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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
[Table view] |
Text
11 0 PStiG*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New'Jersey 08038 Nuclear Department Ref: LCR 81-19 (Rev. 1)
September 23, 1983 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention: Mr. Steven Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen:
PAGE REVISIONS TO REQUEST FOR AMENDMENT TO FACILITY OPERATING LICENSES DPR-70 AND DPR-75 UNIT NOS. 1 AND 2 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 The attached modifications to the description and safety evaluation sections of our previously submitted amendment request (LCR 81-19) provides additional details and amplifying material. For continuity, unaffected pages from the amendment request are also included so that the entire section can be replaced with the attached pages 1 through 8. Modifications are identified by a vertical line in the right hand margin.
Additionally, a minor change to our Station Operations Review Committee (SORC) composition has been made to reflect the latest membership.
Very truly yours, 8309300269 830923 PDR ADOCK 05000272 p PDR
/ ~
Manager - Nuclear Licensing and Regulation Attachment The Energy People 95-2168 (SOM) 11-82
Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 9/23/83 CC: Mr. Donald C. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection
1.
Ref: LCR 79-01 (Rev. 1)
LCR 81-19 (Rev. 1)
PROPOSED CHANGES TECHNICAL SPECIFICATIONS UNIT NOS. 1 AND 2 DESCRIPTION OF CHANGE The proposed changes contained herein revise two previously submitted amendment requests which incorporated the principles of 10 CFRSO, Appendix I (LCR 79-01) and involved organizational changes in the Administrative Controls section (LCR-81-19).
Additionally, these proposed changes add requirements in the Administrative Controls section concerning overtime limitations, PORV and safety valve challenge/failure reporting and audits.
DISCUSSION OF SPECIFIC REVISIONS Overall Comment - Previous LCR's 79-01 and 81-19, affect many sections of the Technical Specifications. In the interest of continuity and clarity, both units' Administrative Controls sections have been retyped in their entirety to make them, as much as possible, read the same. The INDEX and DEFINITIONS sectiorts.have also been retyped/alphabetized to make them consistent and easier to use.
LCR 79-01 (Rev. 1)
This change revises appropriate sections of the Salem Nuclear Generating Station Technical Specif ictions to incorporate the principles of 10CFR 50, Appendix I. This change also deletes "Part 1-Radiological" of the Environmental Technical Specifications and incorporates the salient items of this section into Appendix A of the Salem Operating License.
Revised License Change Request 79-01 was developed using the guidance provided in NUREG-0472, Rev. 3, and constitutes the PSE&G version of the standard Radiological Effluent Technical Specification (RETS).
LCR 81-19 (Rev. 1) 6.2 ORGANIZATION - The Nuclear Department structure, which resulted from an organizational review of our nuclear operation and support staff, is depicted in the Organization Charts, Figure 6.2.1, CORPORATE HEADQUARTERS AND OFFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT and Figure 6.2.2, FACILITY
Page 2 ORGANIZATION. Title changes and the shifting of functional responsibilities and authority are reflected throughout Section 6.0, Administrative Controls, and are indicated by vertical lines in theright hand margin next to the changes.
6.2.2.f Facility Staff - A statement concerning limitation of overtime has been added in accordance with Generic Letter 82-12.
6.5.1.2 - SORC composition has been modified to add the Safety Review Engineer and adds the Station Planning Engineer vice the Senior Radiaiton Protection Supervisor.
6.5.2.8 Audits - Audit frequencies for the Facility Security Plan and Facility Emergency Plan have been changed from 24 months to 12 months to bring them into conformance with 10CFR50 and 10CFR73 requirements.
6.9.1.6 Monthly Operating Report - Added to the routine monthly operating statistics and shutdown experience, will be a report of all challenges to PORV's or safety valves. ~ailures of the safety valves will be reported under the existing requirements of Section 6.9.1.7 and 6.9.1.8.
REASON FOR CHANGE LCR-79-01 (Rev. 1)
In keeping with USNRC efforts to standardize all nuclear power plant Technical Specifications, PSE&G has been requested to implement the specifications which they developed. An earlier version of this amendment was originally prepared and submitted to the USNRC on November 26, 1979. As a result of the accident at Three Mile Island, the Nuclear Regulatory Commission has not actively reviewed our proposed Effluent Technical Specif ica-tions. The USNRC is now prepared to fully review our submittal and has requested that we resubmit our proposed changes updated with the guidance provided by the USNRC in Revision 3 to NUREG 0472.
LCR 81-19 (Rev. 1)
As a result of the experience gained in the operation and technical support of the Salem units and our continuing desire to improve the efficiency and effectiveness of these functions, a review was performed of the structure and capability of our nuclear operations and support organizations. Considered in detail in this review were the many requirements and
Page 3 recommendations that have come forth from the post-TMI assessment of the nuclear industry, as well as the specific observations made by both NRC and INPO.
The results of this organizational review led to the integration, within a centralized Nuclear Department, of a major portion of PSE&G's nuclear operations and support functions. To improve the dedication and responsiveness of support personnel to plant operations, this new department has been located directly at the Artificial Island site. This action enhances our state of emergency preparedness, and enables us to more effectively satisfy the requirements of NUREG-0654 (Criteria for Preparation and Evaluation of Radiological Emergency Response Plans).
This revision makes several changes and additions that reflect organizational modifications and/or respond to specific NRC requirements that have developed since our original submittal of this LCR.
SAFETY EVALUATIONS LCR 79-01 (Rev. 1)
This proposed amendment to the Salem Nuclear Generating Station Technical Specification incorporates the requirements of Appendix I 10CFRSO and clarifies certain aspects of our exist-ing Environmental Technical Specifications. The changes being proposed in this license change request will not result in any reduction in the levels of safety already provided by the existing technical specifications. The changes being proposed will tend to strengthen many of the surveillance requirements for instrumentation and, in general, will tend to increase the margin of safety already provided. The following is a summary of key changes being proposed, along with our evaluation of why margins of safety have not been reduced:
License to provide specification of the alarm/setpoints for certain effluent radiation monitors.
Current technical specifications for the Salem station do not require that setpoints be provided for effluent channels. This change will require that alarm/trip setpoints be provided in a separate document called an Off-site Dose Calculation Manual.
The setpoints in this document will be reviewed by the USNRC prior to implementation. This change will result in additional surveillance; hence, it will not decrease the margin of safety already provided in the technical specification.
Page 4 Amend license to require several gaseous and liquid process instruments to be operational and in addition required that explosive gas mixtures be continuously monitored.
Gaseous and liquid process instrumenation at the Salem Station will be maintained and operated when necessary to process radioactive waste. Current technical specifications do not clearly specify what action should be taken when radiation monitoring equipment is temporarily unavailable. New technical specifications will clearly specify what actions will be taken. In addition, the technical specifications will call for continuous surveillance of explosive mixtures of hydrogen and oxygen in the gaseous waste holdup system. This change will increase the margin of safety already provided in the technical specifications.
Amend the Salem license to remove curie limitations and replace them by dose limitations.
Curie limitation are no longer required by the USNRC and have been replaced by dose limitation. Expressing environmental impact in units of curies is not sufficient alone to determine off-site environmental impact from radioactive releases. The NRC has recognized that it is more appropriate to express environmental impact in terms of cumulative dose. Operation of radwaste equipment will be based on cumulative dose delivered to man and not upon exceeding a curie limit.
Amend the Salem license to require the maintenance of document called an Offsite Dose Calculation Manual (ODCM).
The creation of a manual called an ODCM will clearly specify how PSE&G will determine radiation dose to the public. This document must also be approved by the USNRC before implementation. The amendment of the Salem license to include this document will not reduce any of the safety margins which currently exist.
We have determined that this change involves no significant hazards consideration in that it would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
Page 5 LCR 81-19 (Rev. 1)
These proposed changes are administrative in nature and have been determined to involve no significant hazards consideration in that they would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
The change to the Station Operations Review Committee reflects the latest membership and adds the Safety Review Engineer. The limitation on overtime, which complies with the guidance of Generic Letter 82-12; the change from a 24 month to a 12 month audit frequency for the Facility Security Plan and Facility Emergency Plan, which conforms to 10CFR 50 and 10CFR 73 requirements; and the reporting of PORV/safety valve challenges/
failures, each incorporate additional limitations and restrictions on the Facility Operating License to improve overall plant safety.
The functions performed by the proposed Nuclear Department organization are the same as were performed by various departments at the plant and corporate headquarters prior to the formation of the new organization. Functional responsibilities and authority levels have been reassigned within the Nuclear Department support organizations to reduce the non-operational workload of plant management while combining these organizations into a single, centralized, integrated structure. Headed by a Vice President as the senior nuclear manager, this organization clearly established the responsiblity for safe and efficient operation of our nuclear facilities. It also provides for unambiguous management control and effective lines of authority and communication between responsible groups involved in the management, technical and administrative support and operation of our nuclear units.
The strength and effectiveness of this organization resides in five key senior management positions providing the overall management direction and control of the Company's nuclear programs. These positions, Vice President - Nuclear, General Manager - Salem Operations, General Manager - Hope Creek Operations, General Manager - Nuclear Support and General Manager
- Nuclear Services are further described below in terms of functional responsibility and authority.
_I
Page 6 Vice President - Nuclear The Vice President - Nuclear is the senior nuclear manager in overall charge of our nuclear programs at Artificial Island, including plant operations and nuclear safety. The General Manager - Salem Operations, General Manager - Hope Creek Operations, the General Manager - Nuclear Support and the General Manager - Nuclear Services report directly to the Vice President - Nuclear. It is expected that the total work force will number approximately 1400 persons by the time of commercial operation of the first unit at Hope Creek. In the event of a nuclear emergency at Artificial Island, the Vice President - Nuclear assumes the role of Emergency Response Manager and takes command and control of all PSE&G on-site and off-site response activities. Additionally, the Vice President -
Nuclear establishes policies on nuclear operations matters within the Company, subject to the advice and consent of senior corporate manangement. Where questions or disagreements arise within the nuclear organization concerning nuclear safety matters, the Vice President - Nuclear Department will establish Company policy. In addition, he has the authority and responsibility to determine when the plants must be shut down to maintain the safety of the facilities.
As the senior nuclear manager in overall charge of Company nuclear programs, the Vice President - Nuclear provides management direction and control for the operation and support activities associated with our nuclear facilities at Artificial Island. This includes the establishment of qualification requirements for management positions which directly support plant operations, the development of goals, objectives andCompany policy relating to the safe and reliable operation of the nuclear units, and implementation of formalized programs, such as security, fire protection, radiation protection, and operator training.
The senior nuclear manager is actively involved in plant operational activities and reviews significant operating deficiencies and violations of Technical Specifications. He monitors the activities of the Nuclear Review Board that perform the independent review function of important matters affecting nuclear operation and safety. Close attention to unanticipated and unusual plant occurrences and review of operational trend analysis by the senior nuclear manager assures that the highest standards affecting plant operations ~re maintained.
Reporting directly to the Vice President - Nuclear is the Manager - Methods and Administration - Nuclear, who is responsible for planning and scheduling, cost control, systems development, computer applications, and coordination of all personnel and administrative functions including payroll, accounting, employment and compensation, and medical services.
Page 7 General Manager - Salem Operations General Manager - Hope Creek Operations The General Manager for each nuclear station is responsible for the safe and efficient operation of the nuclear units and general direction of the Operating, Maintenance, Radiation Protection andTechnical Support Departments. This encompasses a plant staff inexcess of 400 employees. Reporting directly to the station General Manager is an Assistant General Manager, followed by four major station department heads, the Operating Manager, Maintenance Manager, Technical Manager, and Radiation Protection Engineer.
The General Manager is responsible for compliance with all applicable requirements of the NRC Operating License and Technical Specifications, and the prompt reporting of unusual events, deficiences and corrective action implementation. He monitors the activities of the Station Operations Review Committee (SORC), involving evaluations of plant safety related activities. Additionally, he is responsible for assuring that the nuclear station needs for engineering, maintenance and other site support services are identified and can be adequately satisfied by the site support organizations to meet all requirements for safe and reliable plant operation.
The General Manager is responsible for assuring that plant staff positions are maintained by fully qualified and trained personnel. He directs the implementation of a radiation protection program that assures that radiation exposure of plant and support personnel is maintained as low as reasonably achievable. He is also responsible for the approval of operating procedures as required by Technical Specifications and for the development and control of budgets for the operation and maintenance of the station.
General Manager - Nuclear Support The General Manger - Nuclear Support is responsible for providing support to the nuclear stations in the areas of engineering and design, reactor engineering and fuel management, the maintenance of the operating licenses, and review of the investigations conducted by the Safety Review Group. In addition, he provides support for the Nuclear Department concerning public relations, public information, and the operation of the Site Nuclear Information Center.
The station General Manager will direct the General Manager -
Nuclear Support to provide assistance for performance of the required work in these areas of responsibility. The General Manager - Nuclear Support will make the determination of which
Page 8 activities are performed by on-site and/or off-site personnel, and furthermore provide technical direction for all off-site support functions performed in these areas. All off-site communications regarding these areas of responsibility shall be through the Nuclear Support Department.
Reporting directly to the General Manager - Nuclear Support are the Safety Review Group; three department managers responsible for licensing and regulation, nuclear safety and assessment, and fuel cycle; and the Assistant General Manager - Nuclear Engineering who, in turn, directs four additional department managers whose responsibilities include plant systems, engineering and design.
General Manager - Nuclear Services The General Manager - Nuclear Services is responsible for providing technical support to the station organizations in the area of radiation protection; site protection including fire, security and emergency preparedness; training of licensed and non-licensed personnel; in-service inspection and non-destructive examination.
This organization also provides the stations with calibration and instrument repair, radwaste management, and maintenance support services. In addition, he is responsible for material management, warehousing and control of all contractor activities.
The station General Manager will direct the General Manager -
Nuclear Services to provide assistance for performance of the required work in these areas of responsibility. The General Manager - Nuclear Services will make the determination of which activities are performed by on-site and/or _off-site personnel, and furthermore provide technical direction for all off-site support functions performed in these areas. All off-site communications regarding these areas of responsibility shall be through the Nuclear Services Department.
Reporting to the General Manager - Nuclear Services are six department managers who provide services to the two nuclear stations. Under the direction and control of the ~eneral Manager - Nuclear Services, common activities required by both nuclear stations are combined to provide improved utilization of resources and greater control of the identified support functions.
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