|
|
(2 intermediate revisions by the same user not shown) |
Line 19: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:Public Service Electric and Gas Company Corbin A. McNeill, Jr. Vice President | | {{#Wiki_filter: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 Vice President - |
| -Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 Nuclear U.S. Nuclear Regulatory Commission Off ice of Nuclear Reactor Regulation Division of Licensing Washington, D. C. 20555 Attention:
| | Nuclear August 6, 1985 Ref: LCR 85-10 U.S. Nuclear Regulatory Commission Off ice of Nuclear Reactor Regulation Division of Licensing Washington, D. C. 20555 Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen: |
| Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen: | | REQUEST FOR AMENDMENT AND 10CFR50, APPENDIX J EXEMPTION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 UNIT NOS. 1 AND 2 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 Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2. |
| August 6, 1985 Ref: LCR 85-10 REQUEST FOR AMENDMENT AND 10CFR50, APPENDIX J EXEMPTION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 UNIT NOS. 1 AND 2 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 Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2. This amendment request consists of changes to containment air lock testing. Additionally, in accordance with the provisions of lOCFRS0.12, we are requesting exemption from the requirements of lOCFRSO, Appendix J, III D.2(b}(ii}.
| | This amendment request consists of changes to containment air lock testing. |
| | Additionally, in accordance with the provisions of 10CFRS0.12, we are requesting exemption from the requirements of 10CFRSO, Appendix J, III D.2(b}(ii}. |
| In accordance with the fee requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed. | | In accordance with the fee requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed. |
| 8508160370 850806 2 DDR ADOCK 0500027 ' ** PDR p \ I I I Steven A. Varga 8-6-85 Pursuant to the requirements of 10CRF50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below. This submittal includes three (3) signed originals and forty (40) copies. Enclosure C Mr. Donald C. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Mr. Samuel J. Collins, Chief Projects Branch No. 2, DPRP Region 1 Sincerely, Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, N.J. 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801 r Ref: LCR 85-10 EXEMPTION REQUIRED 10CFR50, App. J. STATE OF NEW JERSEY ) ) SS. COUNTY OF SALEM ) Corbin A. McNeill, Jr., 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 letter dated August 6, 1985, concerning our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75, and exemption from the requirements of 10CFR50, Appenidx J, III D.2(b)(ii) are true to the best of my knowledge, information and belief. My Commission expires on I *. *. I PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 Description of Change Ref: LCR 85-10 Change Section 4.6.1.3, Containment Air Lock Surveillance Requirements, to read: a. *By pressurizing the volume between the airlock door gaskets to > 10.0 psig and checking for an extrapolated** | | \ |
| seal leakage rate equal to or less than 0.01 La. 1. After each opening, except when for multiple entries, then at least once per 72 hours. 2. After performing maintenance which could affect the airlock door gaskets sealing capability. | | I 8508160370 850806 2 I DDR ADOCK 0500027 I |
| : 3. Prior to establishing containment integrity, b. By conducting an overall air lock leakage test at design pressure (47.0 psig) and verifying the overall air leakage rate is within its limit: 1. At. least once per six months#. 2. Prior to establishing containment integrity when maintenance that could affect the airlock sealing capability was performed and the maintenance affects components other than the door gaskets,* | | 'p ** PDR |
| and c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time. Reason for Change During the last refueling outage, In-service Inspection personnel became aware of the difference in surveillance requirements for Unit 1 and Unit 2 air locks. Since both units have the same air locks, the surveillance requirements to ensure operability should be the same. This change incorporates ideas from NUREG 0452, clarifies the former paragraph in Unit 2, and imposes more stringent requirements in Unit 1 technical specifications.
| | |
| Standardizing
| | Mr~ Steven A. Varga 8-6-85 Pursuant to the requirements of 10CRF50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below. |
| *. surveillance requirements for both units will decrease confusion when testing the .air locks. Significant Hazards Consideration This change conforms to NUREG 0452, Standard Technical Specifications for Westinghouse Pressurizer Water Reactors.
| | This submittal includes three (3) signed originals and forty (40) copies. |
| Conducting the overall airlock test at least once per six months and after performance of maintenance that could affect the sealing capability does not involve a significant hazard. Opening of the airlock has the potential of altering the sealing of the airlock because of possible damage to the seals. The door operator (hand wheel) shaft seals experience very little alteration as the shafts rotate within packing. History indicates the shaft seals are very effective in maintaining the sealing capability, even with door operation, and a complete test every six months and after maintenance is sufficient to assure operability. | | Sincerely, Enclosure C Mr. Donald C. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Mr. Samuel J. Collins, Chief Projects Branch No. 2, DPRP Region 1 Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, N.J. 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801 |
| Contrary to the shaft seals, the door seals could experience significant alteration when the doors cycle. The alterations occur the knife edges impact the seals. Pressurization of the volume between the seals after each opening, after maintenance which could affect airlock door gasketst and prior to establishing containment integrity, provides the necessary surveillance to ensure the sealing capability. | | |
| of the seals. This change corresponds to examples (i) and (ii) of the guidance provided in Federal Register 14870 by the Commission for Amendments That Are Considered Not Likely To Involve Significant Hazards Considerations. | | r Ref: LCR 85-10 EXEMPTION REQUIRED 10CFR50, App. J. |
| The change to Unit No. 1 constitutes addition of a more stringent surveillance requirement | | STATE OF NEW JERSEY ) |
| [example (ii)] and the change conforms to example (i} for both Salem units in that it is an administrative change that achieves consistency between the Salem Technical Specifications and NUREG 0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors. | | ) SS. |
| Based on the above, we have determined that this change involves no Significant Hazards Consideration. | | COUNTY OF SALEM ) |
| Our request for amendment, above, relies upon an exemption to 10CFR50, Appendix J, III.D.2(b)(ii) to accommodate the requested changes to Technical Specifications. | | Corbin A. McNeill, Jr., being duly sworn according to law deposes and says: |
| The evaluation of No Significant Hazards Consideration for this amendment also provides justification for our request for ab30 1-2}} | | I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated August 6, 1985, concerning our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75, and exemption from the requirements of 10CFR50, Appenidx J, III D.2(b)(ii) are true to the best of my knowledge, information and belief. |
| | My Commission expires on |
| | |
| | ~* |
| | I *. *. |
| | I PROPOSED CHANGE TO Ref: LCR 85-10 TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 Description of Change Change Section 4.6.1.3, Containment Air Lock Surveillance Requirements, to read: |
| | : a. *By pressurizing the volume between the airlock door gaskets to > 10.0 psig and checking for an extrapolated** seal leakage rate equal to or less than 0.01 La. |
| | : 1. After each opening, except when ~sed for multiple entries, then at least once per 72 hours. |
| | : 2. After performing maintenance which could affect the airlock door gaskets sealing capability. |
| | : 3. Prior to establishing containment integrity, |
| | : b. By conducting an overall air lock leakage test at design pressure (47.0 psig) and verifying the overall air leakage rate is within its limit: |
| | : 1. At. least once per six months#. |
| | : 2. Prior to establishing containment integrity when maintenance that could affect the airlock sealing capability was performed and the maintenance affects components other than the door gaskets,* and |
| | : c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time. |
| | Reason for Change During the last refueling outage, In-service Inspection personnel became aware of the difference in surveillance requirements for Unit 1 and Unit 2 air locks. Since both units have the same air locks, the surveillance requirements to ensure operability should be the same. This change incorporates ideas from NUREG 0452, clarifies the former paragraph in Unit 2, and imposes more stringent requirements in Unit 1 technical specifications. Standardizing |
| | |
| | surveillance requirements for both units will decrease confusion when testing the .air locks. |
| | Significant Hazards Consideration This change conforms to NUREG 0452, Standard Technical Specifications for Westinghouse Pressurizer Water Reactors. |
| | Conducting the overall airlock test at least once per six months and after performance of maintenance that could affect the sealing capability does not involve a significant hazard. |
| | Opening of the airlock has the potential of altering the sealing ca~ability of the airlock because of possible damage to the seals. The door operator (hand wheel) shaft seals experience very little alteration as the shafts rotate within packing. History indicates the shaft seals are very effective in maintaining the sealing capability, even with door operation, and a complete test every six months and after maintenance is sufficient to assure operability. |
| | Contrary to the shaft seals, the door seals could experience significant alteration when the doors cycle. The alterations occur ~s the knife edges impact the seals. |
| | Pressurization of the volume between the seals after each opening, after maintenance which could affect airlock door gasketst and prior to establishing containment integrity, provides the necessary surveillance to ensure the sealing capability. of the ~oor seals. |
| | This change corresponds to examples (i) and (ii) of the guidance provided in Federal Register 14870 by the Commission for Amendments That Are Considered Not Likely To Involve Significant Hazards Considerations. The change to Unit No. 1 constitutes addition of a more stringent surveillance requirement [example (ii)] and the change conforms to example (i} for both Salem units in that it is an administrative change that achieves consistency between the Salem Technical Specifications and NUREG 0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors. Based on the above, we have determined that this change involves no Significant Hazards Consideration. |
| | Our request for amendment, above, relies upon an exemption to 10CFR50, Appendix J, III.D.2(b)(ii) to accommodate the requested changes to Technical Specifications. The evaluation of No Significant Hazards Consideration for this amendment also provides justification for our request for exempti~n. |
| | ab30 1-2}} |
Similar Documents at Salem |
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18107A4991999-08-25025 August 1999 Application for Amends to Licenses DPR-70 & DPR-75,proposing to Authorize Licensee to Perform Single Cell Charging of Connected Cells in Operable Class 1E Batteries ML18107A5141999-08-25025 August 1999 Suppl to 971114 Application for Amends to Licenses DPR-70 & DPR-75,deleting Footnotes Added as one-time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Unit 2 ML18107A4631999-07-29029 July 1999 Application for Amends to Licenses DPR-70 & DPR-75,replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4581999-07-23023 July 1999 Application for Amends to Licenses DPR-70 & DPR-75 to Change TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4221999-07-0202 July 1999 Application for Amends to Licenses DPR-70 & DPR-75 to Relocate TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to Ufsar,Iaw GL 95-10 ML18107A3771999-06-10010 June 1999 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.6.1, Containment Integrity, by Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3571999-06-0404 June 1999 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57 Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New,Affiliated Nuclear Generating Company, PSEG Nuclear Llc.Proprietary Encls Withheld ML18107A2081999-04-14014 April 1999 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.9.12, Fhvas, to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,Per NUREG-1431. Page 4 of 4 in Attachment 2 of Incoming Submittal Omitted ML18106B1571999-03-31031 March 1999 Suppl to 990115 Application for Amend to License DPR-70, Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0621999-02-0808 February 1999 Application for Amends to Licenses DPR-70 & DPR-75, Respectively.Proposed Amend Modifies ECCS Subsystems Surveillance Requirement 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0501999-02-0202 February 1999 Application for Amends to Licenses DPR-70 & DPR-75,revising Max Permissible Enrichment of Stored New Fuel Described in TS Section 5.6.1.1.Rept Entitled, Criticality Analysis of Salem Units 1 & 2 Fresh Fuel Racks, Encl ML18106B0221999-01-15015 January 1999 Application for Amend to License DPR-70,proposing one-time Changes to Certain Unit 1 TS Surveillance Requirements for Fuel Cycle 13,currently Scheduled to Begin on 990918 ML18106A9161998-10-12012 October 1998 Application for Amend to License DPR-75,requesting one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10.Basis for Requested Changes,Analysis Supporting No Significant Hazards Determination & Marked Up TS Pages,Encl ML18106A8921998-09-29029 September 1998 Application for Amends to Licenses DPR-72 & DPR-75,modifying TS 3/4.9.4 to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8761998-09-17017 September 1998 Application for Amends to Licenses DPR-70 & DPR-75,modifying TSs 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8351998-08-12012 August 1998 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS for Containment Air Locks for Salem Units 1 & 2 ML18106A7911998-07-30030 July 1998 Application for Amends to Licenses DPR-70 & DPR-75,revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Following Phrase ML18106A4271998-03-26026 March 1998 Application for Amend to License DPR-70,changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A4221998-03-26026 March 1998 Application for Amends to Licenses DPR-70 & DPR-75, Respectively,Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A2521998-01-0808 January 1998 Supplemental Application for Amends to Licenses DPR-70 & DPR-75,respectively Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2111997-12-15015 December 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modifying Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1941997-12-11011 December 1997 Application for Amend to License DPR-70,requesting one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6771997-11-14014 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,providing TS Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6731997-11-14014 November 1997 Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance ML18102B6611997-11-0404 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.8.1 Re EDG & Deleting SR 4.8.1.1.2.d.1,calling for Diesels to Be Subjected to Insp Based on Vendor Recommendations ML18102B6571997-11-0404 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6371997-10-29029 October 1997 Application for Amend to License DPR-75,revising TS 3/4.4.6, Steam Generators, Making One Time Change to Unit 2 SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6411997-10-29029 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.8.1.1.2.d.2 Proposed in Util 960925 Submittal Re EDG Testing ML18102B6471997-10-24024 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6441997-10-24024 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6291997-10-21021 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers in Closed Position ML18102B6181997-10-14014 October 1997 Application for Amend to License DPR-70,modifying Pressure Isolation Valve Lco,Lco Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 ML18102B6061997-10-0606 October 1997 Application for Amend to License DPR-70,changing TS for LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys. ML18102B5551997-08-27027 August 1997 Application for Amends to Licenses DPR-70 & DPR-75,providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, to State That CCW Pumps Required to Be Operable to Meet LCO ML18102B5281997-08-19019 August 1997 Application for Amend to License DPR-75,providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Plant Unit 2 ML18102B5321997-08-18018 August 1997 Application for Amend to License DPR-75,incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies ML18102B4871997-08-0101 August 1997 Application for Amends to Licenses DPR-70 & DPR-75,rewording TS Section 4.2.1 to State That Util Will Adhere to Section 7 Incidental Take Statement Approved by Natl Marine Fisheries Svc ML18102B3041997-05-14014 May 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.7.6.1.d.1 to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & to Reflecting Filter Dp Acceptance Value of Greater than 2.70 Wg ML18102B2611997-05-0101 May 1997 Suppl Info to Util 970211 Application for Amends to Licenses DPR-70 & DPR-75,revising TS for Chilled Water Sys - Auxiliary Bldg Subsystem.Ref to Radiation Monitoring Signal Removed from Bases Section ML18102B2581997-05-0101 May 1997 Application for Amend to License DPR-75,revising TS Section 3/4.7.7 to Reflect Extended Allowed Outage Times & Creating New TS Section 3/4.7.11 to Address Importance of Switchgear & Penetration Area Ventilation Sys ML18102B0071997-04-30030 April 1997 Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger ML18102B2511997-04-28028 April 1997 Submits Suppl to 970131 & 0314 Applications for Amends to Licenses DPR-70 & DPR-75,revising TS on Pressurizer Power Operated Relief Valves.Suppl Issued to State That Conclusion of NSHC Remains Valid ML18102B0221997-04-25025 April 1997 Application for Amends to Licenses DPR-70 & DPR-75, Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2 ML18102A9791997-04-11011 April 1997 Application for Amends to Licenses DPR-70 & DPR-75, Increasing Cw Flow to 2550 Gpm for 31 Day Surveillance Fans Started & Operated in Low Speed ML18102A8951997-03-0404 March 1997 Application for Amends to Licenses DPR-70 & DPR-75,modifying ECCS Surveillance Test Acceptance Criteria for Centrifugal Charging & SI Pumps ML18102A8491997-02-11011 February 1997 Application for Amends to Licenses DPR-70 & DPR-75, Requesting Addition of New TS 3/4.7.10, Chilled Water Sys ML18102A8361997-01-31031 January 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.4.3 to Ensure That Automatic Capability of Power Operated Relief Valve to Relieve Pressure Is Maintained When Valves Are Isolated by Closure of Block Valves ML18102A8021997-01-31031 January 1997 Application for Amends to Licenses DPR-70 & DPR-75, Requesting Rev to TS Re Containment Systems Air Temp to Ensure Representative Average Air Temp Is Measured ML18102A7861997-01-23023 January 1997 Application for Amend to License DPR-75,revising TS Bases 3/4.3.3.1 Re Radiation Monitoring Instrumentation Channel 2R41 ML18102A7361997-01-0707 January 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising Eighteen Month Surveillance Performed to Measure RCS Total Flow Rate to Account for Necessary Plant Conditions for Performing Test in Mode 1 & Current Extended Plant Outages 1999-08-25
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18107A4991999-08-25025 August 1999 Application for Amends to Licenses DPR-70 & DPR-75,proposing to Authorize Licensee to Perform Single Cell Charging of Connected Cells in Operable Class 1E Batteries ML18107A5141999-08-25025 August 1999 Suppl to 971114 Application for Amends to Licenses DPR-70 & DPR-75,deleting Footnotes Added as one-time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Unit 2 ML18107A4631999-07-29029 July 1999 Application for Amends to Licenses DPR-70 & DPR-75,replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4581999-07-23023 July 1999 Application for Amends to Licenses DPR-70 & DPR-75 to Change TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4221999-07-0202 July 1999 Application for Amends to Licenses DPR-70 & DPR-75 to Relocate TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to Ufsar,Iaw GL 95-10 ML18107A3771999-06-10010 June 1999 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.6.1, Containment Integrity, by Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3571999-06-0404 June 1999 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57 Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New,Affiliated Nuclear Generating Company, PSEG Nuclear Llc.Proprietary Encls Withheld ML18107A2081999-04-14014 April 1999 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.9.12, Fhvas, to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,Per NUREG-1431. Page 4 of 4 in Attachment 2 of Incoming Submittal Omitted ML18106B1571999-03-31031 March 1999 Suppl to 990115 Application for Amend to License DPR-70, Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0621999-02-0808 February 1999 Application for Amends to Licenses DPR-70 & DPR-75, Respectively.Proposed Amend Modifies ECCS Subsystems Surveillance Requirement 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0501999-02-0202 February 1999 Application for Amends to Licenses DPR-70 & DPR-75,revising Max Permissible Enrichment of Stored New Fuel Described in TS Section 5.6.1.1.Rept Entitled, Criticality Analysis of Salem Units 1 & 2 Fresh Fuel Racks, Encl ML18106B0221999-01-15015 January 1999 Application for Amend to License DPR-70,proposing one-time Changes to Certain Unit 1 TS Surveillance Requirements for Fuel Cycle 13,currently Scheduled to Begin on 990918 ML18106A9161998-10-12012 October 1998 Application for Amend to License DPR-75,requesting one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10.Basis for Requested Changes,Analysis Supporting No Significant Hazards Determination & Marked Up TS Pages,Encl ML18106A8921998-09-29029 September 1998 Application for Amends to Licenses DPR-72 & DPR-75,modifying TS 3/4.9.4 to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8761998-09-17017 September 1998 Application for Amends to Licenses DPR-70 & DPR-75,modifying TSs 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8351998-08-12012 August 1998 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS for Containment Air Locks for Salem Units 1 & 2 ML18106A7911998-07-30030 July 1998 Application for Amends to Licenses DPR-70 & DPR-75,revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Following Phrase ML18106A4271998-03-26026 March 1998 Application for Amend to License DPR-70,changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A4221998-03-26026 March 1998 Application for Amends to Licenses DPR-70 & DPR-75, Respectively,Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A2521998-01-0808 January 1998 Supplemental Application for Amends to Licenses DPR-70 & DPR-75,respectively Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2111997-12-15015 December 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modifying Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1941997-12-11011 December 1997 Application for Amend to License DPR-70,requesting one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6771997-11-14014 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,providing TS Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6731997-11-14014 November 1997 Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance ML18102B6611997-11-0404 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.8.1 Re EDG & Deleting SR 4.8.1.1.2.d.1,calling for Diesels to Be Subjected to Insp Based on Vendor Recommendations ML18102B6571997-11-0404 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6371997-10-29029 October 1997 Application for Amend to License DPR-75,revising TS 3/4.4.6, Steam Generators, Making One Time Change to Unit 2 SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6411997-10-29029 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.8.1.1.2.d.2 Proposed in Util 960925 Submittal Re EDG Testing ML18102B6471997-10-24024 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6441997-10-24024 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6291997-10-21021 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers in Closed Position ML18102B6181997-10-14014 October 1997 Application for Amend to License DPR-70,modifying Pressure Isolation Valve Lco,Lco Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 ML18102B6061997-10-0606 October 1997 Application for Amend to License DPR-70,changing TS for LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys. ML18102B5551997-08-27027 August 1997 Application for Amends to Licenses DPR-70 & DPR-75,providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, to State That CCW Pumps Required to Be Operable to Meet LCO ML18102B5281997-08-19019 August 1997 Application for Amend to License DPR-75,providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Plant Unit 2 ML18102B5321997-08-18018 August 1997 Application for Amend to License DPR-75,incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies ML18102B4871997-08-0101 August 1997 Application for Amends to Licenses DPR-70 & DPR-75,rewording TS Section 4.2.1 to State That Util Will Adhere to Section 7 Incidental Take Statement Approved by Natl Marine Fisheries Svc ML20148K0841997-06-0404 June 1997 Amends 194 & 177 to Licenses DPR-70 & DPR-75,respectively, Changing TSs 3.4.3 & 3.4.5, Relief Valves, to Ensure That Automatic Capability of PORVs to Relieve Pressure Is Maintained When Valves Are Isolated ML18102B3041997-05-14014 May 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.7.6.1.d.1 to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & to Reflecting Filter Dp Acceptance Value of Greater than 2.70 Wg ML18102B2611997-05-0101 May 1997 Suppl Info to Util 970211 Application for Amends to Licenses DPR-70 & DPR-75,revising TS for Chilled Water Sys - Auxiliary Bldg Subsystem.Ref to Radiation Monitoring Signal Removed from Bases Section ML18102B2581997-05-0101 May 1997 Application for Amend to License DPR-75,revising TS Section 3/4.7.7 to Reflect Extended Allowed Outage Times & Creating New TS Section 3/4.7.11 to Address Importance of Switchgear & Penetration Area Ventilation Sys ML18102B0071997-04-30030 April 1997 Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger ML18102B2511997-04-28028 April 1997 Submits Suppl to 970131 & 0314 Applications for Amends to Licenses DPR-70 & DPR-75,revising TS on Pressurizer Power Operated Relief Valves.Suppl Issued to State That Conclusion of NSHC Remains Valid ML18102B0221997-04-25025 April 1997 Application for Amends to Licenses DPR-70 & DPR-75, Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2 ML18102A9791997-04-11011 April 1997 Application for Amends to Licenses DPR-70 & DPR-75, Increasing Cw Flow to 2550 Gpm for 31 Day Surveillance Fans Started & Operated in Low Speed ML18102A8951997-03-0404 March 1997 Application for Amends to Licenses DPR-70 & DPR-75,modifying ECCS Surveillance Test Acceptance Criteria for Centrifugal Charging & SI Pumps ML18102A8491997-02-11011 February 1997 Application for Amends to Licenses DPR-70 & DPR-75, Requesting Addition of New TS 3/4.7.10, Chilled Water Sys ML18102A8361997-01-31031 January 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.4.3 to Ensure That Automatic Capability of Power Operated Relief Valve to Relieve Pressure Is Maintained When Valves Are Isolated by Closure of Block Valves ML18102A8021997-01-31031 January 1997 Application for Amends to Licenses DPR-70 & DPR-75, Requesting Rev to TS Re Containment Systems Air Temp to Ensure Representative Average Air Temp Is Measured ML18102A7861997-01-23023 January 1997 Application for Amend to License DPR-75,revising TS Bases 3/4.3.3.1 Re Radiation Monitoring Instrumentation Channel 2R41 1999-08-25
[Table view] |
Text
Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 Vice President -
Nuclear August 6, 1985 Ref: LCR 85-10 U.S. Nuclear Regulatory Commission Off ice of Nuclear Reactor Regulation Division of Licensing Washington, D. C. 20555 Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:
REQUEST FOR AMENDMENT AND 10CFR50, APPENDIX J EXEMPTION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 UNIT NOS. 1 AND 2 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 Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2.
This amendment request consists of changes to containment air lock testing.
Additionally, in accordance with the provisions of 10CFRS0.12, we are requesting exemption from the requirements of 10CFRSO, Appendix J, III D.2(b}(ii}.
In accordance with the fee requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed.
\
I 8508160370 850806 2 I DDR ADOCK 0500027 I
'p ** PDR
Mr~ Steven A. Varga 8-6-85 Pursuant to the requirements of 10CRF50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below.
This submittal includes three (3) signed originals and forty (40) copies.
Sincerely, Enclosure C Mr. Donald C. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Mr. Samuel J. Collins, Chief Projects Branch No. 2, DPRP Region 1 Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, N.J. 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801
r Ref: LCR 85-10 EXEMPTION REQUIRED 10CFR50, App. J.
STATE OF NEW JERSEY )
) SS.
COUNTY OF SALEM )
Corbin A. McNeill, Jr., 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 letter dated August 6, 1985, concerning our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75, and exemption from the requirements of 10CFR50, Appenidx J, III D.2(b)(ii) are true to the best of my knowledge, information and belief.
My Commission expires on
~*
I *. *.
I PROPOSED CHANGE TO Ref: LCR 85-10 TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 Description of Change Change Section 4.6.1.3, Containment Air Lock Surveillance Requirements, to read:
- a. *By pressurizing the volume between the airlock door gaskets to > 10.0 psig and checking for an extrapolated** seal leakage rate equal to or less than 0.01 La.
- 1. After each opening, except when ~sed for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- 2. After performing maintenance which could affect the airlock door gaskets sealing capability.
- 3. Prior to establishing containment integrity,
- b. By conducting an overall air lock leakage test at design pressure (47.0 psig) and verifying the overall air leakage rate is within its limit:
- 1. At. least once per six months#.
- 2. Prior to establishing containment integrity when maintenance that could affect the airlock sealing capability was performed and the maintenance affects components other than the door gaskets,* and
- c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
Reason for Change During the last refueling outage, In-service Inspection personnel became aware of the difference in surveillance requirements for Unit 1 and Unit 2 air locks. Since both units have the same air locks, the surveillance requirements to ensure operability should be the same. This change incorporates ideas from NUREG 0452, clarifies the former paragraph in Unit 2, and imposes more stringent requirements in Unit 1 technical specifications. Standardizing
surveillance requirements for both units will decrease confusion when testing the .air locks.
Significant Hazards Consideration This change conforms to NUREG 0452, Standard Technical Specifications for Westinghouse Pressurizer Water Reactors.
Conducting the overall airlock test at least once per six months and after performance of maintenance that could affect the sealing capability does not involve a significant hazard.
Opening of the airlock has the potential of altering the sealing ca~ability of the airlock because of possible damage to the seals. The door operator (hand wheel) shaft seals experience very little alteration as the shafts rotate within packing. History indicates the shaft seals are very effective in maintaining the sealing capability, even with door operation, and a complete test every six months and after maintenance is sufficient to assure operability.
Contrary to the shaft seals, the door seals could experience significant alteration when the doors cycle. The alterations occur ~s the knife edges impact the seals.
Pressurization of the volume between the seals after each opening, after maintenance which could affect airlock door gasketst and prior to establishing containment integrity, provides the necessary surveillance to ensure the sealing capability. of the ~oor seals.
This change corresponds to examples (i) and (ii) of the guidance provided in Federal Register 14870 by the Commission for Amendments That Are Considered Not Likely To Involve Significant Hazards Considerations. The change to Unit No. 1 constitutes addition of a more stringent surveillance requirement [example (ii)] and the change conforms to example (i} for both Salem units in that it is an administrative change that achieves consistency between the Salem Technical Specifications and NUREG 0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors. Based on the above, we have determined that this change involves no Significant Hazards Consideration.
Our request for amendment, above, relies upon an exemption to 10CFR50, Appendix J, III.D.2(b)(ii) to accommodate the requested changes to Technical Specifications. The evaluation of No Significant Hazards Consideration for this amendment also provides justification for our request for exempti~n.
ab30 1-2