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{{#Wiki_filter:REGULATOR NFORMATION DISTRIBUTION TEM (RIDS)ACCESSION NBR: 8306060152 DOC~DATE: 83/06/02 NOTARI'ZED:
{{#Wiki_filter:REGULATOR                 NFORMATION DISTRIBUTION           TEM (RIDS)
NO FACIL:50 F00 Shearon Harris Nuclear Power Plant~Uni t 1~Carolina SO"401 Shearon Harris Nuclear Power PlantP Unit 2~Car oli,na AUTH BYNAME AUTHOR AFFILIATION MCDUFFIEgM>>A, Carolina Power 8 Light Co~REC IP~NAME RECIPIENT AFFILIATION DENTONrH~RE Office of Nuclear Reactor RegulationE Director SUBJECT!Forwards response to draft SER Open Item 210 re results of evaluation of chemical 8 vol control sys malfunction event, Transient scenario would not experience significant change except for delay of pressurizer low pressure trip.DISTRIBUTION CODE: BOO IS COPIES RECEIVED:LTR
ACCESSION NBR: 8306060152                       DOC ~ DATE: 83/06/02     NOTARI'ZED: NO         DOCKET FACIL:50 F00     Shearon       Harris           Nuclear   Power Plant~ Uni t 1 ~ Carolina     05000000 SO"401 Shearon Harris Nuclear Power PlantP Unit 2~ Car oli,na BYNAME                                                                                    05000401 AUTH                   AUTHOR             AFFILIATION MCDUFFIEgM>>A,           Carolina Power 8 Light Co                 ~
/ENCL jSIZE: TITLE: Licensing Submittal>>
REC IP ~ NAME           RECIPIENT AFFILIATION DENTONrH ~ RE           Office of Nuclear Reactor RegulationE Director SUBJECT! Forwards       response to draft SER Open Item 210 re results of evaluation of chemical 8 vol control sys malfunction event, Transient scenario would not experience significant change except for delay of pressurizer low pressure trip.
PSAR/FSAR Amdts L Related Correspondence NOTES: DOCKET 05000000 05000401 REC IP IENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL: ELD/HDS1 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2'RR/DE/SGEB 30 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DSI/ASB NRR/DS I/CSB 09 NRR/DS I/METB 1?RAB 22 REG FILE 04 I/MIB EXTERNAl: ACRS 41 DMS/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 0 1 0 3 1 1 1 2 2 1 1 1 1 1 1 1 1 0 1 1 f 1 1 1 1 1 1 0 6 1 1'1 RECIPIENT ID CODE/NAME NRR LB3 BC KADAMBI pP 01 IE FILE IE/DEPER/IR8
DISTRIBUTION CODE:       BOO             IS COPIES RECEIVED:LTR       / ENCL jSIZE:
$5 NRR/DF/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/HFEBPO NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DS I/CP8 10 NRR/DSI/ICSB 16 NRR/DS I/PSB 19 NRR/DSI/RSB 23 RGN2 BNL(AMDTS ONLY)FEMA REP DIV 39 NRC PDR 02 NTIS COPIES lTTR ENCL 0 1 1 1 1 1 1 1 0 1 1 2 2 1'2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 1 1 1 1 1 1 1 1'TOTAL NUMBER OF COPIES REQUIRED: LTTR 55 ENCL 48 k III , ilt 1 I't III p'i f)~i".i I ill II ill 4,i Il,.i'iI4 l j j,l fi 4 i ll l II', rr Eg W'I i il I'I 1 l Wf''~n n'l'lt i 4 I'[.4 Il,j r,4 III4 ll I" h 4W crl K CÃQE,.Carolina Power&Light Company r MIJN 03>983 SERIAL: LAP-83-140 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.1 AND 2 DOCKET NOS.50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES REACTOR SYSTEMS BRANCH
TITLE: Licensing Submittal>> PSAR/FSAR Amdts                         L Related Correspondence NOTES:
REC IP IENT                     COPIES            RECIPIENT            COPIES ID CODE/NAME                     LTTR ENCL        ID CODE/NAME          lTTR  ENCL NRR/DL/ADL                           1      0    NRR   LB3 BC                    0 NRR  LB3 LA                                 0    KADAMBIpP        01      1    1 INTERNAL: ELD/HDS1                                 1      0    IE FILE                  1    1 IE/DEPER/EPB       36                       3    IE/DEPER/IR8    $5      1    1 IE/DEQA/QAB       21                 1            NRR/DF/AEAB              1    0 NRR/DE/CEB           11               1      1    NRR/DE/EHEB              1    1 NRR/DE/EQB          13              2      2    NRR/DE/GB        28      2    2 NRR/DE/MEB          18                1      1    NRR/DE/MTEB 17            1 NRR/DE/SAB                            1      1    NRR/DE/SGEB 25          '2    2 30 2'RR/DE/SGEB 1            NRR/DHFS/HFEBPO          1    1 NRR/DHFS/LQB 32                      1      1    NRR/DHFS/PSRB            1    1 NRR/DL/SSPB                          1      0    NRR/DS I/AEB 26          1    1 NRR/DSI/ASB                          1      1    NRR/DS I/CP8    10      1    1 NRR/DS I/CSB 09                              f    NRR/DSI/ICSB 16           1    1 NRR/DS I/METB 1?                      1      1    NRR/DS I/PSB     19       1    1 RAB    22                  1      1    NRR/DSI/RSB 23           1    1 REG FILE          04                        1    RGN2                     3    3 I/MIB                      1      0 EXTERNAl: ACRS                  41                        6    BNL(AMDTS ONLY)           1    1 DMS/DSS    (AMDTS)                '  1      1    FEMA REP DIV 39           1    1 LPDR              03                              NRC PDR         02       1     1 NSIC              05                  1           NTIS                      1     1
'TOTAL NUMBER OF COPIES REQUIRED: LTTR                         55   ENCL   48


==Dear Mr.Denton:==
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Carolina Power 5 Light Company (CPKL)hereby transmits one original and forty copies of the response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER)CPAL Open Item No.210.Carolina Power&Light Company will be providing responses to other Open Items in the DSER shortly.Yours very truly, PS/cfr (6738PSA)Attachment M.A.McDuffie Senior Vice President Engineering
            ,
&Construction cc: Mr.N.Prasad Kadambi (NRC)Mr.Evangelo Marinos (NRC-RSB)Mr.G.F.Maxwell (NRC-SHNPP)
ilt 1                            f
Mr.J.P.O'Reilly (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)
                                      ) ~   i"  .i I  ill II ill I 't III        4,i    Il,.i'iI4 l                4 i            l                    Eg j,l j
Chapel Hill Public Library Wake County Public Library Mr.Wells Eddleman Dr.Phyllis Lotchin Ms.Patricia T.Newman Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.0.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)830bOb0152 830b02 PDR ADOCK 05000400 E PDR 411 Fayettevllle Street~P.O.Box 1551 o Raleigh, N.C.27602@eel tlt 0 t i 3PJ 8 f>YiV f I 4 h\l I//
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OPEN ITEM No.210 (DSER Section'l5.5, page 15-24)Provide the results of the evaluation of the Chemical and Volume Control System malfunction event (Q 440.132).RESPONSE TO OPEN ITEM No.210 This concern was previously presented as FSAR Safety Review Question 440.132.Attachment I provides the response to Question 440.132.
                                                                          'I i  il I'I     1 l Wf'' ~
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ATTACHMENT I Response to FSAR Safety Review Question 440.132
SERIAL: LAP-83-140 CÃQE,.
Carolina Power & Light Company r
MIJN  03  >983 Mr. Harold R. Denton,      Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington,    DC    20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES REACTOR SYSTEMS BRANCH


0UESTION 440.132 (15.5): Your response to question 440.93 is not clear.Mould the power increase caused by the iniection of cold unborated water chanae the transient scenario7 If so, provide verification that this does not present a worse case transient.
==Dear  Mr . Denton:==
RESPONSE The SI system purge volume between'the BIT and the cold legs is approximately 8 FT.This volume, if cold and unborated, is purged in a very short period 3 by the Safety Injection System and immediately followed by 20000 ppm borated water from the BIT.This could result in a slight power increase similar to the boron dilution event and would be overridden by the borated water from the BIT.The transient scenario would not experience any significant change with the exception of the Pressurizer L'ow Pressure trip being delayed.
 
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Carolina Power      5 Light Company (CPKL) hereby transmits one original and  forty copies of the        response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER) CPAL Open Item No. 210.
Carolina Power      & Light      Company    will be    providing responses      to other Open  Items in the    DSER  shortly.
Yours very      truly, M. A. McDuffie Senior Vice President Engineering & Construction PS/cfr    (6738PSA)
Attachment cc:    Mr. N. Prasad Kadambi (NRC)                              Mr. Wells Eddleman Mr. Evangelo Marinos (NRC-RSB)                          Dr. Phyllis Lotchin Mr. G. F. Maxwell (NRC-SHNPP)                            Ms. Patricia T. Newman Mr. J. P. O'Reilly (NRC-RII)                            Mr. John D. Runkle Mr. Travis Payne (KUDZU)                                Dr. Richard D. Wilson Mr. Daniel F. Read (CHANGE/ELP)                          Mr. G. 0. Bright (ASLB)
Chapel Hill Public Library                              Dr. J. H. Carpenter (ASLB)
Wake County Public Library                              Mr. J. L. Kelley (ASLB) 830bOb0152 830b02 PDR ADOCK 05000400 E                    PDR                                                                                  @eel 411 Fayettevllle Street ~ P. O. Box 1551 o Raleigh, N. C. 27602                    tlt
 
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OPEN ITEM No. 210 (DSER  Section 'l5.5, page 15-24)
Provide the results of the evaluation of the Chemical and Volume Control System malfunction event (Q 440. 132).
RESPONSE TO OPEN ITEM No. 210 This concern was previously presented as FSAR Safety Review Question 440. 132. Attachment I provides the response to Question 440. 132.
 
ATTACHMENT I Response to FSAR Safety Review Question 440. 132
 
0UESTION 440.132   (15.5):
Your response to question 440.93 is not clear. Mould the power increase caused by the iniection of cold unborated water chanae the transient scenario7   If so, provide verification that this does not present a worse   case transient.
 
===RESPONSE===
The SI system purge volume between'the   BIT and the cold legs is approximately 3
8 FT . This volume, if cold and unborated, is purged in a very short period by the Safety Injection System and immediately followed by 20000 ppm borated water from the BIT. This could result in a slight power increase similar to the boron dilution event and would be overridden by the borated water from the BIT. The transient scenario would not experience any significant change with the exception of the Pressurizer L'ow Pressure trip being delayed.
 
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Revision as of 06:23, 22 October 2019

Forwards Response to Draft SER Open Item 210 Re Results of Evaluation of Chemical & Vol Control Sys Malfunction Event. Transient Scenario Would Not Experience Significant Change Except for Delay of Pressurizer Low Pressure Trip
ML18003A878
Person / Time
Site: Harris  
Issue date: 06/02/1983
From: Mcduffie M
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
LAP-83-140, NUDOCS 8306060152
Download: ML18003A878 (10)
v • d • e


Text

REGULATOR NFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR: 8306060152 DOC ~ DATE: 83/06/02 NOTARI'ZED: NO DOCKET FACIL:50 F00 Shearon Harris Nuclear Power Plant~ Uni t 1 ~ Carolina 05000000 SO"401 Shearon Harris Nuclear Power PlantP Unit 2~ Car oli,na BYNAME 05000401 AUTH AUTHOR AFFILIATION MCDUFFIEgM>>A, Carolina Power 8 Light Co ~

REC IP ~ NAME RECIPIENT AFFILIATION DENTONrH ~ RE Office of Nuclear Reactor RegulationE Director SUBJECT! Forwards response to draft SER Open Item 210 re results of evaluation of chemical 8 vol control sys malfunction event, Transient scenario would not experience significant change except for delay of pressurizer low pressure trip.

DISTRIBUTION CODE: BOO IS COPIES RECEIVED:LTR / ENCL jSIZE:

TITLE: Licensing Submittal>> PSAR/FSAR Amdts L Related Correspondence NOTES:

REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME lTTR ENCL NRR/DL/ADL 1 0 NRR LB3 BC 0 NRR LB3 LA 0 KADAMBIpP 01 1 1 INTERNAL: ELD/HDS1 1 0 IE FILE 1 1 IE/DEPER/EPB 36 3 IE/DEPER/IR8 $5 1 1 IE/DEQA/QAB 21 1 NRR/DF/AEAB 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 NRR/DE/SAB 1 1 NRR/DE/SGEB 25 '2 2 30 2'RR/DE/SGEB 1 NRR/DHFS/HFEBPO 1 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRR/DS I/AEB 26 1 1 NRR/DSI/ASB 1 1 NRR/DS I/CP8 10 1 1 NRR/DS I/CSB 09 f NRR/DSI/ICSB 16 1 1 NRR/DS I/METB 1? 1 1 NRR/DS I/PSB 19 1 1 RAB 22 1 1 NRR/DSI/RSB 23 1 1 REG FILE 04 1 RGN2 3 3 I/MIB 1 0 EXTERNAl: ACRS 41 6 BNL(AMDTS ONLY) 1 1 DMS/DSS (AMDTS) ' 1 1 FEMA REP DIV 39 1 1 LPDR 03 NRC PDR 02 1 1 NSIC 05 1 NTIS 1 1

'TOTAL NUMBER OF COPIES REQUIRED: LTTR 55 ENCL 48

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SERIAL: LAP-83-140 CÃQE,.

Carolina Power & Light Company r

MIJN 03 >983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES REACTOR SYSTEMS BRANCH

Dear Mr . Denton:

Carolina Power 5 Light Company (CPKL) hereby transmits one original and forty copies of the response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER) CPAL Open Item No. 210.

Carolina Power & Light Company will be providing responses to other Open Items in the DSER shortly.

Yours very truly, M. A. McDuffie Senior Vice President Engineering & Construction PS/cfr (6738PSA)

Attachment cc: Mr. N. Prasad Kadambi (NRC) Mr. Wells Eddleman Mr. Evangelo Marinos (NRC-RSB) Dr. Phyllis Lotchin Mr. G. F. Maxwell (NRC-SHNPP) Ms. Patricia T. Newman Mr. J. P. O'Reilly (NRC-RII) Mr. John D. Runkle Mr. Travis Payne (KUDZU) Dr. Richard D. Wilson Mr. Daniel F. Read (CHANGE/ELP) Mr. G. 0. Bright (ASLB)

Chapel Hill Public Library Dr. J. H. Carpenter (ASLB)

Wake County Public Library Mr. J. L. Kelley (ASLB) 830bOb0152 830b02 PDR ADOCK 05000400 E PDR @eel 411 Fayettevllle Street ~ P. O. Box 1551 o Raleigh, N. C. 27602 tlt

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OPEN ITEM No. 210 (DSER Section 'l5.5, page 15-24)

Provide the results of the evaluation of the Chemical and Volume Control System malfunction event (Q 440. 132).

RESPONSE TO OPEN ITEM No. 210 This concern was previously presented as FSAR Safety Review Question 440. 132. Attachment I provides the response to Question 440. 132.

ATTACHMENT I Response to FSAR Safety Review Question 440. 132

0UESTION 440.132 (15.5):

Your response to question 440.93 is not clear. Mould the power increase caused by the iniection of cold unborated water chanae the transient scenario7 If so, provide verification that this does not present a worse case transient.

RESPONSE

The SI system purge volume between'the BIT and the cold legs is approximately 3

8 FT . This volume, if cold and unborated, is purged in a very short period by the Safety Injection System and immediately followed by 20000 ppm borated water from the BIT. This could result in a slight power increase similar to the boron dilution event and would be overridden by the borated water from the BIT. The transient scenario would not experience any significant change with the exception of the Pressurizer L'ow Pressure trip being delayed.

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