ML20012D368

Forwards Proprietary & Nonproprietary Suppl 2 to WCAP-12218 & WCAP-12219, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Vogtle Units 1 & 2, Per 900226 Request.Proprietary Rept Withheld (Ref 10CFR2.790)

ML20012D368
Person / Time
Site:	Vogtle
Issue date:	03/19/1990
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19293A285	List: ML20012D368 ML20012D374 ML20012D381
References
ELV-01444, ELV-1444, IEB-88-011, IEB-88-11, NUDOCS 9003270239
Download: ML20012D368 (3)

Text

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, W. G. Hairston, Hi -

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Nuclear Operations ELV-01444: .;

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0298 Docket No.- 50-424

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' ATTN:- Document Control Desk" '/ yl q L Washington,1 D. C. 20555 , 3  ;

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Gentlemen t-L V0GTLE ELECTRIC GENERATING PLANT l PRESSURIZER SURGE LINE THERMAL STRATIFICATION By. letter ELV-01196 dated January 4, 1990, Georgia Power Company (GPC) provided- I copies'of WCAP-12218,-Supplement 1:and WCAP-11219 Supplement 1-to the NRC,~in ,

response to NRC. Bulletin 88-11 for Vogtle Electric Generating Plant '(VEGP)'-Unit. 1

1. :0n February 26,-1990, GPC met with the NRC staff to discuss the pressurizer-1 surge 111ne stratification issue. Enclosed with this letter are:

1. :5 copies of WCAP-12218, Supplement 2 "A Supplementary Assessment of

. Leak-Before-Break for the Pressurizer Surge Lines of Vogtle Units 1 and -i 2", dated March 1990 (Proprietary). .j L 2.15 copies of WCAP-12219 Supplement 2." Supplementary Assessment of Leak-Before-Break for the Pressurizer Surge Lines of Vogtle Units 1 and 1 L 2", dated. March 1990-(Non-Proprietary).

? Also enclosed is'a Westinghouse authorization. letter, CAW-90-017, Proprietary  :

l, Information Notice,.and accompanying Affidavit. -

r b These topical reports provide the presentation overheads used during the meeting  !

with-the NRC staff. The information in these topical reports which is

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proprietary. to Westinghouse has. been properly marked, consistent with the '

commitments in Westinghouse letter NS-NRC-90-3493 dated February 23, 1990.

At' the~ February .26 meeting, the NRC requested additional information regarding

, the' leak-before-break analysis performed for VEGP Unit 1. Specifically requested were a new load case considering different stratification conditions, ,

. and a combination of this and other load cases with safe shutdown earthquake (SSE) l_oadings. This additional information is also applicable to Unit 2 and is 4 included in the subject topical reports. il

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'U. S.-Nuclear Regulatory Commission ELV-01444

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1 l On February 25,.1990, a visual inspection (ASME,Section XI, VT-3) was performed on' the VEGP Unit 1 surge line as required by NRC Bulletin 88-11. The areas-examined. included the pressurizer nozzle safe end area, the surge line to main i loop branch connection, and all associated hangers, snubbers and supports  ;

including whip restraints and piping. Specific attention was given to '

hanger / support anchorages and component connections. The inspection was performed with the insulation in place and the reactor in Mode 5. The inspection showed no evidence of structural damage or distress. There was also no evidence of abnormal . movement or interference of the surge line~ piping.

The VEGP Technical Specifications require shutdown for unidentified RCS leakage l l exceeding 1 gpm. VEGP procedures for unidentified leakage from the RCS during l< operation would result in identification of a postulated surge line crack while L the plant is in Mode 3, when there is minimal delta T on the surge line pipe.

Upon discovery that the source is a nonisolable RCS pressure boundary leak, depressurization of.the RCS would be paramount, and the operators would be expected.to initiate depressurization expeditiously. To provide further l assurance, plant operating procedures have been revised to reinforce the need for timely depressurization, in accordance with the Technical Specifications, in the event of a nonisolable leak in the RCS.

Further, in order to assure that the analytical bases for the qualification of the Units 1 and 2 surge lines remain valid, VEGP procedures for heatup have been revised to reflect-a maximum delta T limit between the pressurizer and the l- reactor coolant loop. Cooldown related procedures will be revised by April 9, l 1990. The delta T limit for heatup is 320 degrees F; the limit for cooldown is 300 degrees F.

Detailed' analyses have been performed to address pressurizer surge line stratification for VEGP Unit 2 and documented in WCAP-12218. Compliance with the requirements of the ASME Code Section III regarding the effects on-pipe stress and fatigue, and with revised General Design Criterion 4 (Appendix A to 10 CFR Part 50) for application of leak-before-break (LBB) has been demonstrated. The applicability of the Unit 2 analyses to VEGP Unit 1, as well

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! as additional plant specific efforts, have been provided in WCAP-12218, Supplements 1 and 2. These submittals indicate that compliance with the ASME Code and with GDC-4 has also been. demonstrated for VEGP Unit 1.

Following the meeting with the NRC on February 26, the NRC staff visited the VEGP site and reviewed information concerning pressurizer surge line thermal stratification. There were no unresolved questions as a result of this meeting.

l l As Supplement 2 to WCAP-12218 contains information proprietary to Westinghouse

[ Electric Corporation, it is supported by an affidavit signed by Westinghouse, j the owner of the information. The affidavit sets forth the basis on which the 1 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. )

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

< Correspondence with respect to the proprietary aspects of the Application for.

- Withholding or the supporting Westinghouse Affidavit should' reference CAW-90-017 and should be addressed to R.A. Wiesemann, Manager of Regulatory & Legislative Affairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania- 15230-0355. l 1

In summary, based on-the efforts discussed above and documented in-WCAP-12218, including Supplements 1 and 2, it is' considered that all aspects of NRC Bulletin 88-11 have been satisfactorily addressed for VEGP Units 1 and 2.  !

Mr. W. G. Hairston, III states that he is a Senior Vice President of Georgia Power. Company and is authorized to execute this oath on behalf of Georgia Power Company and that, to the best of his knowledge and belief, the facts set forth i in this letter and enclosures are true.

GEORGIA POWER COMPANY j By: lA] A lbu l

W. G. Hairston, III i 1

Sworn to and subscribed before me this /S_%ayof YIMI , 1990'.

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Enclosure:

xc: Georoia Power Company Mr. C. K. McCoy I Mr. G. Bockhold, Jr.

Mr. R. M. Odom Mr. P. D. Rushton I

NORMS U. S. Nuclear Reaulatory Commissio_n  ;

Mr. S. D. Ebneter, Regional Administrator

! Mr. T. A. Reed, Licensing Project Manager, NRR Mr. R. F. Aiello, Senior Resident Inspector, Vogtle i

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