ML20059D039

Concludes Analyses Presented in BAW-2148P & BAW-2192P for Units 1 & 2 Have Adequate Margins of Safety for Load Level a & B Service Conditions Re Response to GL-92-01

ML20059D039
Person / Time
Site:	Point Beach
Issue date:	11/01/1993
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-93-114 GL-92-01, GL-92-1, VPNPD-93-185, NUDOCS 9311020111
Download: ML20059D039 (2)

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Wisconsin

!likkCtHCL POWER COMPANY 231 W McNgon. Po Box 2046. Wmwee. WI 53201-2046 (414)220 2345.

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t VPNPD-93-185 NRC-93-114 November 1, 1993 Document Control Desk U.S.

NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 REACTOR VESSEL LOW UPPER-SHELF TOUGHNESS FRACTURE MECHANICS ANALYSIS LOAD LEVEL A AND B CONDITIONS POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 Nuclear Regulatory Commission (NRC) Generic LetterL(GL) 92-01,

" Reactor Vessel Structural Integrity," dated March 6, 1992, was issued to obtain informativn from licensees to enable the NRC.to assess compliance with regulatory requirements and commitments-regarding reactor vessel integrity.. Our._responseato_GL 92-01 was-1 provided to the NRC-on June 25,_1992.

In~that response,1 Wisconsin Electric Power Company stated-that~an analysis would be conducted _

j by the end of 1993 for the Point Beach Nuclear. Plants.to demonstrate adequate margins of safety with: respect'to the requirements of 10 CFR 50 Appendix:G, "FracturecToughness Requirements."

This submittal discusses;the results of this-analysis for load level A and B conditions.~

For the' level A and B serv 5ce loads,.the B&W Owners Group Reactor.

Vessel Working Group,~under the direction of. Wisconsin Electric and other member utilities, performed a leadLplant fracture ~ mechanics.

evaluation.

The results of this evaluation vere'reportedLin-BAW-2148P,-" Low Upper-Shelf ToughnesstFracture Analysis of React'or

-Vessels of-Zion Units.1:and 2 for-Load LevelEA & B Conditions."-

J This~ report wasLsubmitted to the NRC in September;1992 and

.l concludes that adequate marginsLof safety exist for-Level A'and-B service loads.for Zion Units 1 and 2.

l'l The B&W Ownars Group Re' actor Vessel Working Group ~has subsequently.

H developed report BAW-2192P, " Low Upper-Shelf. Toughness Fracture Mechanics-Analysis of Reactor Vessels of B&W Owners Group Reactorg Vessel. Working Group for Load ~ Level A & B Service Loads."

This report was submitted lto the NRC by the B&W-Owners Group on August j_,

26, 1993.. BAW-2192P documents additional analyses that w5ref performed for each B&W--fabricated PWR-vessel to' determine whether'

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the' vessels are bounded by-the lead plant analyses.

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Document Control Desk November 1, 1993 Page 2 The analyses reported in BAW-2192P considered plant-specific reactor vessel materials, operating conditions, and dimensions.

These analyses demonstrate that each plant is bounded by the lead plant analysis for Zion Units 1 and 2 for level A and B service loads.

As reported in BAW-2192P, BAW-2148P demonstrates the adequacy of the margin of safety for continued. operation of the Point Beach reactor vessels beyond the end of.the existing license.

We conclude, therefore, that based on the analyses presented in BAW-2148P and BAW-2192P, Point Beach Nuclear Plant Units 1 and 2 have adequate margins of safety for load level A and B service conditions.

If you have any questions or require additional information, please contact us.

L Sincerely,

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Bob Link Vice President Nuclear Power cc:

NRC Regional Administrator, Region III NRC Resident Inspector i

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