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| {{#Wiki_filter:** J ' Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref: LCR-84-10 January 11, 1985 Director of Nuclear Reactor Regulation | | {{#Wiki_filter:** J ' |
| : u. s. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: | | Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref: LCR-84-10 January 11, 1985 Director of Nuclear Reactor Regulation |
| Mr. Steven A. Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen: | | : u. s. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Steven A. Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen: |
| REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES UNIT NO. 2 SALEM GENERATING STATION DOCKET NO. 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 License DPR-75 for Salem Generating Station, Unit No. 2. This amendment request consists of a revision to Technical Specifications, Appendix A, Section 3.2.3, Power Dependent Insertion Limit requirements, Figure 3.1-1. In accordance with the fee requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed. | | REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES UNIT NO. 2 SALEM GENERATING STATION DOCKET NO. 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 License DPR-75 for Salem Generating Station, Unit No. 2. |
| Pursuant to the requirements of 10CFR50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below. 8501220379 850111 PDR ADOCK 05000311 p PDR The Energy People ,,91.00 95-2168 (25M) 6-84 | | This amendment request consists of a revision to Technical Specifications, Appendix A, Section 3.2.3, Power Dependent Insertion Limit requirements, Figure 3.1-1. |
| *, Mr. Steven A. Varga 1/11/85 This submittal includes three (3) signed originals and forty (40) copies. Sincerely, Manager -Nuclear Enclosure C Mr. Donald C. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector Licensing and Regulation Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, New Jersey 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801 | | In accordance with the fee requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed. |
| ' ' STATE OF NEW JERSEY ) ) COUNTY OF SALEM ) Ref: LCR-84-10 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 dated January 11, 1985, are true to the best of my knowledge, information and belief. RICHARD A*. UD§"°RITZ | | Pursuant to the requirements of 10CFR50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below. |
| ;,fr Subscribed and sworn to before me this I J tJ.., day of , 1985 Notary Public of New Jersey i:mmm G. mTCl-lNER NOTl\RY PUBLIC OF NEW JERSEY My Comm i s s ion exp ires o n _ | | 8501220379 850111 PDR ADOCK 05000311 p PDR |
| _19_8_7 __ _
| | ,,91.00 |
| . . PROPOSED TECH. SPEC. CHANGE POWER DEPENDENT INSERTION LIMITS SALEM GENERATING STATION UNIT NO. 2 Description of Change Ref: . LCR 84-10 The R_ower Dependent Insertion Limit (PDIL) change requires an increase of the Salem Unit rod insertion capability to match that of the Unit 1 limits. The current and proposed PDIL for Unit 2 are shown in Figures 1 and 2. Reason for Change *Prior to the startup of Unit 2, Cycle 2, the PDIL's were changed to comply with the Fh limits given in Tech. Spec. Section 3.2.3 and to maintain acceptable power peaking factors for Cycle 2 operation.* | | ~(!..~~ \JJ~"'C.11-The Energy People 95-2168 (25M) 6-84 |
| The cycle 2 reload design necessitated the reduction of rod insertion limits. The limits*were made more restrictive and thus resulted in a decrease in operational The cycle 2 design identified the need to revise the control rod pattern (bank grouping). | | |
| To the above lack of flexibility, the cycle 3 reload design is based on a revised control rod pattern which closely*approximates the current Unit 1 control rod pattern. The design change request to reidentify control banks is being implemented during cycle 2-3 refueling outage, under the provisions of lOCFRS0.59. | | *, |
| The benefits w{th the revised rod pattern are follows: 1. Reduces the maximum hot channel enthalpy rise factors during reactor maneuvers. | | Mr. Steven A. Varga 1/11/85 This submittal includes three (3) signed originals and forty (40) copies. |
| : 2. Provides a significant increase in operational flexibility by allowing an increase of the rod insertion limits. Therefore, to take advantage of the irtcreased flexibility identified in the cycle 3 RSE Report, the PDIL should be changed to allow a relaxation of the Unit 2 rod insertion requirements to match that of the current Unit 1 limits. Significant Hazards Consideration It has been determined that the LCR no significant hazards consideration under lOCFRS0.92. | | Sincerely, |
| The purpose of the power dependent rod insertion limits is threefold. | | !~Manager - Nuclear Licensing and Regulation Enclosure C 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 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801 |
| First, rod insertion is limited in order | | |
| ,, " .. to ensure acceptable power distributions; second, to maintain minimum shutdown margin; and third, to minimize the effects of postulated rod ejection accident.
| | ' ' |
| Cycle specific tions are performed to evaluate and determine the power dependent insertion limits required to satisfy the above three requirements. | | Ref: LCR-84-10 STATE OF NEW JERSEY ) |
| A Reload Safety Evaluation (RSE) for cycle 3 has been performed by-Westinghouse (Reference | | ) ss: COUNTY OF SALEM COUNTY OF SALEM ) |
| : 1) and reviewed by PSE&G to mine the impact of less restrictive (i.e. deeper) rod insertion limits. The results of the Westinghouse RSE show that the proposed limits do not cause the previously acceptable safety limits for any incident to be exceeded.
| | RICHARD A. UDERITZ, being duly sworn according to law deposes and says: |
| PSE&G has reviewed this analysis and concurs with the The PSE&G review consisted of performing an independent reload safety evaluation for cycle 3 using in-house computer codes, and it resulted in the determination that the current safety analysis design bases continue to be met. Operation of Salem Unit 2 in accordance with the proposed power dependent insertion limits: 0 0 0 0 would not involve a sigriificant increase in the bility or consequences of an accident previously evaluated for Salem Unit 2, since the proposed change in PDIL showed that the current core safety limits were still applicable. | | 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 dated January 11, 1985, are true to the best of my knowledge, information and belief. |
| in no way creates the possibility of a new or different kind of accident from any accident previously evaluated for Salem Unit 2, since no plant modifications resulted from this change. does not involve a significant reduction in any margin of safety. is clearly within all acceptable criteria specified in the Standard Review Plan. Based on the above evaluation we have determined that the proposed change in PDIL corresponds to example (vi) of guidance provided by the Commission in Federal Register 48FR 14870 for Amendments Likely To Not Involve Significant Hazards Consideration. | | ~~~ |
| | RICHARD A*. UD§"°RITZ ;,fr Subscribed and sworn to before me this I J tJ.., day of ~e<..a~ , 1985 Notary Public of New Jersey i:mmm G. mTCl-lNER NOTl\RY PUBLIC OF NEW JERSEY My Comm i s s ion exp ires o n_ _JJM<!Jv'"-'C~o"-'-m"""m'"'"'.is::..::.s:.;:.io.:..:..n=E:~zp..:...ir..:...es=-~-Aa_r_ch_2_4..:...,_19_8_7_ __ |
| | |
| | . . |
| | Ref: . LCR 84-10 PROPOSED TECH. SPEC. CHANGE POWER DEPENDENT INSERTION LIMITS SALEM GENERATING STATION UNIT NO. 2 Description of Change The R_ower Dependent Insertion Limit (PDIL) change requires an increase of the Salem Unit ~ rod insertion capability to match that of the curr~nt Unit 1 limits. The current and proposed PDIL for Unit 2 are shown in Figures 1 and 2. |
| | Reason for Change |
| | *Prior to the startup of Unit 2, Cycle 2, the PDIL's were changed to comply with the Fh limits given in Tech. Spec. |
| | Section 3.2.3 and to maintain acceptable power peaking factors for Cycle 2 operation.* The cycle 2 reload design necessitated the reduction of rod insertion limits. The limits*were made more restrictive and thus resulted in a decrease in operational flexibility~ The cycle 2 design identified the need to revise the control rod pattern (bank grouping). |
| | To allevi~te the above lack of flexibility, the cycle 3 reload design is based on a revised control rod pattern which closely*approximates the current Unit 1 control rod pattern. The design change request to reidentify control banks is being implemented during cycle 2-3 refueling outage, under the provisions of lOCFRS0.59. The benefits a~sociated w{th the revised rod pattern are a~ follows: |
| | : 1. Reduces the maximum hot channel enthalpy rise factors during reactor maneuvers. |
| | : 2. Provides a significant increase in operational flexibility by allowing an increase of the rod insertion limits. |
| | Therefore, to take advantage of the irtcreased flexibility identified in the cycle 3 RSE Report, the PDIL should be changed to allow a relaxation of the Unit 2 rod insertion requirements to match that of the current Unit 1 limits. |
| | Significant Hazards Consideration It has been determined that the LCR invol~es no significant hazards consideration under lOCFRS0.92. |
| | The purpose of the power dependent rod insertion limits is threefold. First, rod insertion is limited in order |
| | |
| | " .. |
| | to ensure acceptable power distributions; second, to maintain minimum shutdown margin; and third, to minimize the effects of postulated rod ejection accident. Cycle specific calcula-tions are performed to evaluate and determine the power dependent insertion limits required to satisfy the above three requirements. |
| | A Reload Safety Evaluation (RSE) for cycle 3 has been performed by-Westinghouse (Reference 1) and reviewed by PSE&G to deter-mine the impact of less restrictive (i.e. deeper) rod insertion limits. The results of the Westinghouse RSE show that the proposed limits do not cause the previously acceptable safety limits for any incident to be exceeded. PSE&G has reviewed this analysis and concurs with the Westinghouse~conclusions. |
| | The PSE&G review consisted of performing an independent reload safety evaluation for cycle 3 using in-house computer codes, and it resulted in the determination that the current safety analysis design bases continue to be met. Operation of Salem Unit 2 in accordance with the proposed power dependent insertion limits: |
| | 0 would not involve a sigriificant increase in the proba-bility or consequences of an accident previously evaluated for Salem Unit 2, since the proposed change in PDIL showed that the current core safety limits were still applicable. |
| | 0 in no way creates the possibility of a new or different kind of accident from any accident previously evaluated for Salem Unit 2, since no plant modifications resulted from this change. |
| | 0 does not involve a significant reduction in any margin of safety. |
| | 0 is clearly within all acceptable criteria specified in the Standard Review Plan. |
| | Based on the above evaluation we have determined that the proposed change in PDIL corresponds to example (vi) of guidance provided by the Commission in Federal Register 48FR 14870 for Amendments Likely To Not Involve Significant Hazards Consideration. |
| References | | References |
| : 1. Reload Safety Evaluation for Salem Unit 2, Cycle 3; December 1984, Westinghouse Nuclear Fuel Division, M. M. Weber, A. N. Piplica, E. F. Pulver, M. E. Pohlman.}} | | : 1. Reload Safety Evaluation for Salem Unit 2, Cycle 3; December 1984, Westinghouse Nuclear Fuel Division, M. M. Weber, A. N. Piplica, E. F. Pulver, M. E. Pohlman.}} |
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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 P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref: LCR-84-10 January 11, 1985 Director of Nuclear Reactor Regulation
- u. s. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Steven A. Varga, Chief Operations Reactors Branch 1 Division of Licensing Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES UNIT NO. 2 SALEM GENERATING STATION DOCKET NO. 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 License DPR-75 for Salem Generating Station, Unit No. 2.
This amendment request consists of a revision to Technical Specifications, Appendix A, Section 3.2.3, Power Dependent Insertion Limit requirements, Figure 3.1-1.
In accordance with the fee requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed.
Pursuant to the requirements of 10CFR50.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below.
8501220379 850111 PDR ADOCK 05000311 p PDR
,,91.00
~(!..~~ \JJ~"'C.11-The Energy People 95-2168 (25M) 6-84
Mr. Steven A. Varga 1/11/85 This submittal includes three (3) signed originals and forty (40) copies.
Sincerely,
!~Manager - Nuclear Licensing and Regulation Enclosure C 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 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801
' '
Ref: LCR-84-10 STATE OF NEW JERSEY )
) ss: COUNTY OF SALEM 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 dated January 11, 1985, are true to the best of my knowledge, information and belief.
~~~
RICHARD A*. UD§"°RITZ ;,fr Subscribed and sworn to before me this I J tJ.., day of ~e<..a~ , 1985 Notary Public of New Jersey i:mmm G. mTCl-lNER NOTl\RY PUBLIC OF NEW JERSEY My Comm i s s ion exp ires o n_ _JJM<!Jv'"-'C~o"-'-m"""m'"'"'.is::..::.s:.;:.io.:..:..n=E:~zp..:...ir..:...es=-~-Aa_r_ch_2_4..:...,_19_8_7_ __
. .
Ref: . LCR 84-10 PROPOSED TECH. SPEC. CHANGE POWER DEPENDENT INSERTION LIMITS SALEM GENERATING STATION UNIT NO. 2 Description of Change The R_ower Dependent Insertion Limit (PDIL) change requires an increase of the Salem Unit ~ rod insertion capability to match that of the curr~nt Unit 1 limits. The current and proposed PDIL for Unit 2 are shown in Figures 1 and 2.
Reason for Change
- Prior to the startup of Unit 2, Cycle 2, the PDIL's were changed to comply with the Fh limits given in Tech. Spec.
Section 3.2.3 and to maintain acceptable power peaking factors for Cycle 2 operation.* The cycle 2 reload design necessitated the reduction of rod insertion limits. The limits*were made more restrictive and thus resulted in a decrease in operational flexibility~ The cycle 2 design identified the need to revise the control rod pattern (bank grouping).
To allevi~te the above lack of flexibility, the cycle 3 reload design is based on a revised control rod pattern which closely*approximates the current Unit 1 control rod pattern. The design change request to reidentify control banks is being implemented during cycle 2-3 refueling outage, under the provisions of lOCFRS0.59. The benefits a~sociated w{th the revised rod pattern are a~ follows:
- 1. Reduces the maximum hot channel enthalpy rise factors during reactor maneuvers.
- 2. Provides a significant increase in operational flexibility by allowing an increase of the rod insertion limits.
Therefore, to take advantage of the irtcreased flexibility identified in the cycle 3 RSE Report, the PDIL should be changed to allow a relaxation of the Unit 2 rod insertion requirements to match that of the current Unit 1 limits.
Significant Hazards Consideration It has been determined that the LCR invol~es no significant hazards consideration under lOCFRS0.92.
The purpose of the power dependent rod insertion limits is threefold. First, rod insertion is limited in order
" ..
to ensure acceptable power distributions; second, to maintain minimum shutdown margin; and third, to minimize the effects of postulated rod ejection accident. Cycle specific calcula-tions are performed to evaluate and determine the power dependent insertion limits required to satisfy the above three requirements.
A Reload Safety Evaluation (RSE) for cycle 3 has been performed by-Westinghouse (Reference 1) and reviewed by PSE&G to deter-mine the impact of less restrictive (i.e. deeper) rod insertion limits. The results of the Westinghouse RSE show that the proposed limits do not cause the previously acceptable safety limits for any incident to be exceeded. PSE&G has reviewed this analysis and concurs with the Westinghouse~conclusions.
The PSE&G review consisted of performing an independent reload safety evaluation for cycle 3 using in-house computer codes, and it resulted in the determination that the current safety analysis design bases continue to be met. Operation of Salem Unit 2 in accordance with the proposed power dependent insertion limits:
0 would not involve a sigriificant increase in the proba-bility or consequences of an accident previously evaluated for Salem Unit 2, since the proposed change in PDIL showed that the current core safety limits were still applicable.
0 in no way creates the possibility of a new or different kind of accident from any accident previously evaluated for Salem Unit 2, since no plant modifications resulted from this change.
0 does not involve a significant reduction in any margin of safety.
0 is clearly within all acceptable criteria specified in the Standard Review Plan.
Based on the above evaluation we have determined that the proposed change in PDIL corresponds to example (vi) of guidance provided by the Commission in Federal Register 48FR 14870 for Amendments Likely To Not Involve Significant Hazards Consideration.
References
- 1. Reload Safety Evaluation for Salem Unit 2, Cycle 3; December 1984, Westinghouse Nuclear Fuel Division, M. M. Weber, A. N. Piplica, E. F. Pulver, M. E. Pohlman.