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| {{#Wiki_filter:Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department September 19, 1983 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: | | {{#Wiki_filter:PS~G* |
| Mr. Steven Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen: | | Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref: LCR 83-10 LCR 83-11 September 19, 1983 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Steven Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen: |
| REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES DPR-70 AND DPR-75 NO. 1 AND 2 UNITS SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 Ref: LCR 83-10 LCR 83-11 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment and our analyses of the changes to ity Operating License DPR-70 for Salem Generating Station, Unit No. 1 and DPR-75 for Salem Generating Station Unit No. 2. This request proposes to change the allowable time to ize and vent the reactor coolant system through a 3.14 square inch vent path in the event of an inoperable Pressurizer pressure Protection System (LCR 83-10) and to change the method for ensuring closed block valves in the event of inoperable power operated relief/block valves (LCR 83-11). The changes do not involve significant hazards considerations and each change involves consideration of a single safety issue for one unit and is a duplicate for the second unit; therefore, the proposed amendments are deemed to be Class III and Class I Amendments respectively as defined by lOCFR 170.22. A check in the amount of $8,800 will be sent to you under separate cover. Pursuant to the requirements of 10 CFR50.9l(b)(l), a copy of this request for amendment has been sent to the State of New Jersey as indicated below. 8309270293 830919 PDR ADOCK 05000272 P PDR The Energy People 95-21 68 (80 M) 11-82 | | REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES DPR-70 AND DPR-75 NO. 1 AND 2 UNITS SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment and our analyses of the changes to Facil-ity Operating License DPR-70 for Salem Generating Station, Unit No. 1 and DPR-75 for Salem Generating Station Unit No. 2. |
| * Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 9/19/83 This submittal includes three (3) signed originals and forty (40) copies. Very truly yours, Enclosure CC: Mr. Donald C. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector Liden Manager -Nuclear Licensing and Regulation Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, New Jersey 08628 1 STATE OF NEW JERSEY ) ) SS. COUNTY OF SALEM ) RICHARD A. UDERITZ, being duly sworn according to law deposes and says: I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75 dated September 19, 1983, concerning Pressurizer Overpressure Protection System (LCR 83-10) and Pressurizer PORV/Block Valves (LCR 83-11), are true to the best of my knowledge, information and belief. Subscribed and sworn to before me My Commission expires on P'Jtnl**L'-" * * ,.._ _J 1 '* r1 L. \'On ;=:cf-'1-''=""i'
| | This request proposes to change the allowable time to depressur-ize and vent the reactor coolant system through a 3.14 square inch vent path in the event of an inoperable Pressurizer Over-pressure Protection System (LCR 83-10) and to change the method for ensuring closed block valves in the event of inoperable power operated relief/block valves (LCR 83-11). |
| *.-* . *0'--..*, !;,_"-; 1'-* . Notary Public of New | | The changes do not involve significant hazards considerations and each change involves consideration of a single safety issue for one unit and is a duplicate for the second unit; therefore, the proposed amendments are deemed to be Class III and Class I Amendments respectively as defined by 10CFR 170.22. A check in the amount of $8,800 will be sent to you under separate cover. |
| *' i*::y Corrnnissiori
| | Pursuant to the requirements of 10 CFR50.9l(b)(l), a copy of this request for amendment has been sent to the State of New Jersey as indicated below. |
| -, v,,__. iJ * *:iept. I 0, 11'?.'!.'-".
| | 8309270293 830919 PDR ADOCK 05000272 P PDR The Energy People 95-21 68 (80 M) 11-82 |
| PROPOSED LICENSE CHANGE .SALEM GENERATING STATION NO. 1 2 UNITS DOCKET NO. 50-272 AND 50-311 Reactor Coolant System Overpressure Protection System Limiting Condition for Operation Description LCR 83-10 Change the statements in paragraph (a) and (h) of the limiting condition for operation in Technical Specification Sections 3.4.9.3 (Unit 1) and 3.4.10.3 (Unit 2) to read as follows: a *. With one POPS inoperable, either restore the inoperable POPS to OPERABLE status within 7 days or depressurize and vent the RCS through a 3.14 square inch vent(s) within the next 24 maintain the RCS in a vented condition until both POPS have been restored to OPERABLE status. b. With both POPS inoperable, depressurize and vent the RCS through a 3.14 square inch vent(s) within 24 maintain RCS in a vented condition until both POPS have been restored to OPERABLE status. Reason for Change The existing action statements in limiting condtion for operation presently require that the Reactor Coolant System (RCS) be depressurized and vented through a 3.14 square inch vent(s) within 8 hours if both Pressurizer Overpressure Protection System (POPS) relief valves are inoperable or one POPS is inoperable and can not be restored to OPERABLE status within 7 days. Depressurization and venting of the RCS require that the steam bubble in the pressurizer be eliminated, reactor coolant be degassed to eliminate hydrogen buildup and hence possibility of explosion, and the pressurizer power operated relief valves (PORVs) be gagged open to establish the required vent path. The current requirement to depressurize and vent the RCS within 8 hours is not realistic. | | |
| Given the amount of time _it takes to perform each step, the entire sequence of events required to depressurize and vent the RCS could take up to 24 hours. | | Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 9/19/83 1 |
| Safety Evaluation LCR 83-10 Page 2 The Pressurizer Overpressure Protection System (POPS) relief valves are provided to protect the RCS from pressure transients which could exceed the limits of Appendix G to lOCFR Part 50 when one or more RCS cold leg temperature is at or below 312°F. -Either POPS has adequate relieving capacity to protect the RCS from overpressurization as a result of the limiting heat input or mass input cases, namely i) the start of an idle Reactor Coolant Pump (RCP) with the secondary water temperature of the steam generator less than or equal to 50°F above RCS cold leg temperature or ii) the start of a safety injection pump and its injection into the water solid RCS. A number of provisions for prevention of pressure transients below P-.7 (when the RCS temperature is below 312°F) presently exists. Current Specification 3.4.1.3 for stratup (and a RCP that a steam bubble must be established in the pressurizer prior to pump start or the SG/RCS AT be verified to be less than 50°F. Also Technical Specification 3.5.3 allows a maximum of one safety injection pump to remain operable and power to all inoperable safety injection pumps must be removed by racking out the power supply breakers when the RCS temperature is below 350°F. Also the shutdown procedure requires that a steam bubble be maintained in the pressurizer during plant cooldowns.
| | This submittal includes three (3) signed originals and forty (40) copies. |
| | Very truly yours, |
| | ~ |
| | E~ Liden Manager - Nuclear Licensing and Regulation Enclosure 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 380 Scotch Road Trenton, New Jersey 08628 |
| | |
| | STATE OF NEW JERSEY ) |
| | ) SS. |
| | COUNTY OF SALEM ) |
| | RICHARD A. UDERITZ, being duly sworn according to law deposes and says: |
| | I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75 dated September 19, 1983, concerning Pressurizer Overpressure Protection System (LCR 83-10) and Pressurizer PORV/Block Valves (LCR 83-11), are true to the best of my knowledge, information and belief. |
| | Subscribed and sworn to before me P'Jtnl**L'-"r1* *L. \'On ;=:cf-'1-''=""i' *.-* |
| | ,.._ _J 1 |
| | i*::y Notary Public of New tc~:,,~ |
| | Corrnnissiori Exr~ires -, v,,__. ~cy |
| | *0'--..*, !;,_"-; 1'-* |
| | My Commission expires on iJ * *:iept. I 0, 11'?.'!.'-". |
| | |
| | LCR 83-10 PROPOSED LICENSE CHANGE |
| | .SALEM GENERATING STATION NO. 1 ~ND 2 UNITS DOCKET NO. 50-272 AND 50-311 Reactor Coolant System Overpressure Protection System Limiting Condition for Operation Description ~f Ch~nge Change the actio~ statements in paragraph (a) and (h) of the limiting condition for operation in Technical Specification Sections 3.4.9.3 (Unit 1) and 3.4.10.3 (Unit 2) to read as follows: |
| | a * . With one POPS inoperable, either restore the inoperable POPS to OPERABLE status within 7 days or depressurize and vent the RCS through a 3.14 square inch vent(s) within the next 24 hours~ maintain the RCS in a vented condition until both POPS have been restored to OPERABLE status. |
| | : b. With both POPS inoperable, depressurize and vent the RCS through a 3.14 square inch vent(s) within 24 hours~ maintain RCS in a vented condition until both POPS have been restored to OPERABLE status. |
| | Reason for Change The existing action statements in limiting condtion for operation presently require that the Reactor Coolant System (RCS) be depressurized and vented through a 3.14 square inch vent(s) within 8 hours if both Pressurizer Overpressure Protection System (POPS) relief valves are inoperable or one POPS is inoperable and can not be restored to OPERABLE status within 7 days. |
| | Depressurization and venting of the RCS require that the steam bubble in the pressurizer be eliminated, reactor coolant be degassed to eliminate hydrogen buildup and hence possibility of explosion, and the pressurizer power operated relief valves (PORVs) be gagged open to establish the required vent path. The current requirement to depressurize and vent the RCS within 8 hours is not realistic. Given the amount of time _it takes to perform each step, the entire sequence of events required to depressurize and vent the RCS could take up to 24 hours. |
| | |
| | LCR 83-10 Page 2 Safety Evaluation The Pressurizer Overpressure Protection System (POPS) relief valves are provided to protect the RCS from pressure transients which could exceed the limits of Appendix G to 10CFR Part 50 when one or more RCS cold leg temperature is at or below 312°F. |
| | -Either POPS has adequate relieving capacity to protect the RCS from overpressurization as a result of the limiting heat input or mass input cases, namely i) the start of an idle Reactor Coolant Pump (RCP) with the secondary water temperature of the steam generator less than or equal to 50°F above RCS cold leg temperature or ii) the start of a safety injection pump and its injection into the water solid RCS. |
| | A number of provisions for prevention of pressure transients below P-.7 (when the RCS temperature is below 312°F) presently exists. Current Specification 3.4.1.3 for stratup (and joggin~) |
| | a RCP requir~s that a steam bubble must be established in the pressurizer prior to pump start or the SG/RCS AT be verified to be less than 50°F. Also Technical Specification 3.5.3 allows a maximum of one safety injection pump to remain operable and power to all inoperable safety injection pumps must be removed by racking out the power supply breakers when the RCS temperature is below 350°F. Also the shutdown procedure requires that a steam bubble be maintained in the pressurizer during plant cooldowns. |
| The Residual Heat Removal (RHR) System is initiated once the RCS temperature is below 350°F but above 312°F. The RHR system provides relief capacity for which no credit has been taken in the low temperature overpressure analysis. | | The Residual Heat Removal (RHR) System is initiated once the RCS temperature is below 350°F but above 312°F. The RHR system provides relief capacity for which no credit has been taken in the low temperature overpressure analysis. |
| Upon detection that both of the POPS relief v.alves are inoperable, the RCS will be depressurized and a vent path will be established as soon as realistically achievable which could require a time period of up to 24 hours. The intent of the existing Technical Specification to depressurize and vent the RCS upon detection of inoperable POPS relief valves is met and the proposed change does not a substantial safety hazard as the following criteria are fulfilled: | | Upon detection that both of the POPS relief v.alves are inoperable, the RCS will be depressurized and a vent path will be established as soon as realistically achievable which could require a time period of up to 24 hours. The intent of the existing Technical Specification to depressurize and vent the RCS upon detection of inoperable POPS relief valves is met and the proposed change does not involv~ a substantial safety hazard as the following criteria are fulfilled: |
| : a. Probability of ocurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report will not be significantly increased. | | : a. Probability of ocurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report will not be significantly increased. |
| The requested change when approved will. increase the allowable time .period within which the RCS will he depressurized. | | The requested change when approved will. increase the allowable time .period within which the RCS will he depressurized. However, the protective features described above will be available. Depressurization of the RCS will |
| However, the protective features described above will be available. | | |
| Depressurization of the RCS will -------- | | r I |
| r I I I LCR 83-10 Page 3 be initiated and a vent path will be established through a 3.14 square inch opening(s) as soon as realistically achievable (but within 24 hours) so that the maximum RCS pressure will remain below the Appendix G limits. b *. The possibility of .an accident or malfunction of a different type than any evaluated previously in the safety analysis report will not be created. The requested change will only extend the allowable time period required to depressurize and vent the RCS, and does not involve any physical change in design. With the protective procedural and administrative measures, this will not impact the safe operation of any system, component or structure required for safety.* c. The margin of safety as defined in the basis for any Technical Specification is not significantly reduced. A vent opening of greater than or equal to 3.14 square inches has adequate relieving capacity as either POPS relief valves so that the RCS pressure temperatue limits as identified in the bases for the Technical Specification is within the Appendix.G limits. The margin of safety provided by depressurizing and venting the system within 8 hours following the determination that both POPSs are inoperable is not realistically achievahle | | I I |
| *. With the protective measures described above, the margin of safety will not be significantly reduced even when the allowable time period to depressurize and vent RCS is increased to 24 hours.}} | | LCR 83-10 Page 3 be initiated and a vent path will be established through a 3.14 square inch opening(s) as soon as realistically achievable (but within 24 hours) so that the maximum RCS pressure will remain below the Appendix G limits. |
| | b * . The possibility of .an accident or malfunction of a different type than any evaluated previously in the safety analysis report will not be created. |
| | The requested change will only extend the allowable time period required to depressurize and vent the RCS, and does not involve any physical change in design. With the protective procedural and administrative measures, this will not impact the safe operation of any system, component or structure required for safety.* |
| | : c. The margin of safety as defined in the basis for any Technical Specification is not significantly reduced. |
| | A vent opening of greater than or equal to 3.14 square inches has adequate relieving capacity as either POPS relief valves so that the RCS pressure temperatue limits as identified in the bases for the Technical Specification is maint~ined within the Appendix.G limits. The margin of safety provided by depressurizing and venting the system within 8 hours following the determination that both POPSs are inoperable is not realistically achievahle *. With the protective measures described above, the margin of safety will not be significantly reduced even when the allowable time period to depressurize and vent RCS is increased to 24 hours.}} |
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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
PS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref: LCR 83-10 LCR 83-11 September 19, 1983 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Steven Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES DPR-70 AND DPR-75 NO. 1 AND 2 UNITS SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment and our analyses of the changes to Facil-ity Operating License DPR-70 for Salem Generating Station, Unit No. 1 and DPR-75 for Salem Generating Station Unit No. 2.
This request proposes to change the allowable time to depressur-ize and vent the reactor coolant system through a 3.14 square inch vent path in the event of an inoperable Pressurizer Over-pressure Protection System (LCR 83-10) and to change the method for ensuring closed block valves in the event of inoperable power operated relief/block valves (LCR 83-11).
The changes do not involve significant hazards considerations and each change involves consideration of a single safety issue for one unit and is a duplicate for the second unit; therefore, the proposed amendments are deemed to be Class III and Class I Amendments respectively as defined by 10CFR 170.22. A check in the amount of $8,800 will be sent to you under separate cover.
Pursuant to the requirements of 10 CFR50.9l(b)(l), a copy of this request for amendment has been sent to the State of New Jersey as indicated below.
8309270293 830919 PDR ADOCK 05000272 P PDR The Energy People 95-21 68 (80 M) 11-82
Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 9/19/83 1
This submittal includes three (3) signed originals and forty (40) copies.
Very truly yours,
~
E~ Liden Manager - Nuclear Licensing and Regulation Enclosure 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 380 Scotch Road Trenton, New Jersey 08628
STATE OF NEW JERSEY )
) SS.
COUNTY OF SALEM )
RICHARD A. UDERITZ, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75 dated September 19, 1983, concerning Pressurizer Overpressure Protection System (LCR 83-10) and Pressurizer PORV/Block Valves (LCR 83-11), are true to the best of my knowledge, information and belief.
Subscribed and sworn to before me P'Jtnl**L'-"r1* *L. \'On ;=:cf-'1-=""i' *.-*
,.._ _J 1
i*::y Notary Public of New tc~:,,~
Corrnnissiori Exr~ires -, v,,__. ~cy
My Commission expires on iJ * *:iept. I 0, 11'?.'!.'-".
LCR 83-10 PROPOSED LICENSE CHANGE
.SALEM GENERATING STATION NO. 1 ~ND 2 UNITS DOCKET NO. 50-272 AND 50-311 Reactor Coolant System Overpressure Protection System Limiting Condition for Operation Description ~f Ch~nge Change the actio~ statements in paragraph (a) and (h) of the limiting condition for operation in Technical Specification Sections 3.4.9.3 (Unit 1) and 3.4.10.3 (Unit 2) to read as follows:
a * . With one POPS inoperable, either restore the inoperable POPS to OPERABLE status within 7 days or depressurize and vent the RCS through a 3.14 square inch vent(s) within the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s~ maintain the RCS in a vented condition until both POPS have been restored to OPERABLE status.
- b. With both POPS inoperable, depressurize and vent the RCS through a 3.14 square inch vent(s) within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s~ maintain RCS in a vented condition until both POPS have been restored to OPERABLE status.
Reason for Change The existing action statements in limiting condtion for operation presently require that the Reactor Coolant System (RCS) be depressurized and vented through a 3.14 square inch vent(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if both Pressurizer Overpressure Protection System (POPS) relief valves are inoperable or one POPS is inoperable and can not be restored to OPERABLE status within 7 days.
Depressurization and venting of the RCS require that the steam bubble in the pressurizer be eliminated, reactor coolant be degassed to eliminate hydrogen buildup and hence possibility of explosion, and the pressurizer power operated relief valves (PORVs) be gagged open to establish the required vent path. The current requirement to depressurize and vent the RCS within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is not realistic. Given the amount of time _it takes to perform each step, the entire sequence of events required to depressurize and vent the RCS could take up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
LCR 83-10 Page 2 Safety Evaluation The Pressurizer Overpressure Protection System (POPS) relief valves are provided to protect the RCS from pressure transients which could exceed the limits of Appendix G to 10CFR Part 50 when one or more RCS cold leg temperature is at or below 312°F.
-Either POPS has adequate relieving capacity to protect the RCS from overpressurization as a result of the limiting heat input or mass input cases, namely i) the start of an idle Reactor Coolant Pump (RCP) with the secondary water temperature of the steam generator less than or equal to 50°F above RCS cold leg temperature or ii) the start of a safety injection pump and its injection into the water solid RCS.
A number of provisions for prevention of pressure transients below P-.7 (when the RCS temperature is below 312°F) presently exists. Current Specification 3.4.1.3 for stratup (and joggin~)
a RCP requir~s that a steam bubble must be established in the pressurizer prior to pump start or the SG/RCS AT be verified to be less than 50°F. Also Technical Specification 3.5.3 allows a maximum of one safety injection pump to remain operable and power to all inoperable safety injection pumps must be removed by racking out the power supply breakers when the RCS temperature is below 350°F. Also the shutdown procedure requires that a steam bubble be maintained in the pressurizer during plant cooldowns.
The Residual Heat Removal (RHR) System is initiated once the RCS temperature is below 350°F but above 312°F. The RHR system provides relief capacity for which no credit has been taken in the low temperature overpressure analysis.
Upon detection that both of the POPS relief v.alves are inoperable, the RCS will be depressurized and a vent path will be established as soon as realistically achievable which could require a time period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The intent of the existing Technical Specification to depressurize and vent the RCS upon detection of inoperable POPS relief valves is met and the proposed change does not involv~ a substantial safety hazard as the following criteria are fulfilled:
- a. Probability of ocurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report will not be significantly increased.
The requested change when approved will. increase the allowable time .period within which the RCS will he depressurized. However, the protective features described above will be available. Depressurization of the RCS will
r I
I I
LCR 83-10 Page 3 be initiated and a vent path will be established through a 3.14 square inch opening(s) as soon as realistically achievable (but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) so that the maximum RCS pressure will remain below the Appendix G limits.
b * . The possibility of .an accident or malfunction of a different type than any evaluated previously in the safety analysis report will not be created.
The requested change will only extend the allowable time period required to depressurize and vent the RCS, and does not involve any physical change in design. With the protective procedural and administrative measures, this will not impact the safe operation of any system, component or structure required for safety.*
- c. The margin of safety as defined in the basis for any Technical Specification is not significantly reduced.
A vent opening of greater than or equal to 3.14 square inches has adequate relieving capacity as either POPS relief valves so that the RCS pressure temperatue limits as identified in the bases for the Technical Specification is maint~ined within the Appendix.G limits. The margin of safety provided by depressurizing and venting the system within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following the determination that both POPSs are inoperable is not realistically achievahle *. With the protective measures described above, the margin of safety will not be significantly reduced even when the allowable time period to depressurize and vent RCS is increased to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.