ML18030A319
| ML18030A319 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/01/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18030A320 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM PLA-865, NUDOCS 8107060209 | |
| Download: ML18030A319 (3) | |
Text
REGULAT'"Y INFORMATION DISTRIBUTION "YSTEM (RIOS)
O'CCESSION NBR:8107060209 DOC ~ DATE: 81/07/01 NOTARIZED:
NO OOCXET ¹ FACIL:50 387 Susquehanna Steam Electric Station< Unit ii Pennsylva 05000387 50 388 Susquehanna Steam Electric Stationi Unit 2i Pennsy.lva 05 AUTH'AME AUTHOR AFFILIATION CURTIS'
~ ii ~
Pennsylvania Power 8 Light Coo REC IP ~ NAIVE.
RECIPIENi'FFILIATION SCRWKNCERrA ~
Licensing Branch 2
SUBJECT:
Forwards generic BWR safety relief valve test. results to confirm aaequacy of safety relief valves for plant for all test conditions per 8'00917 ltd Final repts on valve qualification 8 piping/supports will be submitted'ISTRIBUTION CODE:
A046S COPIES RECEIVED:LTR
- f. ENCL g SIZE: 2+
TITLEj Response.
to NUREG 0787/NUREG 0660 THI Action Plan Rgmts (OL's)
NOTESj Send I8E 3-copies FSAR
& al l amends.i cy:BWR LRG PM(L.RIB) 05000387 Send I8E 3 copies FSAR 8 al 1
- amends, 1
cy'.BWR LRG PH(L.RIB) 05000388 RECIPIENT ID CODE/NAME ACTION:
LIC BR ¹2 BC 05 INTERNAL: A/D C8 C SYS 27 A/5 FOR TECH 32'/0 LIGENs 1 6 A/D OP REACT 1>.
A/0 RAD PROT 26'EP DIRg DHFS 29 0 IRECTOR i DE.
21.
DIRECTOR i DL 14 DIRECTORiDST 30 EHRG-PRP LIC I8,E 12'R ASSESS BR 18 RAD ASHT BR COP IKS LTTR ENCL 7
7 1
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RECIPIENT ID CODE/NAHE A/D C8S ENG 22 A/D GKN PROJ 31 A/0 M8,Q ENG 23 A/D PLANT SYS25 A/0 SAFETY AS17, DIRgEH PREP 33 0 IRECTOR i OHFS28 DIRECTORS'SI 24 EMERG PRKP DEV FEHA REP DIV OELD PDR 02 G FIL 01 COPIES LTTR ENCL 1
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1 1
1 EXTERNAL; ACRS LPDR NTIS 34 ie 16 03i 1
1 1
1 INPOgJ,STARNKS NSIC 04 1
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5(c TOTAL NUMBER'F COPIES REQUIRED:
LTTR 5'NCL
PPal TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEr t215) 770-5151 NORMAN W. CURTIS Vice President-Engineering tL Construction-Nuclear 770 5381 July 1,
1981 Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION SAFETY/RELIEF VALVE TEST PROGRAM PRELIMINARY RESULTS ER 100450 FILES 204-9 841-12 PLA-865
Dear Mr. Schwencer:
References:
l.
2.
3.
Letter from T. J. Dente, (BWR Owners'roup) to D. G. Eisenhut (NRC), "Transmittal of Preliminary Data from Generic BWR Safety/Relief Valve (SRV) Test Program" dated July 1, 1981 Letter from D. B. Waters (BWR Owners'roup) to R. H. Vollmer (NRC),
"NUREG-0578 Requirement 2.1.2-Performance Testing of BWR and PWR Relief and Safety Valves" dated September 17, 1980 Letter from D. B. Waters (BWR Owner's Group) to D. G. Eisenhut (NRC), "Responses to NRC Questions on the BWR SRV Test Program" dated March 31, 1981 (Response to NRC Question No. 1)
In response to NUREG 0737, Item II.D.l, this letter provides the results of a preliminary review of the generic BWR SRV test program results (Reference 1) in order to confirm the adequacy of the SRV's for Susquehanna Plant for all test conditions as defined in the test description (Reference 2).
The Susquehanna Plant employs the Crosby type of SRV, Model No.
6R10.
The test results for the Crosby Valve, Model No.
6R10 are applicable to this plant's valves (Reference 3).
A preliminary review of the generic BWR SRV test program results demonstrates that the tested valve satisfies the acceptance criteria for operability.
Consequently, based on this preliminary review, the operational adequacy of the SRV's for the Susquehanna Plant has been demonstrated.
go4 S
li PENNSYLVANIA POWER EL LI G H T COMPANY Si0706020'7t 8107~~;.
P DR ADOCK. 050003Bg$,
A
Mr. A. Schwencer Page 2
Final reports on SRV qualification and piping and supports will be submitted as committed in our response to NUREG 0737, requirement II.D.l (PLA-659).
Very truly yours, N. W. Curtis Vice President-Engineering 6 Construction-Nuclear DPM/mks cc:
R. M. Stark NRC
/