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| {{#Wiki_filter:,\-Public Service Electric and Gas Company Corbin A. McNeill, Jr. Vice President | | {{#Wiki_filter:,\- |
| -Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Nuclear August 29, 1986 NLR-N86110 Ref : LCR 8 6 -0 1 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
| | Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Vice President - |
| Mr. Steven A. Varga, Director Project Directorate | | Nuclear August 29, 1986 NLR-N86110 Ref : LCR 8 6 -0 1 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Steven A. Varga, Director Project Directorate #3 Division of PWR Licensing Gen tl eme n: |
| #3 Division of PWR Licensing Gen tl eme n: REQUEST FOR AMENDMENT 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 minor typographical changes to the Technical Specifications. | | REQUEST FOR AMENDMENT 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. |
| In accordance with the fee requirements of 10 CFR 170.21, a check in the amount of $150.00 is enclosed. ( ---------------------8609040092 860829 PDR | | This amendment request consists of minor typographical changes to the Technical Specifications. |
| * ADOCK 05000272 P -PDR | | In accordance with the fee requirements of 10 CFR 170.21, a check in the amount of $150.00 is enclosed. |
| * Mr. Steven A. Varga 2 8-29-86 Pursuant to the requirements of 10 CFR 50.91, a copy of this request for amendment has been sent to the State of New Jersey 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, NJ 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801
| | ( |
| * e STATE OF NEW *JERSEY COUNTY OF SALEM ) ) ) Ref: LCR 86-01 SS. Corbin A. McNeill, Jr., being duly sworn according to law deposes and says: I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated Aug. 2 9, 19 8 6, concerning our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75, are true to the best of my knowledge, information and belief. | | ------ -- ---- - - - - - - - - - |
| this ;// My Commission expires on me 1986 N LARAINE Y. BEARD M otory Public of New Jersey >'Commission Expires May 1, 1991 | | 8609040092 860829 PDR |
| ** PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS SALEM UNIT NOS. 1 AND 2 DESCRIPTION OF CHANGE LCR 86-01 Page 1 of 3 Revise Technical Specifications enumerated below to add clarification, to achieve consistency, or to correct typographical errors. The revisions are identified on the attached changed pages. 1. Revise Unit 1 and 2 Technical Specification Table 3.3-1, Functional Units 16 and 17 (Reactor Coolant Pumps Undervoltage and Underfrequency). | | * ADOCK 05000272 P - PDR |
| The minimum channels operable is being changed from four to three. 2. Revise Technical Specification Tables 3.3-3 and 4.3-2, Functional Unit 8f Emergency Trip of Steam Generator Feedwater Pumps -Start Motor-Driven (Auxiliary Feedwater Pumps). This change adds Mode 2 to APPLICABLE MODES for Unit 1 and corrects the number of channels and ACTION 22 -for Unit 2. 3. Revise Action Statement 20 in Unit 2 Table 3.3-3, to allow one channel of functional Units 4b and Ba (Stearn Line Isolation and Auxiliary Feedwater Automatic Actuation Logic) to be bypassed for 2 hours for surveillance testing. 4. Change table notation in Unit 2 Technical Specification Table 3.3-6, for Action Statement number 24 to correct the number of the referenced specification. | | |
| : 5. Revise Unit 2 surveillance requirements for turbine overspeed protection, Specification 4.3.4.2, and delete Specification 4.3.4.3. | | Mr. Steven A. Varga |
| * 6. Revise Unit 1 Steam Generator surveillance requirement Specifications 4.4.5.2 through. 4.4.5.5. 7. Revise numbering for Unit 2 Surveillance Requirements 4.4.7.2 on reactor coolant system operational leakage. 8. Revise descriptions of SJ 144 valves in Unit 2 Specification Table 3.4-1. 9. Revise Unit 1 Technical Specification 3.5.5, LCO (a) and (b), to correct typographical REASON FOR CHANGE 1. This change corrects typographical errors in the Technical Specifications.
| | * 2 8-29-86 Pursuant to the requirements of 10 CFR 50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below. |
| For four-loop plants three channels are required to be operable. | | This submittal includes three (3) signed originals and forty (40) copies. |
| The change brings the Specifications into conformance with Westinghouse Standard Technical Specifications (NUREG-0452, Revision 4). I . I I | | 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, NJ 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801 |
| * LCR 86-01 Page 2 of 3 2. The APPLICABILITY requirement was inadvertently listed as MODE 1 for Unit 1. The Unit 2 specification was inadvertently taken directly from the Standard Technical Specifications. | | * e Ref: LCR 86-01 STATE OF NEW *JERSEY ) |
| This specification is not applicable since it does not reflect the Salem design. This change is being made to make the Technical Specifications for both units agree and to respond to a specific NRC request for the correction to Unit 1 in Enclosure 1 to Generic Letter 82-16, Status Summary of NUREG-0737 Technical Specifications for Salem 1 and 2. This change supercedes LCR 84-15, dated March 15, 1986. 3. This change corrects a typographical error in the action statement, which currently allows only one hour for surveillance testing. The proposed change to two hours makes the requirement the same as that for Unit 1 and brings the specification into conformance with the Westinghouse Standard Technical Specifications. | | ) SS. |
| : 4. Action Statement 24 for inoperable radiation monitoring system channel currently refers to Specification 3.4.6.1, the Specification for steam generators. | | COUNTY OF SALEM ) |
| It is being corrected to refer to Specification 3.4.7.1 for reactor coolant system leak detection. | | Corbin A. McNeill, Jr., being duly sworn according to law deposes and says: |
| : 5. The present Specifications 4.3.4.2 and 4.3.4.3 are applicable for turbines with sequential arc admission, whereas Unit 2 turbines have full arc admission. | | I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated Aug. 2 9, 19 8 6, concerning our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75, are true to the best of my knowledge, information and belief. |
| The proposed change to Specification 4.3.4.2 brings the Unit 2 specification into conformance with Westinghouse Standard Technical Specifications and makes Specification 4.3.4.3 superfluous. | | Subscrib~ me this ;// 1986 N LARAINE Y. BEARD M otory Public of New Jersey My Commission expires on >'Commission Expires May 1, 1991 |
| | |
| | ** |
| | PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS LCR 86-01 Page 1 of 3 SALEM UNIT NOS. 1 AND 2 DESCRIPTION OF CHANGE Revise Technical Specifications enumerated below to add clarification, to achieve consistency, or to correct typographical errors. The revisions are identified on the attached changed pages. |
| | : 1. Revise Unit 1 and 2 Technical Specification Table 3.3-1, Functional Units 16 and 17 (Reactor Coolant Pumps Undervoltage and Underfrequency). The minimum channels operable is being changed from four to three. |
| | : 2. Revise Technical Specification Tables 3.3-3 and 4.3-2, Functional Unit 8f Emergency Trip of Steam Generator Feedwater Pumps - Start Motor-Driven (Auxiliary Feedwater Pumps). This change adds Mode 2 to APPLICABLE MODES for Unit 1 and corrects the number of channels and ACTION 22 |
| | -for Unit 2. |
| | : 3. Revise Action Statement 20 in Unit 2 Table 3.3-3, to allow one channel of functional Units 4b and Ba (Stearn Line Isolation and Auxiliary Feedwater Automatic Actuation Logic) to be bypassed for 2 hours for surveillance testing. |
| | I |
| | : 4. Change table notation in Unit 2 Technical Specification . I I |
| | Table 3.3-6, for Action Statement number 24 to correct the number of the referenced specification. |
| | : 5. Revise Unit 2 surveillance requirements for turbine overspeed protection, Specification 4.3.4.2, and delete Specification 4.3.4.3. * |
| | : 6. Revise Unit 1 Steam Generator surveillance requirement Specifications 4.4.5.2 through. 4.4.5.5. |
| | : 7. Revise numbering for Unit 2 Surveillance Requirements 4.4.7.2 on reactor coolant system operational leakage. |
| | : 8. Revise descriptions of SJ 144 valves in Unit 2 Specification Table 3.4-1. |
| | : 9. Revise Unit 1 Technical Specification 3.5.5, LCO (a) and (b), to correct typographical erro~s. |
| | REASON FOR CHANGE |
| | : 1. This change corrects typographical errors in the Technical Specifications. For four-loop plants three channels are required to be operable. The change brings the Specifications into conformance with Westinghouse Standard Technical Specifications (NUREG-0452, Revision 4). |
| | |
| | 2. |
| | * LCR 86-01 Page 2 of 3 The APPLICABILITY requirement was inadvertently listed as MODE 1 for Unit 1. The Unit 2 specification was inadvertently taken directly from the Standard Technical Specifications. This specification is not applicable since it does not reflect the Salem design. |
| | This change is being made to make the Technical Specifications for both units agree and to respond to a specific NRC request for the correction to Unit 1 in Enclosure 1 to Generic Letter 82-16, Status Summary of NUREG-0737 Technical Specifications for Salem 1 and 2. |
| | This change supercedes LCR 84-15, dated March 15, 1986. |
| | : 3. This change corrects a typographical error in the action statement, which currently allows only one hour for surveillance testing. The proposed change to two hours makes the requirement the same as that for Unit 1 and brings the specification into conformance with the Westinghouse Standard Technical Specifications. |
| | : 4. Action Statement 24 for inoperable radiation monitoring system channel currently refers to Specification 3.4.6.1, the Specification for steam generators. It is being corrected to refer to Specification 3.4.7.1 for reactor coolant system leak detection. |
| | : 5. The present Specifications 4.3.4.2 and 4.3.4.3 are applicable for turbines with sequential arc admission, whereas Unit 2 turbines have full arc admission. The proposed change to Specification 4.3.4.2 brings the Unit 2 specification into conformance with Westinghouse Standard Technical Specifications and makes Specification 4.3.4.3 superfluous. |
| : 6. The proposed change makes Unit 1 surveillance requirements the same as those for Unit 2, and brings these requirements into conformance with Westinghouse Standard Technical Specifications. | | : 6. The proposed change makes Unit 1 surveillance requirements the same as those for Unit 2, and brings these requirements into conformance with Westinghouse Standard Technical Specifications. |
| 7.-Currently, these are two specifications numbered 4.4.7.2. They are being renumbered to 4.4.7.2.l and 4.4.7.2.2. | | 7.- Currently, these are two specifications numbered 4.4.7.2. |
| : 8. The valves are described in the table as being in high-pressure safety injection lines to the RCS hot legs. They are in the lines to the cold legs. 9. The present Specification states that the volume in the RWST is "between 364,000 and 400,000 of borated wa_ter." The-lower limit is being raised to 364,500; additionally, the word "gallons" is being added. The LCO on boron concentration is being corrected from "between 2000 and 2000 ppm" to "between 2000 and 2200 ppm." | | They are being renumbered to 4.4.7.2.l and 4.4.7.2.2. |
| SIGNIFICANT HAZARDS CONSIDERATION LCR 86-01 Page 3 of 3 These changes are administrative in nature in that they are being made to provide clarification, achieve consistency, or correct errors. There are no modifications to the plant or to plant operating procedures.
| | : 8. The valves are described in the table as being in high-pressure safety injection lines to the RCS hot legs. |
| Therefore the proposed amendment does not constitute a significant in that: 1. It does not involve a significant increase in the probability or consequences of any previously evaluated accident; | | They are actu~lly in the lines to the cold legs. |
| | : 9. The present Specification states that the volume in the RWST is "between 364,000 and 400,000 of borated wa_ter." |
| | The-lower limit is being raised to 364,500; additionally, the word "gallons" is being added. |
| | The LCO on boron concentration is being corrected from "between 2000 and 2000 ppm" to "between 2000 and 2200 ppm." |
| | |
| | LCR 86-01 Page 3 of 3 SIGNIFICANT HAZARDS CONSIDERATION These changes are administrative in nature in that they are being made to provide clarification, achieve consistency, or correct errors. There are no modifications to the plant or to plant operating procedures. Therefore the proposed amendment does not constitute a significant haz~rd in that: |
| | : 1. It does not involve a significant increase in the probability or consequences of any previously evaluated accident; |
| : 2. It does not create the possibility of a new or different kind of accident from any accident previously evaluated; | | : 2. It does not create the possibility of a new or different kind of accident from any accident previously evaluated; |
| : 3. It does not involve significant reduction in a margin of safety. The commission has provided guidance concerning the application of the standards for a No Significant Hazards determination by providing examples of actions not likely to involve a Significant Hazards Consideration in the Federal Register (48FR14870). | | : 3. It does not involve significant reduction in a margin of safety. |
| This proposed amendment corresponds to example (i) for amendments that are not likely to involve significant hazards considerations. | | The commission has provided guidance concerning the application of the standards for a No Significant Hazards determination by providing examples of actions not likely to involve a Significant Hazards Consideration in the Federal Register (48FR14870). This proposed amendment corresponds to example (i) for amendments that are not likely to involve significant hazards considerations. |
| REVISED PAGES -UNIT NO. l}} | | |
| | REVISED PAGES - UNIT NO. l}} |
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[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18107A4991999-08-25025 August 1999 Application for Amends to Licenses DPR-70 & DPR-75,proposing to Authorize Licensee to Perform Single Cell Charging of Connected Cells in Operable Class 1E Batteries ML18107A5141999-08-25025 August 1999 Suppl to 971114 Application for Amends to Licenses DPR-70 & DPR-75,deleting Footnotes Added as one-time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Unit 2 ML18107A4631999-07-29029 July 1999 Application for Amends to Licenses DPR-70 & DPR-75,replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4581999-07-23023 July 1999 Application for Amends to Licenses DPR-70 & DPR-75 to Change TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4221999-07-0202 July 1999 Application for Amends to Licenses DPR-70 & DPR-75 to Relocate TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to Ufsar,Iaw GL 95-10 ML18107A3771999-06-10010 June 1999 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.6.1, Containment Integrity, by Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3571999-06-0404 June 1999 Application for Amends to Licenses DPR-70,DPR-75 & NPF-57 Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New,Affiliated Nuclear Generating Company, PSEG Nuclear Llc.Proprietary Encls Withheld ML18107A2081999-04-14014 April 1999 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.9.12, Fhvas, to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,Per NUREG-1431. Page 4 of 4 in Attachment 2 of Incoming Submittal Omitted ML18106B1571999-03-31031 March 1999 Suppl to 990115 Application for Amend to License DPR-70, Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0621999-02-0808 February 1999 Application for Amends to Licenses DPR-70 & DPR-75, Respectively.Proposed Amend Modifies ECCS Subsystems Surveillance Requirement 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0501999-02-0202 February 1999 Application for Amends to Licenses DPR-70 & DPR-75,revising Max Permissible Enrichment of Stored New Fuel Described in TS Section 5.6.1.1.Rept Entitled, Criticality Analysis of Salem Units 1 & 2 Fresh Fuel Racks, Encl ML18106B0221999-01-15015 January 1999 Application for Amend to License DPR-70,proposing one-time Changes to Certain Unit 1 TS Surveillance Requirements for Fuel Cycle 13,currently Scheduled to Begin on 990918 ML18106A9161998-10-12012 October 1998 Application for Amend to License DPR-75,requesting one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10.Basis for Requested Changes,Analysis Supporting No Significant Hazards Determination & Marked Up TS Pages,Encl ML18106A8921998-09-29029 September 1998 Application for Amends to Licenses DPR-72 & DPR-75,modifying TS 3/4.9.4 to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8761998-09-17017 September 1998 Application for Amends to Licenses DPR-70 & DPR-75,modifying TSs 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8351998-08-12012 August 1998 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS for Containment Air Locks for Salem Units 1 & 2 ML18106A7911998-07-30030 July 1998 Application for Amends to Licenses DPR-70 & DPR-75,revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Following Phrase ML18106A4271998-03-26026 March 1998 Application for Amend to License DPR-70,changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A4221998-03-26026 March 1998 Application for Amends to Licenses DPR-70 & DPR-75, Respectively,Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A2521998-01-0808 January 1998 Supplemental Application for Amends to Licenses DPR-70 & DPR-75,respectively Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2111997-12-15015 December 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modifying Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1941997-12-11011 December 1997 Application for Amend to License DPR-70,requesting one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6771997-11-14014 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,providing TS Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6731997-11-14014 November 1997 Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance ML18102B6611997-11-0404 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.8.1 Re EDG & Deleting SR 4.8.1.1.2.d.1,calling for Diesels to Be Subjected to Insp Based on Vendor Recommendations ML18102B6571997-11-0404 November 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6371997-10-29029 October 1997 Application for Amend to License DPR-75,revising TS 3/4.4.6, Steam Generators, Making One Time Change to Unit 2 SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6411997-10-29029 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.8.1.1.2.d.2 Proposed in Util 960925 Submittal Re EDG Testing ML18102B6471997-10-24024 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6441997-10-24024 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6291997-10-21021 October 1997 Application for Amends to Licenses DPR-70 & DPR-75,extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers in Closed Position ML18102B6181997-10-14014 October 1997 Application for Amend to License DPR-70,modifying Pressure Isolation Valve Lco,Lco Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 ML18102B6061997-10-0606 October 1997 Application for Amend to License DPR-70,changing TS for LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys. ML18102B5551997-08-27027 August 1997 Application for Amends to Licenses DPR-70 & DPR-75,providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, to State That CCW Pumps Required to Be Operable to Meet LCO ML18102B5281997-08-19019 August 1997 Application for Amend to License DPR-75,providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Plant Unit 2 ML18102B5321997-08-18018 August 1997 Application for Amend to License DPR-75,incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies ML18102B4871997-08-0101 August 1997 Application for Amends to Licenses DPR-70 & DPR-75,rewording TS Section 4.2.1 to State That Util Will Adhere to Section 7 Incidental Take Statement Approved by Natl Marine Fisheries Svc ML20148K0841997-06-0404 June 1997 Amends 194 & 177 to Licenses DPR-70 & DPR-75,respectively, Changing TSs 3.4.3 & 3.4.5, Relief Valves, to Ensure That Automatic Capability of PORVs to Relieve Pressure Is Maintained When Valves Are Isolated ML18102B3041997-05-14014 May 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.7.6.1.d.1 to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & to Reflecting Filter Dp Acceptance Value of Greater than 2.70 Wg ML18102B2611997-05-0101 May 1997 Suppl Info to Util 970211 Application for Amends to Licenses DPR-70 & DPR-75,revising TS for Chilled Water Sys - Auxiliary Bldg Subsystem.Ref to Radiation Monitoring Signal Removed from Bases Section ML18102B2581997-05-0101 May 1997 Application for Amend to License DPR-75,revising TS Section 3/4.7.7 to Reflect Extended Allowed Outage Times & Creating New TS Section 3/4.7.11 to Address Importance of Switchgear & Penetration Area Ventilation Sys ML18102B0071997-04-30030 April 1997 Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger ML18102B2511997-04-28028 April 1997 Submits Suppl to 970131 & 0314 Applications for Amends to Licenses DPR-70 & DPR-75,revising TS on Pressurizer Power Operated Relief Valves.Suppl Issued to State That Conclusion of NSHC Remains Valid ML18102B0221997-04-25025 April 1997 Application for Amends to Licenses DPR-70 & DPR-75, Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2 ML18102A9791997-04-11011 April 1997 Application for Amends to Licenses DPR-70 & DPR-75, Increasing Cw Flow to 2550 Gpm for 31 Day Surveillance Fans Started & Operated in Low Speed ML18102A8951997-03-0404 March 1997 Application for Amends to Licenses DPR-70 & DPR-75,modifying ECCS Surveillance Test Acceptance Criteria for Centrifugal Charging & SI Pumps ML18102A8491997-02-11011 February 1997 Application for Amends to Licenses DPR-70 & DPR-75, Requesting Addition of New TS 3/4.7.10, Chilled Water Sys ML18102A8361997-01-31031 January 1997 Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.4.3 to Ensure That Automatic Capability of Power Operated Relief Valve to Relieve Pressure Is Maintained When Valves Are Isolated by Closure of Block Valves ML18102A8021997-01-31031 January 1997 Application for Amends to Licenses DPR-70 & DPR-75, Requesting Rev to TS Re Containment Systems Air Temp to Ensure Representative Average Air Temp Is Measured ML18102A7861997-01-23023 January 1997 Application for Amend to License DPR-75,revising TS Bases 3/4.3.3.1 Re Radiation Monitoring Instrumentation Channel 2R41 1999-08-25
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Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Vice President -
Nuclear August 29, 1986 NLR-N86110 Ref : LCR 8 6 -0 1 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Steven A. Varga, Director Project Directorate #3 Division of PWR Licensing Gen tl eme n:
REQUEST FOR AMENDMENT 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 minor typographical changes to the Technical Specifications.
In accordance with the fee requirements of 10 CFR 170.21, a check in the amount of $150.00 is enclosed.
(
-- ---- - - - - - - - - -
8609040092 860829 PDR
Mr. Steven A. Varga
- 2 8-29-86 Pursuant to the requirements of 10 CFR 50.91, a copy of this request for amendment has been sent to the State of New Jersey 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, NJ 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801
- e Ref: LCR 86-01 STATE OF NEW *JERSEY )
) SS.
COUNTY OF SALEM )
Corbin A. McNeill, Jr., being duly sworn according to law deposes and says:
I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated Aug. 2 9, 19 8 6, concerning our Request for Amendment to Facility Operating Licenses DPR-70 and DPR-75, are true to the best of my knowledge, information and belief.
Subscrib~ me this ;// 1986 N LARAINE Y. BEARD M otory Public of New Jersey My Commission expires on >'Commission Expires May 1, 1991
PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS LCR 86-01 Page 1 of 3 SALEM UNIT NOS. 1 AND 2 DESCRIPTION OF CHANGE Revise Technical Specifications enumerated below to add clarification, to achieve consistency, or to correct typographical errors. The revisions are identified on the attached changed pages.
- 1. Revise Unit 1 and 2 Technical Specification Table 3.3-1, Functional Units 16 and 17 (Reactor Coolant Pumps Undervoltage and Underfrequency). The minimum channels operable is being changed from four to three.
- 2. Revise Technical Specification Tables 3.3-3 and 4.3-2, Functional Unit 8f Emergency Trip of Steam Generator Feedwater Pumps - Start Motor-Driven (Auxiliary Feedwater Pumps). This change adds Mode 2 to APPLICABLE MODES for Unit 1 and corrects the number of channels and ACTION 22
-for Unit 2.
- 3. Revise Action Statement 20 in Unit 2 Table 3.3-3, to allow one channel of functional Units 4b and Ba (Stearn Line Isolation and Auxiliary Feedwater Automatic Actuation Logic) to be bypassed for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing.
I
- 4. Change table notation in Unit 2 Technical Specification . I I
Table 3.3-6, for Action Statement number 24 to correct the number of the referenced specification.
- 5. Revise Unit 2 surveillance requirements for turbine overspeed protection, Specification 4.3.4.2, and delete Specification 4.3.4.3. *
- 6. Revise Unit 1 Steam Generator surveillance requirement Specifications 4.4.5.2 through. 4.4.5.5.
- 7. Revise numbering for Unit 2 Surveillance Requirements 4.4.7.2 on reactor coolant system operational leakage.
- 8. Revise descriptions of SJ 144 valves in Unit 2 Specification Table 3.4-1.
- 9. Revise Unit 1 Technical Specification 3.5.5, LCO (a) and (b), to correct typographical erro~s.
REASON FOR CHANGE
- 1. This change corrects typographical errors in the Technical Specifications. For four-loop plants three channels are required to be operable. The change brings the Specifications into conformance with Westinghouse Standard Technical Specifications (NUREG-0452, Revision 4).
2.
- LCR 86-01 Page 2 of 3 The APPLICABILITY requirement was inadvertently listed as MODE 1 for Unit 1. The Unit 2 specification was inadvertently taken directly from the Standard Technical Specifications. This specification is not applicable since it does not reflect the Salem design.
This change is being made to make the Technical Specifications for both units agree and to respond to a specific NRC request for the correction to Unit 1 in Enclosure 1 to Generic Letter 82-16, Status Summary of NUREG-0737 Technical Specifications for Salem 1 and 2.
This change supercedes LCR 84-15, dated March 15, 1986.
- 3. This change corrects a typographical error in the action statement, which currently allows only one hour for surveillance testing. The proposed change to two hours makes the requirement the same as that for Unit 1 and brings the specification into conformance with the Westinghouse Standard Technical Specifications.
- 4. Action Statement 24 for inoperable radiation monitoring system channel currently refers to Specification 3.4.6.1, the Specification for steam generators. It is being corrected to refer to Specification 3.4.7.1 for reactor coolant system leak detection.
- 5. The present Specifications 4.3.4.2 and 4.3.4.3 are applicable for turbines with sequential arc admission, whereas Unit 2 turbines have full arc admission. The proposed change to Specification 4.3.4.2 brings the Unit 2 specification into conformance with Westinghouse Standard Technical Specifications and makes Specification 4.3.4.3 superfluous.
- 6. The proposed change makes Unit 1 surveillance requirements the same as those for Unit 2, and brings these requirements into conformance with Westinghouse Standard Technical Specifications.
7.- Currently, these are two specifications numbered 4.4.7.2.
They are being renumbered to 4.4.7.2.l and 4.4.7.2.2.
- 8. The valves are described in the table as being in high-pressure safety injection lines to the RCS hot legs.
They are actu~lly in the lines to the cold legs.
- 9. The present Specification states that the volume in the RWST is "between 364,000 and 400,000 of borated wa_ter."
The-lower limit is being raised to 364,500; additionally, the word "gallons" is being added.
The LCO on boron concentration is being corrected from "between 2000 and 2000 ppm" to "between 2000 and 2200 ppm."
LCR 86-01 Page 3 of 3 SIGNIFICANT HAZARDS CONSIDERATION These changes are administrative in nature in that they are being made to provide clarification, achieve consistency, or correct errors. There are no modifications to the plant or to plant operating procedures. Therefore the proposed amendment does not constitute a significant haz~rd in that:
- 1. It does not involve a significant increase in the probability or consequences of any previously evaluated accident;
- 2. It does not create the possibility of a new or different kind of accident from any accident previously evaluated;
- 3. It does not involve significant reduction in a margin of safety.
The commission has provided guidance concerning the application of the standards for a No Significant Hazards determination by providing examples of actions not likely to involve a Significant Hazards Consideration in the Federal Register (48FR14870). This proposed amendment corresponds to example (i) for amendments that are not likely to involve significant hazards considerations.
REVISED PAGES - UNIT NO. l