ML17262A640
| ML17262A640 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/29/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17262A641 | List: |
| References | |
| IEB-88-011, IEB-88-11, NUDOCS 9111070185 | |
| Download: ML17262A640 (6) | |
Text
, ACCELERATED D STRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9111070185 DOC.DATE: 91/10/29 NOTARIZED: YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit -1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. 'ochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R'roject Directorate I-3
/
DOCKET 05000244 R
SUBJECT:
Forwards nonproprietary WCAP-12929
& proprietary WCAP-12928, "Structural Evaluation of RE Ginna Pressurizer Surge Line, Considering Effects of Thermal...,"
as final response to NRC Bulletin 88-011.WCAP-12928 withheld (ref 10CFR2.790).
DISTRIBUTION CODE:
IE30D COPIES RECEIVED:LTR 2 ENCL SIZE: 3 6 L/j TITLE: Bulletin 88-11 Pressurizer Surge Line Thermal S ratification S
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREOY Vice Presidenr Cinna Nuclear Production TELEPHONE AREA CODE 716 546 2700 October 29, 1991 Mr. Allen R. Johnson Project Directorate I-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Response to NRC Bulletin 88-11 Pressurizer Surge Line Thermal Stratification dated December 20, 1988 R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson,
This letter provides RG&E's final response to NRC IE Bulletin 88-11, Pressurizer Surge Line Thermal Stratification, dated December 20, 1988.
This response specifically addresses item 1.d. of the subject bulletin which requires licensees to update the surge line stress and fatigue analysis to ensure compliance with code requirements.
Our previous response detailed the Westinghouse Owner's Group (WOG) generic evaluation of surge line stratification which resulted in a JCO for Ginna for at least ten additional heatup/cooldown cycles prior to final response.
An analysis was prepared by Westinghouse for Ginna station titled "Structural Evaluation of Pressurizer Surge Line, Considering the Affects of Thermal Stratification", WCAP-12928, dated May 1991, to demonstrate compliance to NRC Bulletin 88-11.
The analysis was performed to the requirements of ASME section III, 1986 code edition.
Specific transients and temperature profiles were developed based on Ginna's past operating history and future expected transients which consisted of heatupr
- cooldown, normal and upset conditions.
The resulting transients were used to perform an analysis of the surge line, whereby the existing support configuration was modeled and surge line displacement, stresses and support loadings were determined.
The stresses were used to evaluate fatigue in the surge line with stratification loading.
ASME fatigue usage factors were calculated considering thermal stratification and thermal striping at various locations in the surge line.
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ROCHESTER OAS AND EL RIC CORP.
10/25/91 Mr. Allen R. Johnson SHEET HO.
The results indicate the surge line meets the stress limits and usage factor requirements of the ASME code.
Additionally,
.the pressurizer surge nozzle meets the code stress allowables under thermal stratification loading and fatigue usage requirements of ASME section III.
Ginna's Operating procedures 0-1.1 and 0-2.2 currently have an administrative differential temperature limit between the Pressurizer (PRZR) and Reactor Coolant System (RCS) of 200'F.
Instructions will be added to identify and report if this limit is exceeded so that an engineering evaluation may be performed to ensure that design limits are maintained.
Based upon the'bove discussion, it can be concluded that the pressurizer surge-line meets the requirements of ASME code section III including both stress limits and fatigue usage for the full licensed life of the plant.
This response concludes
'G&E requirements with respect to NRC Bulletin 88-11 compliance.
Enclosed are:
1.
2 copies of WCAP-12928, "Structural Evaluation of the Robert E. Ginna Pressurizer Surge Line, Considering the Effects of Thermal Stratification" (Proprietary).
2.
2 copies of WCAP-12929, "Structural Evaluation of the Robert E. Ginna Pressurizer Surge Line, Considering the Effects of Thermal Stratification" (Non-Proprietary).
Also enclosed are Westinghouse authorization letter, CAW 215, accompanying Affidavit, Proprietary Information Notice, and Copyright Notice.
Item 1 contains information proprietary to Westinghouse Electric Corporation and therefore 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 information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.790 of'he Commission's regulations.
4
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ROCHESTER GAS AND EL R/C CORP.
DATE 10/25/91 Mr. Allen R. Johnson SHEET NO.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-91-215 and should be addressed to R.
P. DiPiazza, Manager of Nuclear Safety Licensing, Westinghouse Electric Corporation, P.O.
Box 355, Pittsburgh, Pennsylvania 15230-0355.
Very ruly yours, Robert C. Mecredy xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, DC 20555 U.S. Nuclear Regulatory Commission Region 1
475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector