ML20196E157

Forwards Proprietary Addendum 2 to Rev 1 to WCAP-10924-P & Nonproprietary WCAP-12071, Westinghouse Large-Break LOCA Best Estimate Methodology, in Support of 880826 Request for Tech Spec Change.Proprietary Rept Withheld (Ref 10CFR2.790)

ML20196E157
Person / Time
Site:	Point Beach
Issue date:	11/30/1988
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML19295G789	List: ML20196E157 ML20196E162 ML20196E175
References
CON-NRC-88-119 VPNPD-88-581, NUDOCS 8812090281
Download: ML20196E157 (3)

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. l h Wisconsin Electnc n.e covmr 231 W V!CWGAN.P o BOX 2046.V1.WAUKEE.WI 53201 (414)22t 2345 VPNPD-88-581 NRC-88-119 November 30, 1988 U.S. NUCLEAR REGULATORY COMMISSION Document Control DesV Mail Station Pl-137 Washington, D.C. 20555 Gentlement b DOCKETS 50-266 AND 50-301 LARGE-BREAK LOSS OF COOLANT ACCIDENT ANALYSIS FOR, TECHNICAL SPECIFICATION CHANGE REQUEST 127 INCREASED ALLOWABLE CORE POWER PEAKING FACTORS POINT BEACH NUCLEAR PLANT;_ UNITS 1 AND 2 j Enclosed are five copies of WCAP-10924-P, Volume 2, Revision 1, Addendula 2 (Proprietary) entitled "Westinghouse Large-Break LCCA Best-Estimate Methodology Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection Addendum 2: PBNP Plant Specific Analysis"; five copies of WCAP-12071 (Non-Proprietary);

and five copies of "Technical Basis for Exemption to Selected Appendix K Requirements." These three enclosures complete the submittal of the large-break LOCA analysis mentioned in Technical Specification Change Request 127 as submitted to the NRC in our letter dated August 26, 1988. This submittal also fulfills Wisconsin Electric's commitments regarding 10 CFR 50.46 and Appendix K as provided in our letter to the NRC dated April 19, 1985.

Addendum 2 to WCAP-10924-P describes the methodology used to perform a large-break LOCA analysis of the PBNP two-loop PWRs equipped with upper plenum injection. The methodology follows the approach outlined in SECY-83-472, "Emergency Core Cooling System Analysis Methoda," dated November 1983. SECY-83-472 requires that the licensee employ best-estimate models to cal-culate the peak cladding temperature (PCT) at nominal conditions, at more conservative 95% probability conditions, and with the required features of Appendix K to 10 CFR Part 50. The results of such calculations performed specifically for PBNP are described in the enclosed Addendum 2. Addendum 2, along with the referenced portions of licensing topical report WCAP-10924-P, satisfies al requirements of the SECY-83-472 approach, b3g t 3 Cd ANGE: 'TA GuL I ss12050281 ADOCg881130 05000266 dD4 Apit

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Document Control Desk November 30, 1988 Page 2 The NRC has accepted the licensing topical report, WCAP-10924-P,  :

for referencing by licensing applications under SECY-83-472 in a letter from A. C. Thadani to W. J. Johnson of Westinghouse, dated I August 29, 1988. However, acceptance is subject to three conditions.

First, an exemption to Appendix K requirements I.D.3 and I.D.5, regarding core exit liquid carryover fraction and refill /reflood  ;

heat transfer, must be granted. WE requests an exemption to i these two Appendix K requirements on the basis of 10 CFR Part l 50.12, paragraph (2)(11) which states: }

Application of the regulation in the particular j circumstances would not serve the underlying purpose j of the rule or is not necessary to achieve the under- l lying purpose of the rule. l l

The NRC safety evaluation of WCAP-10924-P states that the intent i of these two Appendix K requirements is satisfied. An exemption  !

is necessary only to satisfy the letter of the requirement. The technical basis for the exemption is given in an enclosure to this .

letter entitled "Technical Basis For Exemption To Selected Appendix K [

Requirements." l f

The second condition of the NRC's acceptance of WCAP-10924-P t is that sensitivity studies be performed to determine the location l of the hot assembly to obtain the highest PCT. Sensitivity h studies done to determine the location of the hot assembly are described in the enclosed Addendum 2 to WCAP-10924-P, Volume 2. In addition, the Addendum describes sensitivity studies performed specifically for the PBNP analysis and explains why sensitivity studies done using a lead two-loop plant are applicable to the PBNP analysis.

NRC review and approval of changes in the decay heat calculation is the third condition for the NRC's acceptance of WCAP-10924-P.

No changes have been made to the model since the NRC's last review.

Therefore, no additional review or approval is required.

As WCAP-10924-P contains infstmation proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. A copy of the affidavit ir enclosed. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in Para-graph (b)(4) of Section 2.790 of the Commission's regulations.

Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.790 of the Commission's regulations. The non-proprietary version, WCAP-12071, is enclosed.

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Document Control Desk November 30, 1988 Page 3 Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse affidavit should reference the affidavit and should be addressed to R. A. Wiesemann, Manager of Regulatory and Legislative Affairs, Westinghouse Electric Corporation, Post Office Box 355, Pittsburgh, Pennsylvania 15230-0355.

WE believes this submittal satisfies all requirements of ECCS analysis of Point Beach Nuclear Plant, Units 1 and 2, using the SECY-83-472 approach, and also eatisfies the conditions established by the NRC for referen'*ng the licensing topical report WCAP-10924-P.

Please contact us if you have any questions concerning tht large-break LOCA analysis.

Very truly yours, f

b, 6iv Jq C. W. Fay Vice President Nuclear Power Copies to NRC Regional Administrator, Region III NRC Resident. Inspector R. S. Cullen, PSCW W. Swenson, NRC Project Manager for PBNP (3)

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