|
|
| (3 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 05/01/1997 | | | issue date = 05/01/1997 |
| | title = 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 | | | title = 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 |
| | author name = STORZ L F | | | author name = Storz L |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
| Line 14: |
Line 14: |
| | 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= |
| {{#Wiki_filter:------------------ | | {{#Wiki_filter:* |
| ------* .-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}} | |
Similar Documents at Salem |
|---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18107A4991999-08-25025 August 1999
Application for Amends to Licenses DPR-70 & DPR-75,proposing to Authorize Licensee to Perform Single Cell Charging of Connected Cells in Operable Class 1E Batteries
ML18107A5141999-08-25025 August 1999
Suppl to 971114 Application for Amends to Licenses DPR-70 & DPR-75,deleting Footnotes Added as one-time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Unit 2
ML18107A4631999-07-29029 July 1999
Application for Amends to Licenses DPR-70 & DPR-75,replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
ML18107A4581999-07-23023 July 1999
Application for Amends to Licenses DPR-70 & DPR-75 to Change TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown
ML18107A4221999-07-0202 July 1999
Application for Amends to Licenses DPR-70 & DPR-75 to Relocate TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to Ufsar,Iaw GL 95-10
ML18107A3771999-06-10010 June 1999
Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.6.1, Containment Integrity, by Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
ML18107A3571999-06-0404 June 1999
Application for Amends to Licenses DPR-70,DPR-75 & NPF-57 Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New,Affiliated Nuclear Generating Company, PSEG Nuclear Llc.Proprietary Encls Withheld
ML18107A2081999-04-14014 April 1999
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.9.12, Fhvas, to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,Per NUREG-1431. Page 4 of 4 in Attachment 2 of Incoming Submittal Omitted
ML18106B1571999-03-31031 March 1999
Suppl to 990115 Application for Amend to License DPR-70, Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918
ML18106B0621999-02-0808 February 1999
Application for Amends to Licenses DPR-70 & DPR-75, Respectively.Proposed Amend Modifies ECCS Subsystems Surveillance Requirement 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing
ML18106B0501999-02-0202 February 1999
Application for Amends to Licenses DPR-70 & DPR-75,revising Max Permissible Enrichment of Stored New Fuel Described in TS Section 5.6.1.1.Rept Entitled, Criticality Analysis of Salem Units 1 & 2 Fresh Fuel Racks, Encl
ML18106B0221999-01-15015 January 1999
Application for Amend to License DPR-70,proposing one-time Changes to Certain Unit 1 TS Surveillance Requirements for Fuel Cycle 13,currently Scheduled to Begin on 990918
ML18106A9161998-10-12012 October 1998
Application for Amend to License DPR-75,requesting one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10.Basis for Requested Changes,Analysis Supporting No Significant Hazards Determination & Marked Up TS Pages,Encl
ML18106A8921998-09-29029 September 1998
Application for Amends to Licenses DPR-72 & DPR-75,modifying TS 3/4.9.4 to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch
ML18106A8761998-09-17017 September 1998
Application for Amends to Licenses DPR-70 & DPR-75,modifying TSs 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity
ML18106A8351998-08-12012 August 1998
Application for Amends to Licenses DPR-70 & DPR-75,modifying TS for Containment Air Locks for Salem Units 1 & 2
ML18106A7911998-07-30030 July 1998
Application for Amends to Licenses DPR-70 & DPR-75,revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Following Phrase
ML18106A4271998-03-26026 March 1998
Application for Amend to License DPR-70,changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A4221998-03-26026 March 1998
Application for Amends to Licenses DPR-70 & DPR-75, Respectively,Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters.
ML18106A2521998-01-0808 January 1998
Supplemental Application for Amends to Licenses DPR-70 & DPR-75,respectively Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page
ML18106A2111997-12-15015 December 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modifying Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1941997-12-11011 December 1997
Application for Amend to License DPR-70,requesting one-time Exemption to Allow Containment Purging in Modes 3 & 4
ML18102B6771997-11-14014 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,providing TS Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels
ML18102B6731997-11-14014 November 1997
Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance
ML18102B6611997-11-0404 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.8.1 Re EDG & Deleting SR 4.8.1.1.2.d.1,calling for Diesels to Be Subjected to Insp Based on Vendor Recommendations
ML18102B6571997-11-0404 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid
ML18102B6371997-10-29029 October 1997
Application for Amend to License DPR-75,revising TS 3/4.4.6, Steam Generators, Making One Time Change to Unit 2 SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6411997-10-29029 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.8.1.1.2.d.2 Proposed in Util 960925 Submittal Re EDG Testing
ML18102B6471997-10-24024 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases
ML18102B6441997-10-24024 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
ML18102B6291997-10-21021 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers in Closed Position
ML18102B6181997-10-14014 October 1997
Application for Amend to License DPR-70,modifying Pressure Isolation Valve Lco,Lco Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2
ML18102B6061997-10-0606 October 1997
Application for Amend to License DPR-70,changing TS for LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys.
ML18102B5551997-08-27027 August 1997
Application for Amends to Licenses DPR-70 & DPR-75,providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, to State That CCW Pumps Required to Be Operable to Meet LCO
ML18102B5281997-08-19019 August 1997
Application for Amend to License DPR-75,providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Plant Unit 2
ML18102B5321997-08-18018 August 1997
Application for Amend to License DPR-75,incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies
ML18102B4871997-08-0101 August 1997
Application for Amends to Licenses DPR-70 & DPR-75,rewording TS Section 4.2.1 to State That Util Will Adhere to Section 7 Incidental Take Statement Approved by Natl Marine Fisheries Svc
ML18102B3041997-05-14014 May 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.7.6.1.d.1 to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & to Reflecting Filter Dp Acceptance Value of Greater than 2.70 Wg
ML18102B2611997-05-0101 May 1997
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
ML18102B2581997-05-0101 May 1997
Application for Amend to License DPR-75,revising TS Section 3/4.7.7 to Reflect Extended Allowed Outage Times & Creating New TS Section 3/4.7.11 to Address Importance of Switchgear & Penetration Area Ventilation Sys
ML18102B0071997-04-30030 April 1997
Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger
ML18102B2511997-04-28028 April 1997
Submits Suppl to 970131 & 0314 Applications for Amends to Licenses DPR-70 & DPR-75,revising TS on Pressurizer Power Operated Relief Valves.Suppl Issued to State That Conclusion of NSHC Remains Valid
ML18102B0221997-04-25025 April 1997
Application for Amends to Licenses DPR-70 & DPR-75, Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2
ML18102A9791997-04-11011 April 1997
Application for Amends to Licenses DPR-70 & DPR-75, Increasing Cw Flow to 2550 Gpm for 31 Day Surveillance Fans Started & Operated in Low Speed
ML18102A8951997-03-0404 March 1997
Application for Amends to Licenses DPR-70 & DPR-75,modifying ECCS Surveillance Test Acceptance Criteria for Centrifugal Charging & SI Pumps
ML18102A8491997-02-11011 February 1997
Application for Amends to Licenses DPR-70 & DPR-75, Requesting Addition of New TS 3/4.7.10, Chilled Water Sys
ML18102A8361997-01-31031 January 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.4.3 to Ensure That Automatic Capability of Power Operated Relief Valve to Relieve Pressure Is Maintained When Valves Are Isolated by Closure of Block Valves
ML18102A8021997-01-31031 January 1997
Application for Amends to Licenses DPR-70 & DPR-75, Requesting Rev to TS Re Containment Systems Air Temp to Ensure Representative Average Air Temp Is Measured
ML18102A7861997-01-23023 January 1997
Application for Amend to License DPR-75,revising TS Bases 3/4.3.3.1 Re Radiation Monitoring Instrumentation Channel 2R41
ML18102A7361997-01-0707 January 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising Eighteen Month Surveillance Performed to Measure RCS Total Flow Rate to Account for Necessary Plant Conditions for Performing Test in Mode 1 & Current Extended Plant Outages
1999-08-25
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18107A4991999-08-25025 August 1999
Application for Amends to Licenses DPR-70 & DPR-75,proposing to Authorize Licensee to Perform Single Cell Charging of Connected Cells in Operable Class 1E Batteries
ML18107A5141999-08-25025 August 1999
Suppl to 971114 Application for Amends to Licenses DPR-70 & DPR-75,deleting Footnotes Added as one-time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Unit 2
ML18107A4631999-07-29029 July 1999
Application for Amends to Licenses DPR-70 & DPR-75,replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
ML18107A4581999-07-23023 July 1999
Application for Amends to Licenses DPR-70 & DPR-75 to Change TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown
ML18107A4221999-07-0202 July 1999
Application for Amends to Licenses DPR-70 & DPR-75 to Relocate TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to Ufsar,Iaw GL 95-10
ML18107A3771999-06-10010 June 1999
Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.6.1, Containment Integrity, by Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
ML18107A3571999-06-0404 June 1999
Application for Amends to Licenses DPR-70,DPR-75 & NPF-57 Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New,Affiliated Nuclear Generating Company, PSEG Nuclear Llc.Proprietary Encls Withheld
ML18107A2081999-04-14014 April 1999
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.9.12, Fhvas, to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,Per NUREG-1431. Page 4 of 4 in Attachment 2 of Incoming Submittal Omitted
ML18106B1571999-03-31031 March 1999
Suppl to 990115 Application for Amend to License DPR-70, Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918
ML18106B0621999-02-0808 February 1999
Application for Amends to Licenses DPR-70 & DPR-75, Respectively.Proposed Amend Modifies ECCS Subsystems Surveillance Requirement 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing
ML18106B0501999-02-0202 February 1999
Application for Amends to Licenses DPR-70 & DPR-75,revising Max Permissible Enrichment of Stored New Fuel Described in TS Section 5.6.1.1.Rept Entitled, Criticality Analysis of Salem Units 1 & 2 Fresh Fuel Racks, Encl
ML18106B0221999-01-15015 January 1999
Application for Amend to License DPR-70,proposing one-time Changes to Certain Unit 1 TS Surveillance Requirements for Fuel Cycle 13,currently Scheduled to Begin on 990918
ML18106A9161998-10-12012 October 1998
Application for Amend to License DPR-75,requesting one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10.Basis for Requested Changes,Analysis Supporting No Significant Hazards Determination & Marked Up TS Pages,Encl
ML18106A8921998-09-29029 September 1998
Application for Amends to Licenses DPR-72 & DPR-75,modifying TS 3/4.9.4 to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch
ML18106A8761998-09-17017 September 1998
Application for Amends to Licenses DPR-70 & DPR-75,modifying TSs 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity
ML18106A8351998-08-12012 August 1998
Application for Amends to Licenses DPR-70 & DPR-75,modifying TS for Containment Air Locks for Salem Units 1 & 2
ML18106A7911998-07-30030 July 1998
Application for Amends to Licenses DPR-70 & DPR-75,revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Following Phrase
ML18106A4271998-03-26026 March 1998
Application for Amend to License DPR-70,changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A4221998-03-26026 March 1998
Application for Amends to Licenses DPR-70 & DPR-75, Respectively,Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters.
ML18106A2521998-01-0808 January 1998
Supplemental Application for Amends to Licenses DPR-70 & DPR-75,respectively Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page
ML18106A2111997-12-15015 December 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modifying Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1941997-12-11011 December 1997
Application for Amend to License DPR-70,requesting one-time Exemption to Allow Containment Purging in Modes 3 & 4
ML18102B6771997-11-14014 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,providing TS Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels
ML18102B6731997-11-14014 November 1997
Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance
ML18102B6611997-11-0404 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.8.1 Re EDG & Deleting SR 4.8.1.1.2.d.1,calling for Diesels to Be Subjected to Insp Based on Vendor Recommendations
ML18102B6571997-11-0404 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid
ML18102B6371997-10-29029 October 1997
Application for Amend to License DPR-75,revising TS 3/4.4.6, Steam Generators, Making One Time Change to Unit 2 SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6411997-10-29029 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.8.1.1.2.d.2 Proposed in Util 960925 Submittal Re EDG Testing
ML18102B6471997-10-24024 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases
ML18102B6441997-10-24024 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
ML18102B6291997-10-21021 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers in Closed Position
ML18102B6181997-10-14014 October 1997
Application for Amend to License DPR-70,modifying Pressure Isolation Valve Lco,Lco Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2
ML18102B6061997-10-0606 October 1997
Application for Amend to License DPR-70,changing TS for LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys.
ML18102B5551997-08-27027 August 1997
Application for Amends to Licenses DPR-70 & DPR-75,providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, to State That CCW Pumps Required to Be Operable to Meet LCO
ML18102B5281997-08-19019 August 1997
Application for Amend to License DPR-75,providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Plant Unit 2
ML18102B5321997-08-18018 August 1997
Application for Amend to License DPR-75,incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies
ML18102B4871997-08-0101 August 1997
Application for Amends to Licenses DPR-70 & DPR-75,rewording TS Section 4.2.1 to State That Util Will Adhere to Section 7 Incidental Take Statement Approved by Natl Marine Fisheries Svc
ML20148K0841997-06-0404 June 1997
Amends 194 & 177 to Licenses DPR-70 & DPR-75,respectively, Changing TSs 3.4.3 & 3.4.5, Relief Valves, to Ensure That Automatic Capability of PORVs to Relieve Pressure Is Maintained When Valves Are Isolated
ML18102B3041997-05-14014 May 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.7.6.1.d.1 to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & to Reflecting Filter Dp Acceptance Value of Greater than 2.70 Wg
ML18102B2611997-05-0101 May 1997
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
ML18102B2581997-05-0101 May 1997
Application for Amend to License DPR-75,revising TS Section 3/4.7.7 to Reflect Extended Allowed Outage Times & Creating New TS Section 3/4.7.11 to Address Importance of Switchgear & Penetration Area Ventilation Sys
ML18102B0071997-04-30030 April 1997
Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger
ML18102B2511997-04-28028 April 1997
Submits Suppl to 970131 & 0314 Applications for Amends to Licenses DPR-70 & DPR-75,revising TS on Pressurizer Power Operated Relief Valves.Suppl Issued to State That Conclusion of NSHC Remains Valid
ML18102B0221997-04-25025 April 1997
Application for Amends to Licenses DPR-70 & DPR-75, Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2
ML18102A9791997-04-11011 April 1997
Application for Amends to Licenses DPR-70 & DPR-75, Increasing Cw Flow to 2550 Gpm for 31 Day Surveillance Fans Started & Operated in Low Speed
ML18102A8951997-03-0404 March 1997
Application for Amends to Licenses DPR-70 & DPR-75,modifying ECCS Surveillance Test Acceptance Criteria for Centrifugal Charging & SI Pumps
ML18102A8491997-02-11011 February 1997
Application for Amends to Licenses DPR-70 & DPR-75, Requesting Addition of New TS 3/4.7.10, Chilled Water Sys
ML18102A8361997-01-31031 January 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.4.3 to Ensure That Automatic Capability of Power Operated Relief Valve to Relieve Pressure Is Maintained When Valves Are Isolated by Closure of Block Valves
ML18102A8021997-01-31031 January 1997
Application for Amends to Licenses DPR-70 & DPR-75, Requesting Rev to TS Re Containment Systems Air Temp to Ensure Representative Average Air Temp Is Measured
ML18102A7861997-01-23023 January 1997
Application for Amend to License DPR-75,revising TS Bases 3/4.3.3.1 Re Radiation Monitoring Instrumentation Channel 2R41
1999-08-25
[Table view] |
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
