JAFP-96-0291, Informs of Util Intent to Install Alternate Dhrs at Plant in Advance of Refueling Outage 12,scheduled to Commence in Oct 1996.Info Encl Provides Details of Sys Design & Safety Considerations Pertinent to Sys Installation & Testing: Difference between revisions

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{{#Wiki_filter:o James A. FitzPatrick e                                     Nucle:r P:w;r Plant P.O. Box 41 Lycoming, New York 13093 315-342-3840 A NewYo.rkPower                                                                     yicnee, s. co,,,,
{{#Wiki_filter:o James A. FitzPatrick e
                                        & Authonty                                                                         eiemi ueneger July 26,1996 JAFP-96-0291 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, D. C. 20555
Nucle:r P:w;r Plant P.O. Box 41 Lycoming, New York 13093 315-342-3840 A NewYo.rkPower yicnee, s. co,,,,
& Authonty eiemi ueneger July 26,1996 JAFP-96-0291 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, D. C. 20555


==Subject:==
==Subject:==
Line 24: Line 25:


==References:==
==References:==
: 1.       NYPA Letter JPN-90-042, J. C. Brons to NRC, " Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity", dated May 31,1990
1.
: 2.       NYPA Letter JPN-91-027, R. E. Beedle to NRC, " Request for Additional Information for ' Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity'", dated June 26,1991
NYPA Letter JPN-90-042, J. C. Brons to NRC, " Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity", dated May 31,1990 2.
: 3.       Technical Specification Amendment No.175 for the James A.
NYPA Letter JPN-91-027, R. E. Beedle to NRC, " Request for Additional Information for ' Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity'", dated June 26,1991 3.
FitzPatrick Nuclear Power Plant (and associated Safety Evaluation report), USNRC, dated December 31,1991
Technical Specification Amendment No.175 for the James A.
: 4.       NYPA Report No. JAF-RPT-DHR-02413, " Evaluation of the Decay                     I Heat Removal System" Revision 1, dated July 16,1996                             j
FitzPatrick Nuclear Power Plant (and associated Safety Evaluation report), USNRC, dated December 31,1991 4.
: 5.       10 CFR 50.59 Nuclear Safety Evaluation No. JAF-SE-96-039,
NYPA Report No. JAF-RPT-DHR-02413, " Evaluation of the Decay Heat Removal System" Revision 1, dated July 16,1996 j
                                                                  " Installation and Acceptance Testing of the Decay Heat Removal System", approved July 16,1996
5.
: 6.       10 CFR 50.59 Nuclear Sefety Evaluation No. JAF-SE-96-042, "Use of the Decay Heat Removal System in Various Plant Modes and Configurations", approved July 16,1996
10 CFR 50.59 Nuclear Safety Evaluation No. JAF-SE-96-039,
" Installation and Acceptance Testing of the Decay Heat Removal System", approved July 16,1996 6.
10 CFR 50.59 Nuclear Sefety Evaluation No. JAF-SE-96-042, "Use of the Decay Heat Removal System in Various Plant Modes and Configurations", approved July 16,1996


==Dear Sir:==
==Dear Sir:==
As was discussed with members of the NRC Staff during a meeting held on July 23,1996 l
at the Region I offices, the Authority intends to install an alternate Decay Heat Removal System (DHR) at FitzPatrick in advance of refueling outage 12, scheduled to commence in October of this year. As detailed below, the Authority has reviewed the current licensing h()O' basis for spent fuel pool cooling and determined the installation of the DHR is not in conflict with the technical and safety bases of the facility, and will, in fact, result in a i
significant improvement in overall decay heat removal capability during refueling outages.
9608050003 960726 PDR ADOCK 05000333 P
PDR


As was discussed with members of the NRC Staff during a meeting held on July 23,1996                      l at the Region I offices, the Authority intends to install an alternate Decay Heat Removal System (DHR) at FitzPatrick in advance of refueling outage 12, scheduled to commence in                  ,
i U.S. Nucitar R:gul: tory Commission Attn: Document Control Desk
October of this year. As detailed below, the Authority has reviewed the current licensing            h()O' basis for spent fuel pool cooling and determined the installation of the DHR is not in i                                      conflict with the technical and safety bases of the facility, and will, in fact, result in a significant improvement in overall decay heat removal capability during refueling outages.
9608050003 960726 PDR    ADOCK 05000333 P                          PDR
 
i i
U.S. Nucitar R:gul: tory Commission                                                             !
Attn: Document Control Desk                                                                     I


==Subject:==
==Subject:==
Installation of the (Altemate) Decay Heat Removal System
Installation of the (Altemate) Decay Heat Removal System
(         Page           The Authority's decision to pursue installation of a DHR will allow specific work activities to be performed during refuel outage 12, while providing additional decay heat removal capability above and beyond that provided by the original plant design. An integral part of     1 our evaluation of the feasibility of installing the DHR was performance of a detailed review of the licensing bases for decay heat removal (during refueling outages) in general, and spent fuel pool cooling, in particular. The current licensing bases for decay heat removal spent fuel pool cooling is documented in Reference Nos.1 and 2 in support of (then) proposed expansion of spent fuel pool storage capacity. NRC review and approval of the l         associated Technical Specification change are documented in Reference No. 3. The               j l         Authority's evaluation, documented in Reference No. 4, concluded, in part, installation and operation of the DHR system will: (1) constitute a significant enhancement in decay heat' removal capability, particularly during refueling outages, (2) improve the ability to control
(
,          refueling cavity and spent fuel pool water temperature during refueling operations, (3) l         provide greater flexibility in outage planning. The Authority's evaluation also concluded l         there are no unreviewed safety questions associated with DHR installation and operation and the system can be installed in accordance with our Modification Control Manual and
Page The Authority's decision to pursue installation of a DHR will allow specific work activities to be performed during refuel outage 12, while providing additional decay heat removal capability above and beyond that provided by the original plant design. An integral part of 1
!          evaluated in accordance with 10 CFR 50.59. DHR installation and Modification l         acceptance testing have been evaluated in Reference No. 5 and system operation l         evaluated in Reference No. 6.
our evaluation of the feasibility of installing the DHR was performance of a detailed review of the licensing bases for decay heat removal (during refueling outages) in general, and spent fuel pool cooling, in particular. The current licensing bases for decay heat removal spent fuel pool cooling is documented in Reference Nos.1 and 2 in support of (then) proposed expansion of spent fuel pool storage capacity. NRC review and approval of the l
associated Technical Specification change are documented in Reference No. 3. The j
l Authority's evaluation, documented in Reference No. 4, concluded, in part, installation and operation of the DHR system will: (1) constitute a significant enhancement in decay heat' removal capability, particularly during refueling outages, (2) improve the ability to control refueling cavity and spent fuel pool water temperature during refueling operations, (3) l provide greater flexibility in outage planning. The Authority's evaluation also concluded l
there are no unreviewed safety questions associated with DHR installation and operation and the system can be installed in accordance with our Modification Control Manual and evaluated in accordance with 10 CFR 50.59. DHR installation and Modification l
acceptance testing have been evaluated in Reference No. 5 and system operation l
evaluated in Reference No. 6.
Reference Nos. 4,5, and 6 provide details of the system design and the safety considerations pertinent to system installation, testing, and operation. As detailed in those documents, the DHR is designed to ensure postulated failures of the system would have no adverse effects on safety-related systems and components. The DHR has also been designed to withstand a broad spectrum of postulated component failures while maintaining, with operator action, a heat removal capacity more than four times greater than the existing Fuel Pool Cooling and Cleanup System. The design of the system, coupled with administrative controls specified in Reference No. 6 will ensure redundant means of decay heat removal are maintained during refueling outages (when the DHR is in use).
Reference Nos. 4,5, and 6 provide details of the system design and the safety considerations pertinent to system installation, testing, and operation. As detailed in those documents, the DHR is designed to ensure postulated failures of the system would have no adverse effects on safety-related systems and components. The DHR has also been designed to withstand a broad spectrum of postulated component failures while maintaining, with operator action, a heat removal capacity more than four times greater than the existing Fuel Pool Cooling and Cleanup System. The design of the system, coupled with administrative controls specified in Reference No. 6 will ensure redundant means of decay heat removal are maintained during refueling outages (when the DHR is in use).
As requ'ested during the July 23rd meeting, copies of Reference Nos. 4,5, and 6 are             I attached herewith.                                                                             j If you have any questions, please contact Mr. Arthur Zaremba, Licensing Manager, at (315) 349-6365.
As requ'ested during the July 23rd meeting, copies of Reference Nos. 4,5, and 6 are attached herewith.
j If you have any questions, please contact Mr. Arthur Zaremba, Licensing Manager, at (315) 349-6365.
Very truly yours, l
Very truly yours, l
w
w
    /*t- MICHAEL J. COLOMB Plant Manager MJC:KV: RAP:las cc:     next page
/*t-MICHAEL J. COLOMB Plant Manager MJC:KV: RAP:las cc:
next page


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cc:
.      cc: Rggional Administrator                             l l
Rggional Administrator l
U. S. Nuclear Regulatory Commission                 '
U. S. Nuclear Regulatory Commission 475 Allendale Road l
475 Allendale Road                                 !
King of Prussia, PA 19406 l
l          King of Prussia, PA 19406                           l
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Office of the Resident inspector i
!                                                              1 l
U. S. Nuclear Regulatory Commission P.O. Box 136
Office of the Resident inspector i         U. S. Nuclear Regulatory Commission P.O. Box 136                                       )
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Lycoming, NY 13093                                 l 1
Lycoming, NY 13093 1
l l         Ms. K. Cotton, Acting Project Manager               !
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l          Project Directorate 1-1                             )
Ms. K. Cotton, Acting Project Manager l
Division of Reactor Projects-l/il U. S. Nuclear Regulatory Commission
Project Directorate 1-1 Division of Reactor Projects-l/il U. S. Nuclear Regulatory Commission Mail Stop 14 B2 l
;          Mail Stop 14 B2 l         Washington, DC 20555 Mr. F. William Valentino, President
Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research, l
:          New York State Energy, Research, l           and Development Authority l         2 Rockefeller Plaza Albany, NY 12223-1253 l
and Development Authority l
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Latest revision as of 22:40, 12 December 2024

Informs of Util Intent to Install Alternate Dhrs at Plant in Advance of Refueling Outage 12,scheduled to Commence in Oct 1996.Info Encl Provides Details of Sys Design & Safety Considerations Pertinent to Sys Installation & Testing
ML20116D888
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 07/26/1996
From: Michael Colomb
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20116D890 List:
References
JAFP-96-0291, JAFP-96-291, NUDOCS 9608050003
Download: ML20116D888 (3)
v • d • e


Text

o James A. FitzPatrick e

Nucle:r P:w;r Plant P.O. Box 41 Lycoming, New York 13093 315-342-3840 A NewYo.rkPower yicnee, s. co,,,,

& Authonty eiemi ueneger July 26,1996 JAFP-96-0291 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, D. C. 20555

Subject:

Installation of the (Alternate) Decay Heat Removal System

References:

1.

NYPA Letter JPN-90-042, J. C. Brons to NRC, " Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity", dated May 31,1990 2.

NYPA Letter JPN-91-027, R. E. Beedle to NRC, " Request for Additional Information for ' Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity'", dated June 26,1991 3.

Technical Specification Amendment No.175 for the James A.

FitzPatrick Nuclear Power Plant (and associated Safety Evaluation report), USNRC, dated December 31,1991 4.

NYPA Report No. JAF-RPT-DHR-02413, " Evaluation of the Decay Heat Removal System" Revision 1, dated July 16,1996 j

5.

10 CFR 50.59 Nuclear Safety Evaluation No. JAF-SE-96-039,

" Installation and Acceptance Testing of the Decay Heat Removal System", approved July 16,1996 6.

10 CFR 50.59 Nuclear Sefety Evaluation No. JAF-SE-96-042, "Use of the Decay Heat Removal System in Various Plant Modes and Configurations", approved July 16,1996

Dear Sir:

As was discussed with members of the NRC Staff during a meeting held on July 23,1996 l

at the Region I offices, the Authority intends to install an alternate Decay Heat Removal System (DHR) at FitzPatrick in advance of refueling outage 12, scheduled to commence in October of this year. As detailed below, the Authority has reviewed the current licensing h()O' basis for spent fuel pool cooling and determined the installation of the DHR is not in conflict with the technical and safety bases of the facility, and will, in fact, result in a i

significant improvement in overall decay heat removal capability during refueling outages.

9608050003 960726 PDR ADOCK 05000333 P

PDR

i U.S. Nucitar R:gul: tory Commission Attn: Document Control Desk

Subject:

Installation of the (Altemate) Decay Heat Removal System

(

Page The Authority's decision to pursue installation of a DHR will allow specific work activities to be performed during refuel outage 12, while providing additional decay heat removal capability above and beyond that provided by the original plant design. An integral part of 1

our evaluation of the feasibility of installing the DHR was performance of a detailed review of the licensing bases for decay heat removal (during refueling outages) in general, and spent fuel pool cooling, in particular. The current licensing bases for decay heat removal spent fuel pool cooling is documented in Reference Nos.1 and 2 in support of (then) proposed expansion of spent fuel pool storage capacity. NRC review and approval of the l

associated Technical Specification change are documented in Reference No. 3. The j

l Authority's evaluation, documented in Reference No. 4, concluded, in part, installation and operation of the DHR system will: (1) constitute a significant enhancement in decay heat' removal capability, particularly during refueling outages, (2) improve the ability to control refueling cavity and spent fuel pool water temperature during refueling operations, (3) l provide greater flexibility in outage planning. The Authority's evaluation also concluded l

there are no unreviewed safety questions associated with DHR installation and operation and the system can be installed in accordance with our Modification Control Manual and evaluated in accordance with 10 CFR 50.59. DHR installation and Modification l

acceptance testing have been evaluated in Reference No. 5 and system operation l

evaluated in Reference No. 6.

Reference Nos. 4,5, and 6 provide details of the system design and the safety considerations pertinent to system installation, testing, and operation. As detailed in those documents, the DHR is designed to ensure postulated failures of the system would have no adverse effects on safety-related systems and components. The DHR has also been designed to withstand a broad spectrum of postulated component failures while maintaining, with operator action, a heat removal capacity more than four times greater than the existing Fuel Pool Cooling and Cleanup System. The design of the system, coupled with administrative controls specified in Reference No. 6 will ensure redundant means of decay heat removal are maintained during refueling outages (when the DHR is in use).

As requ'ested during the July 23rd meeting, copies of Reference Nos. 4,5, and 6 are attached herewith.

j If you have any questions, please contact Mr. Arthur Zaremba, Licensing Manager, at (315) 349-6365.

Very truly yours, l

w

/*t-MICHAEL J. COLOMB Plant Manager MJC:KV: RAP:las cc:

next page

cc:

Rggional Administrator l

U. S. Nuclear Regulatory Commission 475 Allendale Road l

King of Prussia, PA 19406 l

\\

1 l

Office of the Resident inspector i

U. S. Nuclear Regulatory Commission P.O. Box 136

)

Lycoming, NY 13093 1

l l

Ms. K. Cotton, Acting Project Manager l

Project Directorate 1-1 Division of Reactor Projects-l/il U. S. Nuclear Regulatory Commission Mail Stop 14 B2 l

Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research, l

and Development Authority l

2 Rockefeller Plaza Albany, NY 12223-1253 l

l l

r i

l l

1 i

e d

I

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