ML18018B692

Forwards Rept on Operability of Pressurizer Safety Relief Valves,Porvs & Electrical Motor Operated Block Valves, Per Mechanical Engineering Branch SER Confirmatory Item 6

ML18018B692
Person / Time
Site:	Harris
Issue date:	06/28/1984
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML18018B693	List: ML18018B692 ML18018B694
References
NLS-84-263, NUDOCS 8407030102
Download: ML18018B692 (6)

Text

RFGULATORY INFORMATION DISTRIBUTION 8'~>EM (RIDS)

ACCE'SS ILL NBR: 8007030102 DOC, DATE: BW/06/28 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Poser Plant< Unit 1. Carolina '5000400 A UTH. NAI1E, AUTHOR AFFILIATION I Light ZIMMERMANiS.R, Car ol ina Power RECIPIENT AFF ILIATIQN Co>'ECIP.NAME DENTONgH ~ RE Office of Nuclear Reactor Regulationr Director

SUBJECT:

Forwards "Rept on Operability of Pressurizer Safety Relief Y al vesipoRv sL Electrical Motor Ooerat:ed Block Val ves goer ~d' Mechanical Engineering Branch SER Confirmatory Item 6.

DISTRIBUTION CODE'001S TITLE: Licensing COPIES RECEIVED:LTR Submittal! PSAR/FSAR Amdts K L ENCL ~, SIZE:

Related Correspondence NOTES; RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCI ID CODE/NAh1E LTTR ENCL NRR/DL/ADL 1 0 NRR LB3 BC 1 0 NRR L83 LA 1 0 BUCKLEYgB 01 1 1 e

INTEiRNAL: ELD/HDS1 1 0 IE FILE 1 1 IE/DEPER/EPB 36 3 3 IE/DEPER/IRB 35 1 1

,IE/DQASIP/QA821 1 1 NRR/DE/AEAB 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 NRR/DE/EQB 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 20 1 1 NRR/DE/SGEB 25 1 1 MRR/DHFS/HFE840 4) NRR/DHFS/LQB 32 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRR/DSI/AEB 26 1 1 NRR/DS I/ASB 1 1 NRR/DS I/CPB 10 1 1 NRR/DS I/CSB 09 1 NRR/DSI/ICSB 16 1 1 NRR/DSI/METB 12 1-NRR/DSI/PSB 19 1 1 N 8 22 1 NRR/DS I/RSB 23 1 1 REG F 0Q 1 1 RGN2 3 3 '/ DAMI /MI8 1 0 EXTERNAL: ACRS 01 6 &. BNL(Ah1DTS ONLY) 1 DMB/DSS (AMDTS) 1 1 FEMA "REP DIV 39 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES HNUIREDe LTTR 53 ENCL 46

CSEE Carolina Power & Light Company SERIAL: NLS-84-263 JUN 38 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1' DOCKET NO ~ 50-400 TESTING OF SAFETY AND RELIEF VALVES

Dear Mr. Denton:

Carolina Power 6 Light Company (CPSL) hereby submits additional information concerning Shearon Harris Nuclear Power Plant Testing of Safety and Relief Valves. This information is in response,to--Safety Evaluation Report (SER)

Confirmatory Item No. 6 from the Mechanical Engin'eering Branch.

If you have any questions or require further information, please feel free to contact me.

Yours very truly, S. R. mmerman anager Nuclear Licensing Section ESS/gvc (239NLU)

Attachments CC: Mr. B. C. Buckley (NRC) Wake County Public Library Mr. G. F. Maxwell (NRC-SHNPP) Mr. Wells Eddleman Mr. David Terao (NRC-MEB) Mr. John D. Runkle Mr. J. P. O'Reilly (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. 0. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB)

Chapel Hill Public Library Mr. J. L. Kelley (ASLB) 84Ob28 PpP 84070S010>050p04 0

>DR AQOGW pgR L E

411 Fayetteville Street o P. O. Box 1551 o Raleigh, N. C. 27602

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Shearon Harris Nuclear Power Plant Safety Evaluation Report Confirmator Item No. 6 Item:

In accordance with Item II,DE 1 of NUREG-0737, PWR and BWR licensees and applicants are required to conduct testing to qualify the reactor coolant system relief and safety valves, block valves, and associated piping and supports under expected operating conditions for design-basis transients and accidents.

The Electric Power Research Institute (EPRI) was contracted by the PWR Owners'roup to develop and carry out a generic test program and to provide the generic test data to be used by the PWR utilities to satisfy the NUREG-0737, Item II.D.l requirements. On the basis of a preliminary review of the EPRI Generic Reports, the Staff has concluded that they contain data that can be used by the applicant to prepare an Item IIELD.l plant-specific response for the valves and associated piping for Shearon Harris'he Staff requires that these plant-specific submittals be made before fuel load in accordance with the schedule of NUREG-0737 and the September 29, 1981 clarification letter on this matter. Once the Staff has received this information, it will report its findings in a supplement to the SER.

RESPONSE

Carolina Power E Light Company hereby submits the following documentation as a plant-specific response to Item II.D.l, NUREG-0737:

l. Analysis of pressurizer power operated relief valve and safety valve discharge piping.

2~ Report on the operability of pressurizer safety relief valves, power operated relief valves, and electrical motor operated block valves.

I