ML20011A273

Provides Final Test Results Re Operational Adequacy of Safety Relief Valves,Per TMI Action Plan Item II.D.1

ML20011A273
Person / Time
Site:	Brunswick
Issue date:	10/05/1981
From:	Utley E CAROLINA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NO-81-1631, NUDOCS 8110080413
Download: ML20011A273 (2)

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ll L" Cp&L Carol!na Power & Light Company October 5, 1981 File: NC-3514(B) Serial No.: NO-81-1631 Mr. Darrell G. Eisenhut, Director Division of Licensing United States Nuclear Regulatory Commission Washin'gton, D.C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 NUREG-0737 ITDI II.D.1, " RELIEF AND SAFETY VALVE TEST REQUIREMENT"

Dear Mr. Eisenhut:

In response to NUREG-0737, " Clarification of TMI Action Plan Requirements", Item II.D.1, " Relief and Safety Valve (S/RV) Testing",

this letter provides the final test results which demonstrate the operatior.al adequacy of the.S/RVs for the Brunswick Steam Electric Plant. In addition, the adequacy of the S/RV discharge piping and

. supports-has also been demonstrated. These final test results are contained in NEDE-24988-P, " Analysis of Generic BWR Safety / Relief Valva Operability Test Results" which was submitted to the NRC by the BWR Owners' Group on September 25, 1981. Carolina Power & Light Company is a

. participant in the BWR Owners' Group generic S/RV operability test

-program.

The Brunswick Plant employs the Target Rock type of S/RV, Model Nos. 7467F and 7567F. The applicability of the generic ' test results to this plant's S/RVs has already been demonstrated in CP&L's letter dated June 30, 1981. A review of the test report shows that the operacional-adequacy of the S/RV's and the piping and supports for the Brunswick Plant has been demonstrated for the conditions d. .ined in Item II.D.1 The submittal of NEDE-24988-P and this letter satisfies the October 1, 1981 and January 1, 1982 submittal requirements of Item II.D.1 and completes CP&L efforts on this item.

Table 1-2 of Appendix A of the subject NEDE Report shows that Brunewick Unit 2 has Model No. 7567F S/RVs installed; this is a typographical error. Brunswick Unit 2 currently has Model No. 7467F S/RVs installed.

However, during the next refuellng outage, Model No. 7567F S/RVs will be installed. This error does not affect the validity of the final test results since both Model No. 7467F and 7567F S/RVs meet the test criteria.

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• P. O. Box 1551

• Raleigh, N. C. 27602  !

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E. E. Utley.' \ .I Executive Vice President Power Supply and Engineering & Construction JHE/lr (6437) cc: , Messrs. J. P. O'Reilly (NRC-RII)

M. W.~ Hodges (NRC)

J. A. Olshinski -(NRC)

, D. M.'Verrelli'(NRC)

JJ. Van'Vliet (NRC)

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