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| {{#Wiki_filter:. * * ' / *, Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President | | {{#Wiki_filter:.* |
| -Nuclear Operations JUL 211994 NLR-N94064 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: | | ' / *, Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations JUL 211994 NLR-N94064 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: |
| ASME CODE CASE N-508 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Public Service Electric and Gas Company (PSE&G) requests approval, per 10CFR.50.55a, Section (a) (3) and footnote 6, to use ASME Code Case N-508 (copy attached) for Salem and Hope Creek Generating Stations. | | ASME CODE CASE N-508 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Public Service Electric and Gas Company (PSE&G) requests approval, per 10CFR.50.55a, Section (a) (3) and footnote 6, to use ASME Code Case N-508 (copy attached) for Salem and Hope Creek Generating Stations. This ASME Section XI Code Case entitled,"Rotation of Serviced Snubbers and Pressure Relief Valves for the Purposes of Testing," was approved by ASME and published on March 11, 1993. The use of this Code Case is not presently referenced in NRC Regulatory Guide 1.147,"Inservice Inspection Code Case Acceptability," Revision 10, dated July 1993. |
| This ASME Section XI Code Case entitled,"Rotation of Serviced Snubbers and Pressure Relief Valves for the Purposes of Testing," was approved by ASME and published on March 11, 1993. The use of this Code Case is not presently referenced in NRC Regulatory Guide 1.147,"Inservice Inspection Code Case Acceptability," Revision 10, dated July 1993. Code Case N-508 provides an alternative to the current Section XI, Paragraph IWA-7000 requirements to generate a replacement plan when removing snubbers or pressure relief valves for testing. PSE&G's Code Job Package (CJP) is the equivalent of the Section XI replacement plan. As an alternative to this replacement plan (i.e., PSE&G CJP), nine requirements must be met {Code Case items (a) thru (i)). PSE&G intends to meet all of these requirements. | | Code Case N-508 provides an alternative to the current Section XI, Paragraph IWA-7000 requirements to generate a replacement plan when removing snubbers or pressure relief valves for testing. PSE&G's Code Job Package (CJP) is the equivalent of the Section XI replacement plan. As an alternative to this replacement plan (i.e., PSE&G CJP), nine requirements must be met |
| Code Case item (f) requires a separate mechanism for tracking snubbers and pressure relief valves, which ensures traceability of Inservice Inspection | | {Code Case items (a) thru (i)). PSE&G intends to meet all of these requirements. |
| {ISI) and testing records. PSE&G's ISI group utilizes a computer data base program to track the current test results of all snubbers by type, rating and serial number. This data base provides specifics identifying a snubbers physical plant location at any point in time. This program has been used by PSE&G for several years and is far more efficient than a CJP for providing test result traceability. | | Code Case item (f) requires a separate mechanism for tracking snubbers and pressure relief valves, which ensures traceability of Inservice Inspection {ISI) and testing records. PSE&G's ISI group utilizes a computer data base program to track the current test results of all snubbers by type, rating and serial number. I' This data base provides specifics identifying a snubbers physical plant location at any point in time. This program has been used by PSE&G for several years and is far more efficient than a CJP for providing test result traceability. A similar independent tracking mechanism will be used by the InserVice Testing (IST) group for relief valves prior to application of Code Case N-508. |
| A similar independent tracking mechanism will be used by the InserVice Testing (IST) group for relief valves prior to application of Code Case N-508. These mechanisms will satisfy item (f) of Code Case N-508. -------- | | These mechanisms will satisfy item (f) of Code Case N-508. |
| 9407290158 PDR ADOCK PDR p I' | | ---- --- - --~. |
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| | 9407290158 6~866§72 PDR ADOCK PDR p |
| * Do*ument Control Desk NLR-N94064 2 Each PSE&G CJP requires a significant effort by several PSE&G organizations (Maintenance, Technical, ISI and QA). Generating a separate CJP for each snubber or relief valve removed for testing does not provide improved quality or safety. Code Case N-508, through the elimination of the added work necessary to prepare CJPs, would substantially reduce the resources expended by various station groups, particularly during outages when the requisite testing and possibility of expanded testing exists. This Code Case does not create any technical or administrative changes that would impact the existing Salem or Hope Creek: ISI Programs, IST Programs, or Technical Specifications.
| | |
| Also, it does not introduce a condition that would compromise existing levels of quality or safety. PSE&G considers this submittal a Cost Beneficial Licensing Action (CBLA). We have estimated the cost savings as $4k/yr at each | | t; Doument Control Desk 2 |
| * Salem Unit and $22k/yr at Hope Creek. Savings over the life of the plants is $88k Salem Unit 1, $104k Salem Unit 2 and $704k Hope Creek. Should you have any questions on this transmittal, please contact us. c Mr. T. T. Martin, Administrator | | ~UL211994 NLR-N94064 Each PSE&G CJP requires a significant effort by several PSE&G organizations (Maintenance, Technical, ISI and QA). Generating a separate CJP for each snubber or relief valve removed for testing does not provide improved quality or safety. Code Case N-508, through the elimination of the added work necessary to prepare CJPs, would substantially reduce the resources expended by various station groups, particularly during outages when the requisite testing and possibility of expanded testing exists. |
| -Regi u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager -Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 | | This Code Case does not create any technical or administrative changes that would impact the existing Salem or Hope Creek: ISI Programs, IST Programs, or Technical Specifications. Also, it does not introduce a condition that would compromise existing levels of quality or safety. |
| ,, ,, * * -N-508 CASES OF ASME BOILER AND PRESSURE VESSEL CODE
| | PSE&G considers this submittal a Cost Beneficial Licensing Action (CBLA). We have estimated the cost savings as $4k/yr at each |
| * Approval Date: March 11, 1993 See Numerical Index for expiration and any reaffirmation dates. Case N-508 Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing Section XI, Division 1 Inquiry: What alternative rules to those stated in r.w A-7000 may be used when, for the purpose of testing, snubbers and pressure relief valves are tated from stock and installed on components (including piping systems) within the Section XI boundary?
| | * Salem Unit and $22k/yr at Hope Creek. Savings over the life of the plants is $88k Salem Unit 1, $104k Salem Unit 2 and $704k Hope Creek. |
| * Reply: It is the opinion of the Committee that, as an alte111ative to the provisions of IW A-7000 and for the purpose of testing, snubbers and relief valves may be rotated from stock and installed on components (including piping systems) within the Section XI boundary provided the -following -requirements are met: (a) Items being removed and installed shall be of the same design and construction; (b) Items being removed shall have no evidence of failure at the time of removal; (c) Items being rotated shall be removed and installed only by mechanical means; (d) Items being installed shall previo.usly have been in service; (e) Preservice inspections and pressure tests shall be performed as required by r.w A-7000; (f) The Owner shall maintain a method of tracking the items to ensure traceability of inservice tion and testing records; (g) Use of an NIS-2 form is not required except as in (i) below; (h) Testing of removed snubbers and pressure lief **alves, including required sample expansions, shall be performed in accordance with the Owner's test program; (i) Repair or replacement of removed items, when_
| | Should you have any questions on this transmittal, please contact us. |
| shall be performed in accordance with IWA-4000 or IWA-7000. | | c Mr. T. T. Martin, Administrator - Regi |
| 876.1 SUPP. 4 -NC}} | | : u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09) |
| | USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 |
| | |
| | CASES OF ASME BOILER AND PRESSURE VESSEL CODE |
| | - N-508 Approval Date: March 11, 1993 See Numerical Index for expiration and any reaffirmation dates. |
| | Case N-508 (a) Items being removed and installed shall be of Rotation of Serviced Snubbers and Pressure Relief the same design and construction; Valves for the Purpose of Testing (b) Items being removed shall have no evidence of Section XI, Division 1 failure at the time of removal; (c) Items being rotated shall be removed and installed only by mechanical means; (d) Items being installed shall previo.usly have Inquiry: What alternative rules to those stated in been in service; r.wA-7000 may be used when, for the purpose of (e) Preservice inspections and pressure tests shall testing, snubbers and pressure relief valves are ro-be performed as required by r.wA-7000; tated from stock and installed on components (f) The Owner shall maintain a method of tracking (including piping systems) within the Section XI the items to ensure traceability of inservice inspec-boundary? |
| | * tion and testing records; (g) Use of an NIS-2 form is not required except as provicl~d in (i) below; Reply: It is the opinion of the Committee that, as (h) Testing of removed snubbers and pressure re-an alte111ative to the provisions of IWA-7000 and for lief **alves, including required sample expansions, the purpose of testing, snubbers and relief valves may shall be performed in accordance with the Owner's be rotated from stock and installed on components test program; (including piping systems) within the Section XI (i) Repair or replacement of removed items, when_ |
| | boundary provided the -following -requirements are r~quired, shall be performed in accordance with met: IWA-4000 or IWA-7000. |
| | 876.1 SUPP. 4 - NC}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999 Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217H8471999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station ML20217H9771999-10-13013 October 1999 Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR ML20217A6861999-10-0101 October 1999 Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl ML20217K7781999-09-16016 September 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of Aug 1999. Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML20211N5421999-09-0808 September 1999 Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML20211B5341999-08-20020 August 1999 Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML20210R4911999-08-11011 August 1999 Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys ML20210F3271999-07-22022 July 1999 Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML20210D3971999-07-16016 July 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl ML20209G2831999-07-14014 July 1999 Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 ML20196E6471999-06-21021 June 1999 Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted ML20196E9631999-06-17017 June 1999 Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5 LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999 Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511 05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999 Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness 1999-09-08
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' / *, Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations JUL 211994 NLR-N94064 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
ASME CODE CASE N-508 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Public Service Electric and Gas Company (PSE&G) requests approval, per 10CFR.50.55a, Section (a) (3) and footnote 6, to use ASME Code Case N-508 (copy attached) for Salem and Hope Creek Generating Stations. This ASME Section XI Code Case entitled,"Rotation of Serviced Snubbers and Pressure Relief Valves for the Purposes of Testing," was approved by ASME and published on March 11, 1993. The use of this Code Case is not presently referenced in NRC Regulatory Guide 1.147,"Inservice Inspection Code Case Acceptability," Revision 10, dated July 1993.
Code Case N-508 provides an alternative to the current Section XI, Paragraph IWA-7000 requirements to generate a replacement plan when removing snubbers or pressure relief valves for testing. PSE&G's Code Job Package (CJP) is the equivalent of the Section XI replacement plan. As an alternative to this replacement plan (i.e., PSE&G CJP), nine requirements must be met
{Code Case items (a) thru (i)). PSE&G intends to meet all of these requirements.
Code Case item (f) requires a separate mechanism for tracking snubbers and pressure relief valves, which ensures traceability of Inservice Inspection {ISI) and testing records. PSE&G's ISI group utilizes a computer data base program to track the current test results of all snubbers by type, rating and serial number. I' This data base provides specifics identifying a snubbers physical plant location at any point in time. This program has been used by PSE&G for several years and is far more efficient than a CJP for providing test result traceability. A similar independent tracking mechanism will be used by the InserVice Testing (IST) group for relief valves prior to application of Code Case N-508.
These mechanisms will satisfy item (f) of Code Case N-508.
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9407290158 6~866§72 PDR ADOCK PDR p
t; Doument Control Desk 2
~UL211994 NLR-N94064 Each PSE&G CJP requires a significant effort by several PSE&G organizations (Maintenance, Technical, ISI and QA). Generating a separate CJP for each snubber or relief valve removed for testing does not provide improved quality or safety. Code Case N-508, through the elimination of the added work necessary to prepare CJPs, would substantially reduce the resources expended by various station groups, particularly during outages when the requisite testing and possibility of expanded testing exists.
This Code Case does not create any technical or administrative changes that would impact the existing Salem or Hope Creek: ISI Programs, IST Programs, or Technical Specifications. Also, it does not introduce a condition that would compromise existing levels of quality or safety.
PSE&G considers this submittal a Cost Beneficial Licensing Action (CBLA). We have estimated the cost savings as $4k/yr at each
- Salem Unit and $22k/yr at Hope Creek. Savings over the life of the plants is $88k Salem Unit 1, $104k Salem Unit 2 and $704k Hope Creek.
Should you have any questions on this transmittal, please contact us.
c Mr. T. T. Martin, Administrator - Regi
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
CASES OF ASME BOILER AND PRESSURE VESSEL CODE
- N-508 Approval Date: March 11, 1993 See Numerical Index for expiration and any reaffirmation dates.
Case N-508 (a) Items being removed and installed shall be of Rotation of Serviced Snubbers and Pressure Relief the same design and construction; Valves for the Purpose of Testing (b) Items being removed shall have no evidence of Section XI, Division 1 failure at the time of removal; (c) Items being rotated shall be removed and installed only by mechanical means; (d) Items being installed shall previo.usly have Inquiry: What alternative rules to those stated in been in service; r.wA-7000 may be used when, for the purpose of (e) Preservice inspections and pressure tests shall testing, snubbers and pressure relief valves are ro-be performed as required by r.wA-7000; tated from stock and installed on components (f) The Owner shall maintain a method of tracking (including piping systems) within the Section XI the items to ensure traceability of inservice inspec-boundary?
- tion and testing records; (g) Use of an NIS-2 form is not required except as provicl~d in (i) below; Reply: It is the opinion of the Committee that, as (h) Testing of removed snubbers and pressure re-an alte111ative to the provisions of IWA-7000 and for lief **alves, including required sample expansions, the purpose of testing, snubbers and relief valves may shall be performed in accordance with the Owner's be rotated from stock and installed on components test program; (including piping systems) within the Section XI (i) Repair or replacement of removed items, when_
boundary provided the -following -requirements are r~quired, shall be performed in accordance with met: IWA-4000 or IWA-7000.
876.1 SUPP. 4 - NC