal events is about 1.2E-4/RY, including internal flooding.

For other extemal events, the licensee used the progressive screening approach as described in NUREG 1407 to evaluate high winds, floods, transportation, and nearby facility accidents.

The licensee reviewed and updated the results of a Point Beach probabilistic risk assessment (PRA) pedormed for Unresolved Safety issue (USI) A-45, " Shutdown Decay Heat Removal Requirements" (NRC Task Action Plan A-45), based on screening, bounding, and some

probabilistic calculations. The licensee analyzed tornadoes and external floods further using quantitative bounding and PRA evaluations. Historical data were used for determining straight wind, tomado, and extemal flood frequencies. Some site specific data were used for the analyses of aircraft crashes, land transportation accidents, and nearby facility events. No -

formal PRA or bounding analysis was performed for transportation and nearby facility accidents. These events were screened out due to their low frequency of occurrence.

The licensee's definition of vulnerability associated with external events is the same as that used in their IPE. The licensee's criteria for determining if any plant vulnerability exists are (1) a CDF goal of less than 1 E-4/RY and (2) a goal for frequency of large fission product release of less than 1E-6/RY. Although the IPEEE did not identify any vulnerabilities associated with external events at Point Beach, the licensee has implemented certain plant modifications and proposed to take certain actions. These licensee-identified improvements and proposed actions' are to: (1) modify the diesel gent rator stacks (high wind-related), (2) modify control logic for motor-driven AFW pumps and change fire mitigating procedure (fire-related), and j

, (3) upgrade certain anchorages for equipment and tanks, modify certain cable tray supports, and reevaluate and replace certain relays (seismic-related).  ;

The licensee has addressed the following generic safety issues (GSis): GSI 57," Effects of Fire Protection System Actuation on Safety Related Equipment," GSI 103," Design for Probable Maximum Precipitation (PMP)," and GSI-131, " Potential Seismic interaction involving the -

4 Movable in-Core Flux Mapping System Used in Westinghouse Plants." The licensee also addressed USl A-45, " Shutdown Decay Heat Removal Requirements," and the Fire Risk Scoping Study (FRSS) issues that were explicitly requested in Supplement 4 to GL 88-20 and its associated guidance in NUREG 1407.

' On the basis of the Step 1 and supplemental RAI reviews, the NRC staff concludes that the licensee's IPEEE process is capable of identifying the most likely severe accidents and severe accident vulnere.bilities and, therefore, that the Point Beach IPEEE has met the intent of  ;

Generic Letter 88-20, Supplement 4. 1 i

j

I M.B. Sellman September 15, 1999 In addition, the licensee's IPEEE submittal contains some specific information that addresses the external event aspects of GSI-147, " Fire-induced Alternate Shutdown / Control Room Panel Interactions," GSI-148, " Smoke Control and Manual Fire-Fighting Effectiveness," GSI-156,

" Systematic Evaluation Program (SEP)." and GSI-172, " Multiple System Responses Program."

The specific information associated with each issue is identified and discussed in the enclosed SER. Based on the review of the information contained in the submittal, the NRC staff considered that the licensee's process is capable of identifying potential vulnerabilities associated with these issues. On the basis that no vulnerabilities associated the external event aspects of these issues were identified at Point Beach, the NRC staff considers these issues resolved for this plant site.

This completes the NRC staff's efforts in regard to TAC Nos. M83661 and M83662. The NRC staff appreciates your efforts in regard to this matter. If you have any questions concerning the staff's review of your IPEEE submittal, please contact me at (301) 415-1355.

Sincerely, Original signed by:

Beth A. Wetzel, Senior Project Manager, Section 1 Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation

Enclosure:

Staff Evaluation Report cc w/ encl: See next page DISTRIBUTION Docket File PD31 Reading ,

PUBLIC OGC ACRS GCook RHernan SBlack JChen, RES CWoods, RES DCoe RLanksbury, Rill DOCUMENT NAME: g:\pdili-1\ptbeach\ltr83661 To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PD31 E LA:PD31 , lE SC:PDQ1, o E NAME BWetzel 8//d RBouling h% CCraidf6A(

9//f/99 DATE I ~

9 /(T99  %/D99-OFFICIAL RECORD COPY

M.B. Sellman September 15, 1999 In addition, the licensee's IPEEE submittal contains some specific information that addresses the external event aspects of GSI-147," Fire-induced Alternate Shutdown / Control Room Panel Interactions," GSI-148," Smoke Control and Manual Fire-Fighting Effectiveness," GSI-156,

" Systematic Evaluation Program (SEP)," and GSI-172, " Multiple System Responses Program."

The specific information associated with each issue is identified and discussed in the enclosed SER. Based on the review of the information contained in the submittal, the NRC staff considered that the licensee's process is capable of identifying potential vulnerabilities associated with these issues. On the basis that no vulnerabilities associated the external event aspects of these issues were identified at Point Beach, the NRC staff considers these issues resolved for this plant site.

This completes the NRC staff's efforts in regard to TAC Nos. M83661 and M83662. The NRC staff appreciates your efforts in regard to this matter. If you have any questions concerning the staff's review of your IPEEE submittal, please contact me at (301) 415-1355.

Sincerely, Original signed by:

Beth A. Wetzel, Senior Project Manager, Section 1 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation

Enclosure:

Staff Evaluation Report i cc w/ encl: See next page DISTRIBUTION Docket File PD31 Reading PUBLIC OGC ACRS GCook RHernan SBlack JChen, RES CWoods, RES l DCoe RLanksbury, Rlll I

DOCUMENT NAME: g:\pdiji-1\ptbeach\ltr83661 To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N' = No copy OFFICE PM:PD31 lE LA:PD31_ , lE SC:PDa1 , lE NAME BWetzel -f91) RBouling h%'

CCraid 1 V

'3 i/GJ99 DATE 9 //f/99 9 /l'i/99 OFFICIAL RECORD COPY

r e e

! M.B. Sellman t Iri audition, the licensee's IPEEE submittal contains some specific information that addresses j

- the external event aspects of GSI-147," Fire-Induced Alternate Shutdown / Control Room Panel '

Interactions," GSI-148, " Smoke Control and Manual Fire Fighting Effectiveness," GSI 156,

" Systematic Evaluation Program (SEP)," and GSI-172, " Multiple System Responses Program."

The specific information associated with each issue is identified and discussed in the enclosed SER. Based on the review of the information contained in the submittal, the NRC staff considered that the licensee's process is capable of identifying potential vulnerabilities associated with these issues. On the basis that no vulnerabilities associated the external event aspects of these issues were identified at Point Beach, the NRC staff considers these issues resolved for this plant site.

This completes the NRC staff's efforts in regard to TAC Nos. M83661 and M83662. The NRC staff appreciates your efforts in regard to this matter, if you have any questions concerning the staff's review of your IPEEE submittal, please contact me at (301) 415-1355.

Sincerely, i 0$

Beth A. Wetzel, Senior Project Manager, Section 1 Project Directorate til Division of Licensing Project Management Office of Nuclear Reactor Regulation

Enclosure:

Staff Evaluation Report cc w/enci: See next page i

)

I I

, Wisconsin Electric Power Company

Point Beach Nuclear Plant cc: Units 1 and 2 Mr. John H. O'Ne'ill, Jr, Shaw, Pittman, Potts & Trowbridge Ms. Sarah Jenkins 2300 N Street, NW Electric Division Washington, DC 20037-1128 Public Service Commission of Wisconsin P.O. Box 7854 Mr. Richard R. Gri0g Madison, Wisconsin 53707-7854 President and Chief Operating Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 53201 Mr. Mark E. Reddemann Site Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 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 lil U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office '

U.S. Nuclear Regulatary Commission 6612 Nuclear Road ,

Two Rivers, Wisconsin 54241 October 1998