Similar Documents at Salem |
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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
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- j' Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 Senior Vice President -
Nuclear July 9, 1987 NLR-N87118 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR LICENSE AMENDMENT FACILITY OPERATING LICENSE DPR-70 AND DPR-75 SALEM GENERATING STATION - UNIT NOS. 1 AND 2 In accordance with the Atomic Energy Act of 1954, as amended, and the regulations thereunder, we hereby transmit our request for amendment and our analyses of the changes to Facility Operating Licenses DPR-70 and DPR-75 for the Salem Generating Station Unit Nos. 1 and 2, respectively.
This amendment consists of revised channel descriptions and relay setpoints for the Second Level Undervoltage Protection System.
These changes are necessary to support implementation of final corrective actions developed by Public Service Electric and Gas Company subsequent to the August 26, 1986, false loss of offsite power at Salem Unit No. 2. A check in the amount of $150.00 is enclosed as required by 10 CFR 170.21.
Pursuant to the requirements of 10 CFR 50.91, a copy of. this request for Amendment has been sent to the State of New Jersey, Department of Environmental Protection. This submittal consists of one (1) signed original and thirty-seven (37) copies.
Should there be any questions regarding this matter, please feel free to contact us.
Sincerely,
-8707160003 970709
.--- --------- ',
PDR ADOCK 05000272 .
_fl_ PDR. - .
Attachment
Document Control Desk 2 7-9-87 C Mr. D. c. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628
. -,,~
- - - - - - - - - - - - - - - - - - - - - ----- --- ----- - - ----- - - -- - - - -- - - -
Ref: SGS LCR 87-06 STATE OF NEW JERSEY SS.
COUNTY OF SALEM Corbin A. McNeill, being duly sworn according to law deposes and says:
I am Senior Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated July 9, 1987 , concerning Salem Generating Station License Change Request 87-06, are true to the best of my knowledge, information and belief.
me 1987 LARAINE Y. BEARD Ndtary PuI:P.iic of New Jersey Notary Public of New Jersey My Commission Expires May l, 1991 My Commission expires on - - - - - - - - - - - - - - - - -
l
SECOND LEVEL UNDERVOLTAGE PROTECTION SYSTEM LICENSE CHANGE REQUEST 87-06 DESCRIPTION
- 1. Change Item 7 of Table 3.3-3 as indicated in Attachment 1.
- 2. Change Item 7 of Table 3.3-4 as indicated in Attachment 2.
REASON FOR CHANGE Table 3.3-3 Item 7.a This item is being revised to be consistent with the channel description format used for other items in this Table. This is an editorial change only. No modification is being made to the primary undervoltage protection system.
Table 3.3-3 Item 7.b The second level undervol tage protection system is being redesigned as a result of an event which occurred at Salem Unit No. 2 on August 26, 1986. Immediately following a reactor trip with safety injection, the Unit 2 vital buses began flip-flopping between the No. 21 and 22 Station Power Transformers (SPT) (preferred source of power) until they eventually separated from the offsite power system. The present design provides for the transfer of a vital bus to the alternate SPT whenever the secondary voltage for its designated SPT drops below 91% of rated bus voltage for greater than 10 seconds. This function is controlled by 2 relays on each vital bus. These relays are positioned such that they monitor the secondary voltage of each of the SPT (1 per SPT). In addition to initiating the transfer function these relays provide a transfer permissive signal such that a vital bus can not be transferred unless the alternate SPT has an acceptable secondary voltage. A separate relay monitors vital bus voltage and provides an input to each of the three Safeguards Equipment Controllers (SEC) such that, for a sustained degraded voltage (<91% for
>13 seconds) condition on 2 out of 3 vital buses, all vital buses are separated from the _q_t__f_s_ite __ s_ource- and---sequenced- - ---- - - ---
onto- -the--emergency-source-.---- --
..
This design is unacceptable for the following reasons: 1) the potential exists for damaging safety related motors as a result of frequent starts during flip-flopping of the vital buses between the SPTs, and 2) General Design Criterion (GDC) 17 requires that the connection between the offsite and onsi te power systems be maintained for all expected transients.
As redesigned, the transfer function will be eliminated.
The existing transfer relays will be replaced with relays of similar design but with improved setpoint drift characteristics. These new relays ( 2 per bus) would be connected to operate in parallel with the present vital bus degraded voltage relay. The present vital bus degraded voltage relay will also be replaced with an upgraded relay.
The interface with the SEC would then be reconfigured from its present 2 out of 3 bus design to a 2 out of 3 relay per bus design. A failure analysis (Attachment 3) has been completed for each component in the system and demonstrates that no single failure will result in the creation of an unanalyzed condition. The new configuration: 1) eliminates the possibility of vital bus flip-flopping, 2) provides for the separation of the vital buses from the preferred source on an individual basis only, and 3) satisfies GDC 17 relative to maintaining the connection between the offsite source and the onsite distribution system, as clarified in the following paragraphs.
For this configuration, two situations exist whereby a single vital bus could be separated from its offsite source (SPT) when the offsite source is operating within expected limits. The first *case occurs as a result of a failure of the relay providing the No. 1 input to the affected SEC, coincident with a LOCA signal. This is judged to be acceptable on the following bases: 1) the affected vital bus is automatically loaded onto its emergency source and is available for accident mitigation, 2) the separation occurs only as a result of a failure of the relay providing the No.
1 input to the SEC, and 3) this feature exists as part of the original system design.
The second case occurs as a result of a postulated malfunction of a single SPT such that its secondary output is less than the setpoint of the second level undervoltage system but greater than the setpoint of the primary undervoltage system. This unlikely condition would have to occur for the SPT which is supplying power to two of the three vital buses. For this scenario, the second level undervoltage system would operate as designed such that after 13 seconds the affected buse~ _w_g11ld _be--sepa-r-a-t;;ed--from -
________the--of-fsi-~e- source- -ana.--1oaaecf ___onto the emergency source.
-----
2 I
However, sufficient time exists ( ===10 seconds) between the separation from the preferred source and the sequencing of the bus onto the emergency source, to allow the operation of the primary undervoltage system. The primary undervoltage system would sense a loss of power to the affected buses and, upon completion of its 2 out of 3 bus logic, cause the remaining vital bus (supplied from the alternate SPT) to be separated from the preferred source. This condition has been evaluated and found to be acceptable for the following reasons:
- 1) Expected failure mechanisms for this type of transformer generally result in complete loss of secondary voltage.
- 2) The scenario described above only occurs when two vital buses are being supplied power by the affected transformer. As only one of the two SPTs per unit can be loaded in such a fashion, the probability of an invalid separation occurring is further reduced.
- 3) In the unlikely event that this condition should occur, the bus which is separated from the functioning SPT is loaded onto its emergency source, thereby ensuring its availability in the event of an accident.
It should also be noted that the same scenario would occur if the PSE&G bulk power system is operating below expected limits. However, separation from the offsite source is allowable for this condition.
In addition to the single bus undervoltage feature previously discussed, the Reactor Coolant Pump (RCP) bypass permissive feature is also being retained from the original system design. This feature temporarily bypasses the degraded voltage protection circuitry to allow the starting of a RCP.
Table 3.3-4 Item 7.b This table is being revised to: 1) incorporate the revised trip setpoint for the second level undervoltage protection relays, and 2) to correct the allowable value for second level undervoltage protection. The present Technical Specification allowable value for second level undervoltage protection is in error as it does not reflect an allowance for line loss due to cable length ( ===O. 7%). However, the present trip setpoint for the second level undervoltage protection system (~91%) provides sufficient margin to account for these losses. - --- --
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The new trip setpoint of ~91.6% is based on the results of detailed analyses of the Salem Generating Station electrical distribution system transient response characteristics.
Those analyses indicate that, at the PSE&G bulk power system minimum expected value of 505 kv and for a LOCA on one Salem Unit and a concurrent orderly shutdown of the other Unit, vital bus voltage will recover to a worse case value of
~92.9%. The minimum allowable trip value and trip setpoint are derived using the 90% minimum motor terminal voltage requirement as a starting point, and then applying appropriate allowances as required by R.G. 1.105.
SIGNIFICANT HAZARDS DETERMINATION
- 1) The proposed changes do not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated. The failure analysis provided in Attachment 3 demonstrates that no single failure results in the existence of an unanalyzed condition.
Additionally, the second level undervoltaqe protection system does not provide an input to the Reactor Protection System nor can it cause any one of the incoming 500 Kv sources to be isolated from the Salem Station electrical distribution system. All equipment used in the system will be seismically qualified. Therefore, the probability of occurrence of an accident remains unchanged.
The second level undervoltage system is required to protect against those events (e.g. bulk power system degradation) which result in a degraded voltage at the vital buses but which do not result in a complete loss of voltage. The modified system continues to satisfy this requirement as previously discussed. Additionally, by eliminating the ability to transfer between SPTs, the potential for damage to safety related motors from frequent starts is eliminated.
The increased redundancy in the SEC logic inputs provides greater assurance that the system will perform its intended function. Therefore, the consequences of previously analyzed accidents remain unchanged.
- 2) The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. As demonstrated in Attachment 3, no single failure will result in the existence of an unanalyzed condition. The second level undervol tage system does not provide any input to the Reactor Protection System nor can it cause any one of the incoming 500 KV sources to be isolated from the Salem Station electrical distribution system. The modified design eliminates the possibjJj.~y: __ of---------- --
flip-flopping of the _yj._t_a_l ___ buses---betwe-en____ offsite power
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sources and thereby assures the availability of all safety related equipment.
- 3) The proposed changes do not involve a significant reduction in a margin of safety. The changes to the second level undervoltage system maintain the existing margin of safety by eliminating the transfer between offsite sources, thereby assuring that the integrity of safety related electrical equipment is maintained. The additional redundancy provided in the revised design enhances the overall reliability of the system and further assures that the system function will be completed.
The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (51 FR 7744) of amendments that are not likely to involve significant hazards consideration. The changes to Table 3.3-3 item 7.a are editorial in nature and are made to be consistent with the notation used for Item 7.b and in other sections of the Table. The change to Table 3.3-4, Item 7.b, ALLOWABLE VALUE, is to correct an existing error in the Technical Specifications. As such, these changes are similar to example 2.e(i) contained in the guidance provided.
The changes to Table 3.3-4 item 7.b are similar to those described in example 2. e (ii) in that the new TRIP SETPOINT constitutes a more restrictive requirement than previously included in the Technical Specifications. The changes to Table
- 3. 3-3, Item 7 .b do not conform to any example cited in the guidance, however; these changes have been demonstrated to meet the screening criteria of 10 CFR 50.92. It is therefore concluded that these changes also do not involve a significant hazards consideration.
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