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| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 4
| page count = 4
| project =
| stage = Request
}}
}}


=Text=
=Text=
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------* .-Public Service Electric and Gas Company
Public Service Electric and Gas Company Louis F. Storz                             Public SeNice Electric and Gas Company   P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations LR-N970269 LCR S97-05 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION FOR EXIGENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CHILLED WATER SYSTEM - AUXILIARY BUILDING SUBSYSTEM SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
* Louis F. Storz Public SeNice Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President  
In accordance with 10CFR50.90, on February 11, 1997, Public Service Electric & Gas (PSE&G) Company submitted letter LR-N97087, requesting a revision to the Technical Specifications (TS) for the Salem Generating Station Unit Nos. 1 and 2.                                               In accordance with 10CFR50.9l(b) (1), a copy of this submittal was sent to the State of New Jersey.
-Nuclear Operations LR-N970269 LCR S97-05 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION FOR EXIGENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CHILLED WATER SYSTEM -AUXILIARY BUILDING SUBSYSTEM SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
The proposed TS changes represented the addition of a new Specification 3/4.7.10, "Chilled Water System - Auxiliary Building Subsystem." This change was submitted to address the support function this system provides to other necessary safety systems-.
In accordance with 10CFR50.90, on February 11, 1997, Public Service Electric & Gas (PSE&G) Company submitted letter LR-N97087, requesting a revision to the Technical Specifications (TS) for the Salem Generating Station Unit Nos. 1 and 2. In accordance with 10CFR50.9l(b)
The proposed changes were evaluated in accordance with 10CFR50.9l(a) (1), using the criteria in 10CFR50.92(c) and PSE&G concluded that the request involved no significant hazards considerations.               This letter provides supplemental information relative to the previously requested change.                                     The information provided in this submittal does not impact the significant hazards considerations. Attachment 1 to this letter provides the new proposed TS pages.
(1), a copy of this submittal was sent to the State of New Jersey. The proposed TS changes represented the addition of a new Specification 3/4.7.10, "Chilled Water System -Auxiliary Building Subsystem." This change was submitted to address the support function this system provides to other necessary safety systems-.
The Allowed Outage Times (AOTs) that were included in the original submittal were derived using Probabilistic Safety Assessment (PSA) analyses. A Conditional Core Damage Probability was determined for each combination of equipment unavailable.
The proposed changes were evaluated in accordance with 10CFR50.9l(a)
The PSA analysis supported 38 days for one chiller inoperable and 14 days for one chilled water pump inoper.able.                                       These durations resulted in the equipment unavailability being considered non-risk significant (less than or equal to 1 x 10- 6 ) .                                     The
(1), using the criteria in 10CFR50.92(c) and PSE&G concluded that the request involved no significant hazards considerations.
              ~~::;;~; Z~~~~~:                    this   ~nal ~sis ~);,/ /;:;/~;/~/:/:i:~/11~/~      th the       guidanc~ \l'll     \
This letter provides supplemental information relative to the previously requested change. The information provided in this submittal does not impact the significant hazards considerations.
11::1\. Printed on                                                                       &   1   c *
Attachment 1 to this letter provides the new proposed TS pages. The Allowed Outage Times (AOTs) that were included in the original submittal were derived using Probabilistic Safety Assessment (PSA) analyses.
~ Recycled Paper
A Conditional Core Damage Probability was determined for each combination of equipment unavailable.
_I
The PSA analysis supported 38 days for one chiller inoperable and 14 days for one chilled water pump inoper.able.
 
These durations resulted in the equipment unavailability being considered risk significant (less than or equal to 1 x 10-6). The this th the  
Document Control Desk           2
\ \l'll 11::1\. Printed on & 1 c
* MAY 011991 LR-N970269 provided in the EPRI PSA Applications Guide, EPRI TR-105396, August 1995. Conditional Core Damage Probabilities of less than 1 x 10- 6 are considered to be non-risk significant.
* Recycled Paper _I
The original proposed AOTs were established as 30 days for one chiller inoperable and 14 days for one chilled water pump inoperable. This submittal conservatively decreases the AOTs to 14 days for one chiller inoperable and 7 days for one chilled water pump inoperable. The assumptions used in the original PSA analyses remain valid for these new reduced AOTs. This change to the original request is being submitted based on discussions with NRC staff members regarding the AOTs.
* Document Control Desk LR-N970269 2
Our current policy is to perform a risk analysis prior to a planned entry into a Technical Specification Action Statement.
* MAY 011991 provided in the EPRI PSA Applications Guide, EPRI TR-105396, August 1995. Conditional Core Damage Probabilities of less than 1 x 10-6 are considered to be non-risk significant.
This risk analysis is one of the methods used to comply with Maintenance Rule requirements. The risk analysis includes reviews of redundant system work, other scheduled work, schedule logic, previous work performance, anticipated emergent work, contingencies, plant operating performance, and the resultant safety improvement. The purpose of the risk analysis is to minimize operational vulnerabilities. The revised AOTs, coupled with the risk analysis, provide good assurance that the Chilled Water System will be able to perform its safety function when needed.
The original proposed AOTs were established as 30 days for one chiller inoperable and 14 days for one chilled water pump inoperable.
The Limiting Condition for Operation (LCO) sections of the Technical Specifications are also*being modified. The word "OPERABLE" was inserted, indicating that the chillers and the chilled water pumps are required to be operable for the chilled water system to be operable. Additionally, the LCO sections were reworded for consistency with the Surveillance Requirements sections. This rewording is an editorial change for clarification only.
This submittal conservatively decreases the AOTs to 14 days for one chiller inoperable and 7 days for one chilled water pump inoperable.
The reference to the radiation monitoring signal has been removed from the Bases section. This was an inappropriate reference because the chilled water valves do not receive a direct signal from the radiation monitoring system.
The assumptions used in the original PSA analyses remain valid for these new reduced AOTs. This change to the original request is being submitted based on discussions with NRC staff members regarding the AOTs. Our current policy is to perform a risk analysis prior to a planned entry into a Technical Specification Action Statement.
Should you have any questions regarding this request, we will be pleased to discuss them with you.
This risk analysis is one of the methods used to comply with Maintenance Rule requirements.
Sincerely, 95-4933
The risk analysis includes reviews of redundant system work, other scheduled work, schedule logic, previous work performance, anticipated emergent work, contingencies, plant operating performance, and the resultant safety improvement.
 
The purpose of the risk analysis is to minimize operational vulnerabilities.
i--
The revised AOTs, coupled with the risk analysis, provide good assurance that the Chilled Water System will be able to perform its safety function when needed. The Limiting Condition for Operation (LCO) sections of the Technical Specifications are also*being modified.
Document Control Desk         3 LR-N970269 Affidavit Attachment C   Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24)
The word "OPERABLE" was inserted, indicating that the chillers and the chilled water pumps are required to be operable for the chilled water system to be operable.
USNRC Senior Resident Inspector - Salem Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625
Additionally, the LCO sections were reworded for consistency with the Surveillance Requirements sections.
 
This rewording is an editorial change for clarification only. The reference to the radiation monitoring signal has been removed from the Bases section. This was an inappropriate reference because the chilled water valves do not receive a direct signal from the radiation monitoring system. Should you have any questions regarding this request, we will be pleased to discuss them with you. Sincerely, 95-4933 i--* Document Control Desk LR-N970269 Affidavit Attachment 3 C Mr. H. Miller, Administrator  
STATE OF NEW JERSEY SS.
-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
COUNTY OF SALEM L. F. Storz, being duly sworn according to law deposes and says:
* Mr. L. Olshan, Licensing Project Manager -Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24) USNRC Senior Resident Inspector  
I am Senior Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Units 1 and 2, are true to the best of my knowledge, information and belief.
-Salem Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625
Subscribed and Swor~tJefore me this /ai;   day of     ~ *, 1997 KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission expires on        My Commission Expires April 21, 1998}}
* ** STATE OF NEW JERSEY SS. COUNTY OF SALEM L. F. Storz, being duly sworn according to law deposes and says: I am Senior Vice President  
-Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Units 1 and 2, are true to the best of my knowledge, information and belief. Subscribed this /ai; and me day of *, 1997 My Commission expires on KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission Expires April 21, 1998}}

Latest revision as of 04:15, 3 February 2020

Suppl Info to Util 970211 Application for Amends to Licenses DPR-70 & DPR-75,revising TS for Chilled Water Sys - Auxiliary Bldg Subsystem.Ref to Radiation Monitoring Signal Removed from Bases Section
ML18102B261
Person / Time
Site: Salem  PSEG icon.png
Issue date: 05/01/1997
From: Storz L
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18102B262 List:
References
LCR-S97-05, LCR-S97-5, LR-N970269, NUDOCS 9705070363
Download: ML18102B261 (4)
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Text

Public Service Electric and Gas Company Louis F. Storz Public SeNice Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations LR-N970269 LCR S97-05 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION FOR EXIGENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CHILLED WATER SYSTEM - AUXILIARY BUILDING SUBSYSTEM SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:

In accordance with 10CFR50.90, on February 11, 1997, Public Service Electric & Gas (PSE&G) Company submitted letter LR-N97087, requesting a revision to the Technical Specifications (TS) for the Salem Generating Station Unit Nos. 1 and 2. In accordance with 10CFR50.9l(b) (1), a copy of this submittal was sent to the State of New Jersey.

The proposed TS changes represented the addition of a new Specification 3/4.7.10, "Chilled Water System - Auxiliary Building Subsystem." This change was submitted to address the support function this system provides to other necessary safety systems-.

The proposed changes were evaluated in accordance with 10CFR50.9l(a) (1), using the criteria in 10CFR50.92(c) and PSE&G concluded that the request involved no significant hazards considerations. This letter provides supplemental information relative to the previously requested change. The information provided in this submittal does not impact the significant hazards considerations. Attachment 1 to this letter provides the new proposed TS pages.

The Allowed Outage Times (AOTs) that were included in the original submittal were derived using Probabilistic Safety Assessment (PSA) analyses. A Conditional Core Damage Probability was determined for each combination of equipment unavailable.

The PSA analysis supported 38 days for one chiller inoperable and 14 days for one chilled water pump inoper.able. These durations resulted in the equipment unavailability being considered non-risk significant (less than or equal to 1 x 10- 6 ) . The

~~::;;~; Z~~~~~: this ~nal ~sis ~);,/ /;:;/~;/~/:/:i:~/11~/~ th the guidanc~ \l'll \

11::1\. Printed on & 1 c *

~ Recycled Paper

_I

Document Control Desk 2

  • MAY 011991 LR-N970269 provided in the EPRI PSA Applications Guide, EPRI TR-105396, August 1995. Conditional Core Damage Probabilities of less than 1 x 10- 6 are considered to be non-risk significant.

The original proposed AOTs were established as 30 days for one chiller inoperable and 14 days for one chilled water pump inoperable. This submittal conservatively decreases the AOTs to 14 days for one chiller inoperable and 7 days for one chilled water pump inoperable. The assumptions used in the original PSA analyses remain valid for these new reduced AOTs. This change to the original request is being submitted based on discussions with NRC staff members regarding the AOTs.

Our current policy is to perform a risk analysis prior to a planned entry into a Technical Specification Action Statement.

This risk analysis is one of the methods used to comply with Maintenance Rule requirements. The risk analysis includes reviews of redundant system work, other scheduled work, schedule logic, previous work performance, anticipated emergent work, contingencies, plant operating performance, and the resultant safety improvement. The purpose of the risk analysis is to minimize operational vulnerabilities. The revised AOTs, coupled with the risk analysis, provide good assurance that the Chilled Water System will be able to perform its safety function when needed.

The Limiting Condition for Operation (LCO) sections of the Technical Specifications are also*being modified. The word "OPERABLE" was inserted, indicating that the chillers and the chilled water pumps are required to be operable for the chilled water system to be operable. Additionally, the LCO sections were reworded for consistency with the Surveillance Requirements sections. This rewording is an editorial change for clarification only.

The reference to the radiation monitoring signal has been removed from the Bases section. This was an inappropriate reference because the chilled water valves do not receive a direct signal from the radiation monitoring system.

Should you have any questions regarding this request, we will be pleased to discuss them with you.

Sincerely, 95-4933

i--

Document Control Desk 3 LR-N970269 Affidavit Attachment C Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24)

USNRC Senior Resident Inspector - Salem Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625

STATE OF NEW JERSEY SS.

COUNTY OF SALEM L. F. Storz, being duly sworn according to law deposes and says:

I am Senior Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Units 1 and 2, are true to the best of my knowledge, information and belief.

Subscribed and Swor~tJefore me this /ai; day of ~ *, 1997 KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission expires on My Commission Expires April 21, 1998

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