ML20064F939

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Submits Results of Evaluation of Core Damage Frequency Based on Util Individual Plant Exam Methodology & Current Operation & Maint of Edgs,In Response to NRC 940307 Telcon Request
ML20064F939
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/08/1994
From: Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-94-018, CON-NRC-94-18 VPNPD-94-025, VPNPD-94-25, NUDOCS 9403150502
Download: ML20064F939 (2)


Text

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' Wisconsin dBectnc POVER COMPANY

' 231 w Mqtyn Po Bm 2046.hohoew 5320b2046 (414J 2202345 '

-VPNPD-94-025 NRC-94-018 March 8, 1994 Document Control Desk U.S.

NUCLEAR REGULATORY COMMISSION

' Mail Station P1-137 Washington, DC-20555

. Gentlemen:

DOCKETS 50-266 AND 50-301 EMERGENCY DIESEL GENERATOR MAINTENANCE OUTAGES

,Q_OE3 DAMAGE FREOUENCY EVALUATION O

POINT BEACH NUCLEAR PLANT,' UNITS 1 AND 2 On March 7, 1994, in a telephone conversation between Mr. Allen Hansen of.the NRC and Mr, Stan Guokas of Wisconsin' Electric (WE),

the NRC requested that:WE provide justification for our. practice-of performing emergency diesel generator maintenance.while both

-Point' Beach Nuclear Plant Units 1 and'2 are at' power.- The analysis' described below was performcd in response to this request.

We have completed the ovaluation of core damage frequency based on our Individual Pin-Examination.(IPE) methodology and'the current operation ar tenance of our'emergencyidiesel generators.

We~have d two cases..' The first case provides a baseline (or avera lamage! frequency,using-the average annual unavailabilit.

testing and; maintenance for all-systcms and componentu aing both1 emergency' diesels, G01 and G02, and our gas turnine, G05).'

The second. case provides a core damage frequency for the specific configuration of G01 not available due to testing and maintenance and all'other systems and components available (i.e., not out-of-service for testing and maintenance).

The analysis for the first case provides a core damage frequency of 9.70E-5 per year assuming the.following:

G01 reliability

= 95%

G02 reliability

= 97%

G05 reliability / =-87%

(10% unreliability-+

availability.

.3% onavailability)

-Notet-These; reliability numbers. represent the worst case ~results for either the-last 20,.50, or 100 starts of.the particular generator.

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tw-Documenf Control Desk March 8, 1994 Page 2 The second analysis with G01 alone out-of-service for testing and maintenance provides a core damage frequency of 2.43E-4 per year, assuming the same reliability numbers for G02 and GOS as used in the base case.

As you requested, we have calculated the differential core damage frequency.

We compared the first and second cases and assumed a 305-day year for power operation, and arrived at a value of 4.8E-7 per day.

If you have any questions regarding our calculations, please contact Mr. Stan Guokas at (414)221-3973.

Sincerely, PN c'~j f.j. y,/

f n

g-o Bob Link Vice President Nuclear Power SEG/jg cc:

NRC Resident Inspector NRC Regional Administrator, Region III

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