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{{#Wiki_filter:RFGULATORY INFORMATION DISTRIBUTION 8'~>EM (RIDS)ACCE'SS ILL NBR: 8007030102 DOC, DATE: BW/06/28 NOTARIZED:
{{#Wiki_filter:RFGULATORY INFORMATION DISTRIBUTION 8'~>EM                         (RIDS)
NO DOCKET FACIL:50-400 Shearon Harris Nuclear Poser Plant<Unit 1.Carolina'5000400 A UTH.NAI1E, AUTHOR AFFILIATION ZIMMERMANiS.R, Car ol ina Power I Light Co>'ECIP.NAME RECIPIENT AFF ILIATIQN DENTONgH~RE Office of Nuclear Reactor Regulationr Director  
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:==
==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 COPIES RECEIVED:LTR L ENCL~, SIZE: TITLE: Licensing Submittal!
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.
PSAR/FSAR Amdts K Related Correspondence NOTES;RECIPIENT ID CODE/NAME NRR/DL/ADL NRR L83 LA INTEiRNAL:
DISTRIBUTION CODE'001S TITLE: Licensing COPIES RECEIVED:LTR Submittal! PSAR/FSAR Amdts K L ENCL     ~, SIZE:
ELD/HDS1 IE/DEPER/EPB 36 ,IE/DQASIP/QA821 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 20 MRR/DHFS/HFE840 NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGN2 EXTERNAL: ACRS 01 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCI 1 0 1 0 1 0 3 3 1 1 1 1 2 2 1 1 1 1 4)1 1 1 1 1 1 1 1 1 1 1 1 3 3 6&.1 1 1 1 1 1 RECIPIENT ID CODE/NAh1E NRR LB3 BC BUCKLEYgB 01 e IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DS I/CSB 09 NRR/DSI/METB 12 N 8 22 REG F 0Q'/DAMI/MI8 BNL(Ah1DTS ONLY)FEMA"REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1 0 1 1 1 1 1 1 1 0 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1-1 1 1 1 0 1 1 1 1 1 1 TOTAL NUMBER OF COPIES HNUIREDe LTTR 53 ENCL 46  
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 JUN 38 1984 SERIAL: NLS-84-263 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  
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
 
        /i
~ 1 Ik 1
 
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.


==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, ESS/gvc (239NLU)Attachments S.R.mmerman anager Nuclear Licensing Section CC: Mr.B.C.Buckley (NRC)Mr.G.F.Maxwell (NRC-SHNPP)
Mr.David Terao (NRC-MEB)Mr.J.P.O'Reilly (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library Mr.Wells Eddleman Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.0.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)84Ob28 84070S010>050p04 0>DR AQOGW pgR L E PpP 411 Fayetteville Street o P.O.Box 1551 o Raleigh, N.C.27602
/i~1 Ik 1 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}}
I}}

Latest revision as of 04:21, 22 October 2019

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 Duke Energy icon.png
Issue date: 06/28/1984
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML18018B693 List:
References
NLS-84-263, NUDOCS 8407030102
Download: ML18018B692 (6)
v • d • e


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

/i

~ 1 Ik 1

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

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