ML18022A821

Discusses Review of WOG Rept WCAP-12639 on NRC Bulletin 88-011 Re Generic Detailed Analysis of Pressurizer Surge Line Stratification.Concludes That Methodology Used to Analyze & Evaluate Stress Fatigue Effects,Acceptable

ML18022A821
Person / Time
Site:	Harris
Issue date:	08/19/1991
From:	Mozafari B Office of Nuclear Reactor Regulation
To:	Eury L CAROLINA POWER & LIGHT CO.
References
IEB-88-011, IEB-88-11, TAC-72137, NUDOCS 9108280065
Download: ML18022A821 (6)

Text

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50-400 RE-IS August 20, 1991 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 19, 1991 Mr. Lynn W. Eury Executive Vice President Power Supply Carolina Power 5 Light Company Post Office Box 1551 Raleigh, North Carolina 27602

SUBJECT:

PRESSURIZER SURGE LINE THERMAL STRATIFICATION, BULLETIN 88-11, SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 (TAC NO. 72137)

The NRC staff and its consultant, Brookhaven National Laboratory, have completed their review of the Westinghouse Owners Group (WOG) report (WCAP-12639) on generic detailed analysis of pressurizer surge line stratification.

The staff concluded that the methodology-used to analyze and evaluate the stIess fatigue effects due to thermal stratification and thermal striping was acceptable.

However, for the 43 plants included in the WOG generic analysis, only 15 plants demonstrated acceptable stress'fatigue in the surge line.

Although the results of the WOG generic analysis cannot be used to satisfy Actions 1.c and 1.d of Bulletin 88-11 for your facility, a copy of our review of WCAP-12639 that was sent to the WOG is being provided for your information and use.

The Safety Evaluation provides some guidance for the 28 Westinghouse plants that could not be shown acceptable by the WOG generic analysis.

By letter dated April 30, 1991, you submitted a plant specific analysis for Shearon Harris Nuclear Power Plant, Unit 1 (Harris)., Your analysis for Hay.ris demonstrated conformance to the requirements of the American Society of Mechanical Engineers (ASME) Code,Section III, including both stress limits and fatigue usage for the licensed life of the plant.

Your analysis also demonstrated that two of the surge line rigid supports may experience loads in excess of the code allowable values when the effects of thermal stratification and striping are taken into account concurrently with other design loadings.

We understand that you are investigating possible modification of the design of these supports and, if modifications are necessary, the modifications will be completed in the next refueling outage which is scheduled to begin in September 1992.

Your

August 19, 1991 justification for continued operation dated December 29, 1989, is acceptable to justify operation pending implementation of any needed modifications of the supports.

Please inform us when the modifications, are complete.

This completes the staff's effort on TAC No. 72137.

Sincerely,

Enclosure:

Safety Evaluation cc w/enclosure:

See next page

/s/

Brenda L. Mozafari, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation OFC

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Ray Starling Manager - Legal Department Carolina Power II Light Company P. 0.

Box 1551

Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U. S. Nuclear Regulatory Commission Route 1, Box 315B New Hill, North Carolina 27562 Mr. R. B. Richey, Vice President Harris Nuclear Project Harris Nuclear Plant P. 0.

Box 165 New Hill, North Carolina 27562 Mr. H. A. Cole Special Deputy Attorney General State of North Carolina P. 0.

Box 629

Raleigh, North Carolina 27602 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street Suite 2900 Atlanta, Georgia 30323 Mr. C.

S. Hinnant Plant General Manager Harris Nuclear Plant P. 0.

Box 165 New Hill, North Carolina 27562 Mr. Dayne H. Brown, Director Division of Radiation Protection N.

C. Department of Environmental, Commerce It Natural Resources P. 0.

Box 27687

Raleigh, North Carolina 27611-7687