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{{#Wiki_filter:L    *i
{{#Wiki_filter:L    *i Q                                                              ~
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Q                                                              ~
      *
         ,'  ,e                                                                                                          j e                                                              aosnwansaw                                              I
         ,'  ,e                                                                                                          j e                                                              aosnwansaw                                              I
                   ,                                          hignm Nuclear Ftwer statiori l
                   ,                                          hignm Nuclear Ftwer statiori l
Rot 6 y Hill Road                                    i Plymouth, Masuchusetts 02360 1
Rot 6 y Hill Road                                    i Plymouth, Masuchusetts 02360 1
                                                                                                                          !
naiph c. s6te                                                                                          !
naiph c. s6te                                                                                          !
Senior Vice President - Nuclear                                                                        i BECo 89 159              l U.S. Nuclear Regul0 tory Commission                                            October M,1989 Document Control Desk                                                                                  i Washington, DC .20555                                                                                  }
Senior Vice President - Nuclear                                                                        i BECo 89 159              l U.S. Nuclear Regul0 tory Commission                                            October M,1989 Document Control Desk                                                                                  i Washington, DC .20555                                                                                  }
                                                                                                                          !
License DPR-35          i Docket 50-293            '
License DPR-35          i Docket 50-293            '
                                                                                                                           ;
                                                                                                                           ;
                                                                                                                          !
RESPONSE TO GENERIC LETTER 88-20. SU_PPLEMENT 1                        !
RESPONSE TO GENERIC LETTER 88-20. SU_PPLEMENT 1                        !
                                                                                                                          !
i This letter describes Boston Edison's program plan for completing an Individual                        !
i This letter describes Boston Edison's program plan for completing an Individual                        !
Plant Examination (IPE) for severe accident vulnerabilities for the Pilgrim                            i Nuclear Power Station (PNPS).                                                                          t i
Plant Examination (IPE) for severe accident vulnerabilities for the Pilgrim                            i Nuclear Power Station (PNPS).                                                                          t i
  ,
  '
Boston Edison intends to perform a Level 1 Probabilistic Risk Assessitent (PRA)                        i based on current plant design and operation. The method will be consistent                            ;
Boston Edison intends to perform a Level 1 Probabilistic Risk Assessitent (PRA)                        i based on current plant design and operation. The method will be consistent                            ;
with NUREG/CR-2300 "PRA Procedures Guide", and accepted PRA guidance                                  i documents.                Fault tree linking methodology will be used for the front-end              j systems analysis. The current plan is to use EPRI's CAFTA code for fault tree                        i analysis and the MAAP code for the determination of system success criteria                          i where appropriate. Previous effortt conducted on the performance of a                                  i preliminary PNPS Probabilistic Safety Assessment, based on NUREG/CR-2815,                            !
with NUREG/CR-2300 "PRA Procedures Guide", and accepted PRA guidance                                  i documents.                Fault tree linking methodology will be used for the front-end              j systems analysis. The current plan is to use EPRI's CAFTA code for fault tree                        i analysis and the MAAP code for the determination of system success criteria                          i where appropriate. Previous effortt conducted on the performance of a                                  i preliminary PNPS Probabilistic Safety Assessment, based on NUREG/CR-2815,                            !
Line 45: Line 36:
guidai!:e provided in Appendix 1 to Generic Letter 88-20. " Guidance on the                            >
guidai!:e provided in Appendix 1 to Generic Letter 88-20. " Guidance on the                            >
Examination of Containment System Performance", and Appendix A to NUREG-1335,                        i i,                  " Approach to Back-end Portion of IPE". MAAP will be used to simulate severe                        >
Examination of Containment System Performance", and Appendix A to NUREG-1335,                        i i,                  " Approach to Back-end Portion of IPE". MAAP will be used to simulate severe                        >
"
accident progression and better define the phenomena occurring during the                            [
accident progression and better define the phenomena occurring during the                            [
L                  postulated severe accidents.
L                  postulated severe accidents.
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f I                                                                                                                        i l                                                                                                                        ;
f I                                                                                                                        i l                                                                                                                        ;
l G911070344 091027 PDR                                                                '
l G911070344 091027 PDR                                                                '
:
P    ADOCK 05000293 PNV                                      pq            [
P    ADOCK 05000293 PNV                                      pq            [
                                                                                                             ,, e
                                                                                                             ,, e l
                                                                                                                          .
r
l r
                                                                                                                  ._.-. -
                -      .-.__ __ _ . _ _ _ .                                                - - _    -.


m
m DOSTON EDISON COMPANY
  ,                                                                                                          ,
        ,                                                                                                    !
DOSTON EDISON COMPANY
          '
      '    *
   ;
   ;
        '
O.i.1[uclea'r Yegulatory Commission Page Two l
O.i.1[uclea'r Yegulatory Commission Page Two l
l                                                                                                            j
l                                                                                                            j
Line 73: Line 53:
our self-initiated Safety Enhancement Program (SEP). Regarding the potential                    '
our self-initiated Safety Enhancement Program (SEP). Regarding the potential                    '
   ;          Mark 1 enhancements discussed in Generic 1.etter 88-20 Supplement 1, we have i
   ;          Mark 1 enhancements discussed in Generic 1.etter 88-20 Supplement 1, we have i
already installed a hardened vent path, modified existing structures to provide
already installed a hardened vent path, modified existing structures to provide an alternate source of water injection into the vessel, < mplemented Revision 4                  ;
  ,
of the EPGs, and installed a backup nitrogen supply system to provide longer                    i term pneumatic control capability to the Automatic Depressurization System.                    i I
an alternate source of water injection into the vessel, < mplemented Revision 4                  ;
u(_ - -
of the EPGs, and installed a backup nitrogen supply system to provide longer                    i term pneumatic control capability to the Automatic Depressurization System.                    i
                                                                                                              !
                                                                                                              .
I u(_ - -
R. G. Bird        j JDKlamm/3786                                                                                )  t Commonwealth of Massachusetts)                                                                  !
R. G. Bird        j JDKlamm/3786                                                                                )  t Commonwealth of Massachusetts)                                                                  !
Ccunty of Plymouth                      )                                                      I
Ccunty of Plymouth                      )                                                      I Then personally appeared before me, Ralph G. Bird, who being duly sworn, did state that he is Senior Vice President - Nuclear of Boston Edison Company and                  i that he is duly authorized to execute and file the submittal contained herein                  '
                                                                                                              .
Then personally appeared before me, Ralph G. Bird, who being duly sworn, did state that he is Senior Vice President - Nuclear of Boston Edison Company and                  i that he is duly authorized to execute and file the submittal contained herein                  '
in the name and on behalf of Boston Edison Company and that the statements in                  ,
in the name and on behalf of Boston Edison Company and that the statements in                  ,
said submittal are true to the best of his knowledge and belief.
said submittal are true to the best of his knowledge and belief.
My commission expires:                ddL;g /#g              ght                              !
My commission expires:                ddL;g /#g              ght                              !
DATE '  f            NOTARY'PUBLIC
DATE '  f            NOTARY'PUBLIC cc:    Mr. D. Mcdonald, Project Manager                                                        .
:
cc:    Mr. D. Mcdonald, Project Manager                                                        .
Division of Reactor Projects - I/II                                                    i Office of Nuclear Reactor Regulation                                                    -
Division of Reactor Projects - I/II                                                    i Office of Nuclear Reactor Regulation                                                    -
Mail Stop: 14D1                                                                        ;
Mail Stop: 14D1                                                                        ;
Line 97: Line 69:
,                    Senior NRC Resident Inspector                                                        [
,                    Senior NRC Resident Inspector                                                        [
Pilgrim Nuclear Power Station                                                        :
Pilgrim Nuclear Power Station                                                        :
                                                                                                            !
                                                                                                            .
:
                                                                                                          !
i
i
_ , _ _ . . . _ _  _.        , __._ __. .                            _}}
_ , _ _ . . . _ _  _.        , __._ __. .                            _}}

Revision as of 00:31, 1 February 2020

Responds to Generic Ltr 88-20,Suppl 1,describing Plan for Completing Individual Plant Exam for Severe Accident Vulnerabilities.Performance of Level 1 PRA Based on Current Plant Design & Operation Intended
ML19325E525
Person / Time
Site: Pilgrim
Issue date: 10/27/1989
From: Bird R
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-CR-2300, RTR-NUREG-CR-2815 BECO-89-159, GL-88-20, NUDOCS 8911070344
Download: ML19325E525 (2)


Text

L *i Q ~

,' ,e j e aosnwansaw I

, hignm Nuclear Ftwer statiori l

Rot 6 y Hill Road i Plymouth, Masuchusetts 02360 1

naiph c. s6te  !

Senior Vice President - Nuclear i BECo 89 159 l U.S. Nuclear Regul0 tory Commission October M,1989 Document Control Desk i Washington, DC .20555 }

License DPR-35 i Docket 50-293 '

RESPONSE TO GENERIC LETTER 88-20. SU_PPLEMENT 1  !

i This letter describes Boston Edison's program plan for completing an Individual  !

Plant Examination (IPE) for severe accident vulnerabilities for the Pilgrim i Nuclear Power Station (PNPS). t i

Boston Edison intends to perform a Level 1 Probabilistic Risk Assessitent (PRA) i based on current plant design and operation. The method will be consistent  ;

with NUREG/CR-2300 "PRA Procedures Guide", and accepted PRA guidance i documents. Fault tree linking methodology will be used for the front-end j systems analysis. The current plan is to use EPRI's CAFTA code for fault tree i analysis and the MAAP code for the determination of system success criteria i where appropriate. Previous effortt conducted on the performance of a i preliminary PNPS Probabilistic Safety Assessment, based on NUREG/CR-2815,  !

"Probabilistic Safety Analysis Procedures Guide", and an Individual Plant l Evaluation, based on the IDCOR methodology, will be incorporated into the PRA. '

I The IDCOR IPE methodology will be used in those areas where the NRC has found  ;

the methodology useful and acceptable. ,

t The back-end containment analysis will be performed in accordance with the  ;

guidai!:e provided in Appendix 1 to Generic Letter 88-20. " Guidance on the >

Examination of Containment System Performance", and Appendix A to NUREG-1335, i i, " Approach to Back-end Portion of IPE". MAAP will be used to simulate severe >

accident progression and better define the phenomena occurring during the [

L postulated severe accidents.

L The schedule for ccmpletion of the IPE is tieing developed in conjunction with  !

,, our Long Term Program (LTP) integrated work management process and will be j i reported in the 1990 semi-annual LTP update. ,

f I i l  ;

l G911070344 091027 PDR '

P ADOCK 05000293 PNV pq [

,, e l

r

m DOSTON EDISON COMPANY

O.i.1[uclea'r Yegulatory Commission Page Two l

l j

! Implementation of containment performance improvements began at PNPS as part of l r

our self-initiated Safety Enhancement Program (SEP). Regarding the potential '

Mark 1 enhancements discussed in Generic 1.etter 88-20 Supplement 1, we have i

already installed a hardened vent path, modified existing structures to provide an alternate source of water injection into the vessel, < mplemented Revision 4  ;

of the EPGs, and installed a backup nitrogen supply system to provide longer i term pneumatic control capability to the Automatic Depressurization System. i I

u(_ - -

R. G. Bird j JDKlamm/3786 ) t Commonwealth of Massachusetts)  !

Ccunty of Plymouth ) I Then personally appeared before me, Ralph G. Bird, who being duly sworn, did state that he is Senior Vice President - Nuclear of Boston Edison Company and i that he is duly authorized to execute and file the submittal contained herein '

in the name and on behalf of Boston Edison Company and that the statements in ,

said submittal are true to the best of his knowledge and belief.

My commission expires: ddL;g /#g ght  !

DATE ' f NOTARY'PUBLIC cc: Mr. D. Mcdonald, Project Manager .

Division of Reactor Projects - I/II i Office of Nuclear Reactor Regulation -

Mail Stop: 14D1  ;

U. S. Nuclear Regulatory Commission i 1 White Flint North  :

11555 Rockville Pike Rockville, MD 02852 -

U. S. Nuclear Regulatory Commission l Region I l 475 Allendale Road King of Prussia, PA 19406

, Senior NRC Resident Inspector [

Pilgrim Nuclear Power Station  :

i

_ , _ _ . . . _ _ _. , __._ __. . _