ML20085K659

Forwards Rev 3 to W Rept WCAP-14047 & Rev 3 to Proprietary Rept WCAP-14046.WCAP-14046 Withheld (Ref 10CFR2.790)

ML20085K659
Person / Time
Site:	Braidwood
Issue date:	06/19/1995
From:	Pontious H COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19330G071	List: ML20085K659 ML20085K696 ML20085K710
References
NUDOCS 9506280066
Download: ML20085K659 (3)

Text

Gimmonwealth Edix)n Gampany f ICX) Opus Place 4 Downers Grove. IL 60515 0

I, i

g P June 19,1995 United States Nuclear Regulatory Commission ,

Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

WCAP-14046, "Braidwood Unit 1 Technical Support for Cycle 5 Steam Generator Interim Plugging Criteria," Revision 3 (Proprietary)

Byron Nuclear Power Station, Unit 1 ,

Facility Operating License NPF-37 NRC Docket No. 50f14 Braidwood Nu_ . ower Station, Unit 1 Facility Operating License NPF-72

, NRC Docket No. 50-456

References:

1. George F. Dick, Jr. (NRC) letter to D. L. Farrar (Comed),

Issuance of Amendments (TAC Nos. M90052 and M90053),

dated October 24,1994

2. Denise M. Saccomando (Comed) letter to NRC Document Control Desk, Schedule for LOCA+SSE Steam Generator Load Evaluation for Byron Station Unit I and Braidwood Station Unit 1, dated November 23,1994

3. Harold D. Pontious, Jr. (Comed) letter to NRC Document Control Desk, Evaluation of LOCA + SSE Load Effects on Steam Generator Tubes, dated February 15,1995 e Gentlemen:

In Reference (1), the United States Nuclear Regulatory Commission (NRC) granted g

approval for the application of a voltage-based Tube Support Plate (TSP) Interim j Plugging Criteria (IPC) to disposition steam generator (SG) tubes for continued service i

L:ntatyrbwd:simgens:w14046r3:1 2G0033 t

)ggg j INf 9506280066 950619 i

/)

PDR ADOCK 05000456 g (f a[ A P PDR I

A Unicom Company L

( - -

t

(

i USNRC Document Control Desk June 19,1995

' that are experienang outside diameter stress corrosion cracking (ODSCC) confined within the thickness of the TSPs for Byron Unit 1, Cycle 7. Reference (1) also  !

contained a requirement for the Commonwealth Edison Company (Comed) to submit - l a schedule for evaluating the effects of the loads from a postulated loss-of-coolant l i

accident (LOCA) in combination with a postulated safe shutdown earthquake (SSE) on certain tubes in the vicinity of the TSP wedges that react with the tube bundle load in t the Byron Unit 1 SGs. In Reference (2), Comed committed to provide tha* iluation i to the NRC by February 17,1995. Comed also stated that due to the similanties between Byron Unit I and Braidwood Unit 1, the evaluation would also be applicable ,

to Braidwood Unit 1. Reference (3) transmitted the results of that evaluation. i In Reference (3), the evaluation of the effects of combined LOCA + SSE loads on certain tubes in the vicinity of the TSP wedges that react with the tube bundle load in the Byron Unit I and Braidwood Unit 1 SGs was contained in WCAP-14046, "Braidwood Unit 1 Technical Support for Cycle 5 Steam Generator Interim Plugging Criteria," Revision 2 (Proprietary). WCAP-14046, Revision 2 modified only Section 4.7 of WCAP-14046, Revision 1. Since no other sections of WCAP-14046, Revision I were modified as a result of this evaluation, they were not included in l WCAP-14046, Revision 2.

[

t WCAP-14046, "Braidwood Unit 1 Technical Support for Cycle 5 Steam Generator i Interim Plugging Criteria," Revision 3 (Proprietary) was prepared to compile all information previously provided in WCAP-14046, Revisions 1 and 2 into one document. No new technical information is being provided. This effort was undertaken to ease in the retrievability of information previously provided.

Accordingly, please find enclosed one copy each of Westinghouse authorization letter, CAW-95-807, accompanying affidavit, Proprietary Information Notice, Copyright l Notice, WCAP-14046, "Braidwood Unit 1 Technical Support for Cycle 5 Steam Generator Interim Plugging Criteria," Revision 3 (Pmprietary), and WCAP-14047, "Braidwood Unit 1 Technical Support for Cycle 5 Steam Generator Interim Plugging Criteria," Revision 3 (Non-Proprietary). .

As WCAP-14046, Revision 3 containr information proprietary to Westinghouse ,

Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. 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 Paragraph (b)(4) of Section 2.790 of the Commission's regulations. Accordingly, it is respectfully requested that the informa; ion which is proprietary to Westinghouse be withheld from public disclosure  !

in accordance with 10 CFR 2.790 of the Commission's regulations.  ;

i f

I

?

r- ,

i USNRC Document Control Desk June 19,1995 Correspondence with respect to the proprieta y aspects of the items listed above or the supporting Westinghouse Affidavit should mference CAW-95-807 and should be addressed to N. J. Liparulo, Manager of Nuclear Safety & Regulatory Activities, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

Please address any comments or questions regarding this matter to this office.

Very truly yours,

/

(

Harold D. Pontious Jr.

Nuclear Licensiiig' Administrator Enclosure 1: Westinghouse Letter CAW-95-807 Enclosure 2: WCAP-14046, Revision 3 (Proprietary)

Enclosure 3: WCAP-14047, Revision 3 (~Non-Proprietary) cc: J. B. Martin, Regional Administrator - RIII M. D. Lynch, Senior Project Manager - NRR R. R. Assa, Braidwood Project Manager - NRR G. F. Dick Jr., Byron Project Manager - NRR S. G. DuPont, Senior Resident Inspector - Braidwood H. Peterson, Senior Resident Inspector - Byron Office of Nuclear Facility Safety - IDNS