ML18030A351

Provides Final Test Results Which Demonstrate Operational Adequacy of Safety Relief Valves.Submittal of NEDE-24988-P Satisfies 811001 & 820101 Submittal Requirements of NUREG- 0737,Item II.D.1

ML18030A351
Person / Time
Site:	Susquehanna
Issue date:	10/01/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM PLA-940, NUDOCS 8110070230
Download: ML18030A351 (2)

Text

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RKC Ip. VA'<i=i RKCI ? IiN f AF F Ii.IAT IOV SCHNKNCERR A. 'ii censing, Br anch 2 SUBJECT;. Provides tern' final= test resul ts ~Ehich demonstrate ooer ational adequacy of safety r el i ef val ves Submi ttal of NEDK 2'4988 P ~

sat i sf i es 811001 a 820101 subn<i t tal requir ements of VURKG 0737I I I', 3 ~ 1 ~

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Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215 i 7705151

'L Norman W. Curtis V/ce President-Engineering 6 Construction-Nuclear 215/ 770-5381 A~

October 1, 1981 tr$ t',Pj g -<,

Mr. A. Schwencer, Chief OCT 8 88>~ e Licensing Branch No. 2. .

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Division of Project Management lg U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION SAFETY RELIEF VALVE OPERABILITY TEST REPORT ER 100450 FILE, 834-1 PLA&40

References:

1) Letter- from T'. Dente (BWR Owners'roup) to D. G. Eisenhut (NRC), "Transmittal of Valve Operability Test Report from Generic BWR Safety/Relief Valve (SRV) Test Program" dated September 25,, 1981.

2) Letter from N. W. Curtis to A. Schwencer, "Safety Relief Valve Test Program Preliminary Results," July 1, 1981 (PLA-865).

In response to NUREG 0737 Item II.D.1, this letter provides the final test results which demonstrate the operational. adequacy of the SRVs for Susquehanna.

In addition, the adequacy of the SRV-discharge piping and supports has also been -.demonstrated. These final test results are contained in NEDE-24988-P, "Analysis of Generic BWR Safety/Relief Valve Operability Test Results-"

which was submitted to the NRC via Reference 1. PPSL is a participant in the BWR Owners. Group generic SRV operability test program..

S'usquehanna employs; the Crosby 6R10 SRV. The applicability of the generic test.

results: to this- SRV'as; already been demonstrated in. Reference 2.

A. review. of, the test. report shows that the. operational. adequacy of the. SRVs and the piping and supports has been" demonstrated for the conditions defined 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.l and completes our efforts on this item.

Very truly yours, N. . Curtis Vice President-Engineering & Construction-Nuclear cc: M. W. Hodges (NRC) ~~nl J. A. Olshinski (NRC)

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