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=Text=
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{{#Wiki_filter:.3-84 .1mwfh MWm ~kdimd be 66 10mdh imd kb& .b ow Molcnrumh ft .mft Commlnf IVcF we.SU~fl8Io~adCFHPWIO, 8b40l.,4 a~lOcFlR Int,lo Seaom dM md5Ut 10 CIR Put A0, u4Id 1u0b CMA4 o, 10 FR Pa7d 71u OWISA4Io A p mof 111 Ad and O..tutu.s,naid uiutu. o d Olw o now or hImlaltri efflct; md A. Pd,,u Lmua The ftwmsb md* b operv m. do W ,,,wWr kwh bb ra m In ame of im M(M4 B.AjmrW,~W No. 256 a. hmby kcaqpomuIn oi riemmed ftm.The 1... duopm 1ids May, in acmiurmec v8a Um Teindm~C. F10CW Th 1wImnea dull maik mdbin rpupo in accodrium with ob ruqAiraw Glen@0 T.*iinI qmdkaftbL D., The Elcum. uh. kvWp fWIlyqit In with the rqbmpuiu of go. Tudanmin Bpcllalab.
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            ,.:*cd  h  ft     .mft Commlnf   m*umt SU~fl8Io~adCFHPWIO, 8b40l.,4 a~lOcFlR Int,lo       IVcF        we.
: e. Deltdq bvAmeuipMsnW H. Deleted bAmemknr4 2 SalyAW 31 -Rqpat iad saaproveinft SMl. 5 dated Sepotutr 19.P.m. Sup 1 8 amwb ddt"d May29, 1980, October 9, 1look 1982, 1&wunberIa, 1082. Jamsuy 17,.1984, Fabry 25, 1988, nd Renewmd 1L1ens No._PPR-,, Amendment
Seaom           dM md5Ut 10A0,      CIR Put u4Id 1u0b CMA4o, 10 FR Pa7d     71u OWISA4Io A                 p       mof 111Ad and O..
_o.256 (2) The Updated Final Safety Analysis Report supplement as revised on July 25, October 1, November 4, and December 2, 2002, shall be included in the next scheduled update to the licensee's Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise complies with the requirements in that section.(3) VEPCO is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of an Alternative GOTHIC Containment Analysis Methodology as set forth in the licensee's application dated October 22, 2007, and as supplemented on November 2, 2007 and November 9, 2007.Q. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (1) Fire fighting response strategy with the following elements: a. Pre-defined coordinated fire response strategy and guidance b. Assessment of mutual aid fire fighting assets c. Designated staging areas for equipment and materials d. Command and control e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
tutu.s,naid uiutu. o           d Olw         o now or hImlaltri efflct; md A.                   Pd,,u Lmua E..*,,
: a. Protection and use of personnel assets b. Communications
The ftwmsb md*             b operv m. WU*. do           W ,,,wW m*ra r bb    kwh ra In amem of     im           M(M4 B.
: c. Minimizing fire spread d. Procedures for implementing integrated fire response strategy e. Identification of readily-available pre-staged equipment f. Training on integrated fire response strategy g. Spent fuel pool mitigation measures (3) Actions to minimize release to include consideration of: a. Water spray scrubbing b. Dose to onsite responders Renewed License No. DPR-32 Amendment No. 256 4. This renewed license is effective as of the date of issuance and shall expire at midnight on May 25, 2032.FOR THE NUCLEAR REGULATORY COMMISSION original signed by: Samuel J. Collins, Director Office of Nuclear Reactor Regulation
AjmrW,~W       No. 256 a.hmby kcaqpomuIn oi riemmed ftm.
The 1...       duopm 1ids   May,inacmiurmec v8a Um Teindm~
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The Elcum. uh. kvWp fWIlyqit nc*n              In acc*i*im with the rqbmpuiu of go.Tudanmin Bpcllalab.
E.     Deisledbyhmnd~msnt 8 F.     Ddek~td bVAmwUantU~I71
: e.     Deltdq   bvAmeuipMsnW H.     Deleted bAmemknr4 2 SalyAW     31   -Rqpat iad saaproveinft SMl. 5 dated Sepotutr 19.
P.m.         8Sup 1   amwb ddt"d May29, 1980, October 9, 1look 1982, 1&wunberIa, 1082. Jamsuy 17,.1984, Fabry 25, 1988, nd Renewmd 1L1ens No._PPR-,,
Amendment _o.256
 
(2) The Updated Final Safety Analysis Report supplement as revised on July 25, October 1, November 4, and December 2, 2002, shall be included in the next scheduled update to the licensee's Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise complies with the requirements in that section.
(3) VEPCO is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of an Alternative GOTHIC Containment Analysis Methodology as set forth in the licensee's application dated October 22, 2007, and as supplemented on November 2, 2007 and November 9, 2007.
Q. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(1) Fire fighting response strategy with the following elements:
: a. Pre-defined coordinated fire response strategy and guidance
: b. Assessment of mutual aid fire fighting assets
: c. Designated staging areas for equipment and materials
: d. Command and control
: e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
: a. Protection and use of personnel assets
: b. Communications
: c. Minimizing fire spread
: d. Procedures for implementing integrated fire response strategy
: e. Identification of readily-available pre-staged equipment
: f. Training on integrated fire response strategy
: g. Spent fuel pool mitigation measures (3) Actions to minimize release to include consideration of:
: a. Water spray scrubbing
: b. Dose to onsite responders Renewed License No. DPR-32 Amendment   No. 256
 
I
: 4. This renewed license is effective as of the date of issuance and shall expire at midnight on May 25, 2032.
FOR THE NUCLEAR REGULATORY COMMISSION original signed by:
Samuel J. Collins, Director Office of Nuclear Reactor Regulation


==Attachment:==
==Attachment:==
Appendix A, Technical Specifications Date of Issuance: March 20, 2003 Renewed License No. DPR-32 Amendment No.      256


Appendix A, Technical Specifications Date of Issuance:
                                        -..
March 20, 2003 I Renewed License No. DPR-32 Amendment No. 256
E.       PW,,IW tO dtihAct wd 10 CFH Pods.a0       Wnd 70, b possaw, bll wmt separoK pUch bjprdidW spechi wduar mulrfab as may be pmduced by gm oparalon of the faety.
-..E. PW,,IW tO dtih Act wd 10 CFH Pods.a0 Wnd 70, b possaw, bll wmt separoK pUch bjprdid W spechi wduar mulrfab as may be pmduced by gm oparalon of the faety...... "W ruum d f au .hal be dmW a tond b at b K uhs on d = idWo=q.IphuolIn l-bfooWrdnho d.nropehf O-1OCFIM-20, --.. ..Section 30.84 of 10 OP' Pail80, Stodn 40.41 of 10C'I-iFled 406 Secd o .54 MA d WMAN of110 r1 Put 50, and Secfot ?0J of 10 OFH Put 70W; uid Is blmat to d ppabs of M Act und f niu, rouwlaftns, and id Vie Cmn aodulon nw or heruulor In affdJand is msject bD the odkda.I pannm. ospucied bhbw.A. ME*= .. -Whe lpmsne I ufti =d to opeu the fAky at aluu,/odle rmaw cam POwur levels Rot 14 excs 35of m9" .pa VWu ptal.The T"fmiW Mmovak coanad In Ap.en rvioud tauqO Mwndment Nc. 255 *8 hereY bumpoqFtd In Mb mewd bone.lbw Owcmae shom "Wrue the fadky In octcdmance whth Th Tocleded C, ,&Bmadu+...  
..... "Wruum d fau              .halbe dmW tond a               bat K uhson  = didWo=
'.. +i.The ilcsiiee 8Wia ma1e calahi repae in am= Si.D.. *, ".., The Ikomfue oahal koop Wily apeading uwdahis Inacoridmnce W& the*requtrnments of the Tadfe Spedkatldomw F. Deleted n4 F. eoleted ,,Arnm irentl m0 .mumadmani 55 a. Deleted byAmn',dnmenI2.W K. Duieted 1ý Amndodienl-22T.ý Renewed Lcense ft VPR V Amendment No, 255 P. Updated Final Safety Analysis Report (1) The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on July 25, 2002, October 1,2002, November 4, 2002, and December 2, 2002 describes certain future inspection activities to be completed before the period of extended operation.
q.IphuolIn l-bfooWrdnho               d.nropehf         O-1OCFIM-20, - -.. ..
The licensee shall complete these activities no later than January 29, 2013, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
Section 30.84 of 10 OP' Pail80, Stodn 40.41 of 10C'I-iFled 406 Secd o         MA WMAN
(2) The Updated Final Safety Analysis Report supplement as revised on July 25, 2002, October 1, 2002, November 4, 2002, and December 2, 2002, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.(3) VEPCO is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of an Alternative GOTHIC Containment Analysis Methodology as set forth in the licensee's application dated October 22, 2007, and as supplemented on November 2, 2007 and November 9, 2007.Q. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (1) Fire fighting response strategy with the following elements: a. Pre-defined coordinated fire response strategy and guidance b. Assessment of mutual aid fire fighting assets c. Designated staging areas for equipment and materials d. Command and control e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
                    .54   d       of110 r1 Put 50, and Secfot ?0J of 10OFH Put70W; uid       Is blmat to                 dppabs  of M Actundf niu, rouwlaftns, and id               Vie Cmn aodulon nw or heruulorInaffdJand ismsject bD the odkda.I pannm.ospucied bhbw.
: a. Protection and use of personnel assets b. Communications
A.       ME*=                         ..                                   -
: c. Minimizing fire spread d. Procedures for implementing integrated fire response strategy e. Identification of readily-available pre-staged equipment f. Training on integrated fire response strategy g. Spent fuel pool mitigation measures Renewed License No. DPR-37 Amendment No. 255 (3) Actions to minimize release to include consideration of: a. Water spray scrubbing b. Dose to onsite responders
Whe lpmsne I ufti =d to opeu the fAky at aluu,/odle rmaw cam POwur levels Rot   14 excs       35of m9" VWu.pa ptal.
: 4. This renewed license is effective as of the date of issuance and shall expire at midnight on January 29, 2033.FOR THE NUCLEAR REGULATORY COMMISSION original signed by: Samuel J. Collins, Director Office of Nuclear Reactor Regulation
The T"fmiW Mmovak coanad InAp.en A,*u' rvioudtauqO Mwndment Nc. 255 *8 hereY bumpoqFtd InMb mewd bone.
lbw Owcmae shom "Wrue the fadky In octcdmance whth Th Tocleded C, ,&Bmadu+...
The ilcsiiee 8Wia'..ma1e calahi+i. repae in am=               Si.
D..
            *,                         "..,
The Ikomfue oahal koop Wily apeading uwdahis Inacoridmnce W&the
            *requtrnments of the Tadfe Spedkatldomw F. Deleted A* endmo*nt                          n4 F.         eoleted ,,Arnmirentl m0       .mumadmani     55
: a. Deleted byAmn',dnmenI2.W K. Duieted 1ý Amndodienl-22T.ý Renewed Lcense ft VPR V Amendment No, 255
 
P. Updated Final Safety Analysis Report (1) The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on July 25, 2002, October 1,2002, November 4, 2002, and December 2, 2002 describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than January 29, 2013, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
(2) The Updated Final Safety Analysis Report supplement as revised on July 25, 2002, October 1, 2002, November 4, 2002, and December 2, 2002, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
(3) VEPCO is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of an Alternative GOTHIC Containment Analysis Methodology as set forth in the licensee's application dated October 22, 2007, and as supplemented on November 2, 2007 and November 9, 2007.
Q. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(1) Fire fighting response strategy with the following elements:
: a. Pre-defined coordinated fire response strategy and guidance
: b. Assessment of mutual aid fire fighting assets
: c. Designated staging areas for equipment and materials
: d. Command and control
: e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
: a. Protection and use of personnel assets
: b. Communications
: c. Minimizing fire spread
: d. Procedures for implementing integrated fire response strategy
: e. Identification of readily-available pre-staged equipment
: f. Training on integrated fire response strategy
: g. Spent fuel pool mitigation measures Renewed License No. DPR-37 Amendment No.     255
 
(3) Actions to minimize release to include consideration of:
: a. Water spray scrubbing
: b. Dose to onsite responders
: 4. This renewed license is effective as of the date of issuance and shall expire at midnight on January 29, 2033.
FOR THE NUCLEAR REGULATORY COMMISSION original signed by:
Samuel J. Collins, Director Office of Nuclear Reactor Regulation


==Attachment:==
==Attachment:==
 
Appendix A, Technical Specifications Date of Issuance: March 20, 2003 Renewed License No. DPR-37 Amendment No. 255}}
Appendix A, Technical Specifications Date of Issuance:
March 20, 2003 Renewed License No. DPR-37 Amendment No. 255}}

Revision as of 01:32, 23 November 2019

Technical Specifications for Surry, Units 1 and 2, Issuance of Amendments Use of Gothic Code for Recirculation Spray System Exigent Circumstances (TAC Nos. MD7033 and MD7034)
ML073230610
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/15/2007
From:
NRC/NRR/ADRO/DORL/LPLII-1
To:
Virginia Electric & Power Co (VEPCO)
Jervey, Richard 301-415-2728
Shared Package
ML073120614 List:
References
TAC MD7033, TAC MD7034
Download: ML073230610 (6)


Text

.3-84.1mwfh MWm~kdimd be 66 10mdh imd kb& .b ow Molcnrum

,.:*cd h ft .mft Commlnf m*umt SU~fl8Io~adCFHPWIO, 8b40l.,4 a~lOcFlR Int,lo IVcF we.

Seaom dM md5Ut 10A0, CIR Put u4Id 1u0b CMA4o, 10 FR Pa7d 71u OWISA4Io A p mof 111Ad and O..

tutu.s,naid uiutu. o d Olw o now or hImlaltri efflct; md A. Pd,,u Lmua E..*,,

The ftwmsb md* b operv m. WU*. do W ,,,wW m*ra r bb kwh ra In amem of im M(M4 B.

AjmrW,~W No. 256 a.hmby kcaqpomuIn oi riemmed ftm.

The 1... duopm 1ids May,inacmiurmec v8a Um Teindm~

C. F10CW 1wImnea dull maik mdbin rpupo Th inaccodrium with ob ruqAiraw T.*iinI qmdkaftbL Glen@0 D.,

The Elcum. uh. kvWp fWIlyqit nc*n In acc*i*im with the rqbmpuiu of go.Tudanmin Bpcllalab.

E. Deisledbyhmnd~msnt 8 F. Ddek~td bVAmwUantU~I71

e. Deltdq bvAmeuipMsnW H. Deleted bAmemknr4 2 SalyAW 31 -Rqpat iad saaproveinft SMl. 5 dated Sepotutr 19.

P.m. 8Sup 1 amwb ddt"d May29, 1980, October 9, 1look 1982, 1&wunberIa, 1082. Jamsuy 17,.1984, Fabry 25, 1988, nd Renewmd 1L1ens No._PPR-,,

Amendment _o.256

(2) The Updated Final Safety Analysis Report supplement as revised on July 25, October 1, November 4, and December 2, 2002, shall be included in the next scheduled update to the licensee's Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise complies with the requirements in that section.

(3) VEPCO is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of an Alternative GOTHIC Containment Analysis Methodology as set forth in the licensee's application dated October 22, 2007, and as supplemented on November 2, 2007 and November 9, 2007.

Q. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(1) Fire fighting response strategy with the following elements:

a. Pre-defined coordinated fire response strategy and guidance
b. Assessment of mutual aid fire fighting assets
c. Designated staging areas for equipment and materials
d. Command and control
e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
a. Protection and use of personnel assets
b. Communications
c. Minimizing fire spread
d. Procedures for implementing integrated fire response strategy
e. Identification of readily-available pre-staged equipment
f. Training on integrated fire response strategy
g. Spent fuel pool mitigation measures (3) Actions to minimize release to include consideration of:
a. Water spray scrubbing
b. Dose to onsite responders Renewed License No. DPR-32 Amendment No. 256

I

4. This renewed license is effective as of the date of issuance and shall expire at midnight on May 25, 2032.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by:

Samuel J. Collins, Director Office of Nuclear Reactor Regulation

Attachment:

Appendix A, Technical Specifications Date of Issuance: March 20, 2003 Renewed License No. DPR-32 Amendment No. 256

-..

E. PW,,IW tO dtihAct wd 10 CFH Pods.a0 Wnd 70, b possaw, bll wmt separoK pUch bjprdidW spechi wduar mulrfab as may be pmduced by gm oparalon of the faety.

..... "Wruum d fau .halbe dmW tond a bat K uhson = didWo=

q.IphuolIn l-bfooWrdnho d.nropehf O-1OCFIM-20, - -.. ..

Section 30.84 of 10 OP' Pail80, Stodn 40.41 of 10C'I-iFled 406 Secd o MA WMAN

.54 d of110 r1 Put 50, and Secfot ?0J of 10OFH Put70W; uid Is blmat to dppabs of M Actundf niu, rouwlaftns, and id Vie Cmn aodulon nw or heruulorInaffdJand ismsject bD the odkda.I pannm.ospucied bhbw.

A. ME*= .. -

Whe lpmsne I ufti =d to opeu the fAky at aluu,/odle rmaw cam POwur levels Rot 14 excs 35of m9" VWu.pa ptal.

The T"fmiW Mmovak coanad InAp.en A,*u' rvioudtauqO Mwndment Nc. 255 *8 hereY bumpoqFtd InMb mewd bone.

lbw Owcmae shom "Wrue the fadky In octcdmance whth Th Tocleded C, ,&Bmadu+...

The ilcsiiee 8Wia'..ma1e calahi+i. repae in am= Si.

D..

  • , "..,

The Ikomfue oahal koop Wily apeading uwdahis Inacoridmnce W&the

  • requtrnments of the Tadfe Spedkatldomw F. Deleted A* endmo*nt n4 F. eoleted ,,Arnmirentl m0 .mumadmani 55
a. Deleted byAmn',dnmenI2.W K. Duieted 1ý Amndodienl-22T.ý Renewed Lcense ft VPR V Amendment No, 255

P. Updated Final Safety Analysis Report (1) The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on July 25, 2002, October 1,2002, November 4, 2002, and December 2, 2002 describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than January 29, 2013, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(2) The Updated Final Safety Analysis Report supplement as revised on July 25, 2002, October 1, 2002, November 4, 2002, and December 2, 2002, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(3) VEPCO is authorized to revise the Updated Final Safety Analysis Report (UFSAR) to allow implementation of an Alternative GOTHIC Containment Analysis Methodology as set forth in the licensee's application dated October 22, 2007, and as supplemented on November 2, 2007 and November 9, 2007.

Q. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(1) Fire fighting response strategy with the following elements:

a. Pre-defined coordinated fire response strategy and guidance
b. Assessment of mutual aid fire fighting assets
c. Designated staging areas for equipment and materials
d. Command and control
e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
a. Protection and use of personnel assets
b. Communications
c. Minimizing fire spread
d. Procedures for implementing integrated fire response strategy
e. Identification of readily-available pre-staged equipment
f. Training on integrated fire response strategy
g. Spent fuel pool mitigation measures Renewed License No. DPR-37 Amendment No. 255

(3) Actions to minimize release to include consideration of:

a. Water spray scrubbing
b. Dose to onsite responders
4. This renewed license is effective as of the date of issuance and shall expire at midnight on January 29, 2033.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by:

Samuel J. Collins, Director Office of Nuclear Reactor Regulation

Attachment:

Appendix A, Technical Specifications Date of Issuance: March 20, 2003 Renewed License No. DPR-37 Amendment No. 255