Responds to NRC 980710 Ltr Re Violations Noted in Insp Repts 50-272/98-06,50-311/98-06 & 50-354/98-06,respectively. Corrective Actions:Personnel Involved in Events Will Be Held Accountable IAW Pse&G Policies & Revised ProceduresML18106A801 |
Person / Time |
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Site: |
Salem, Hope Creek |
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Issue date: |
08/03/1998 |
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From: |
Storz L Public Service Enterprise Group |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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50-272-98-06, 50-272-98-6, 50-311-98-06, 50-311-98-6, 50-354-98-06, 50-354-98-6, LR-N980367, NUDOCS 9808110027 |
Download: ML18106A801 (9) |
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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
[Table view] |
Text
Public Service Electric and Gas Company Louis F. Storz Public SeNice Electric and Gas Company . P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations AUG 03 1998 LR-N980367 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT 50-272/98-05, 50-311/98-05 AND 50-354/98-06 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Combined Inspection Report No. 50-272/98-05 and 50-311/98-05 for Salem Nuclear Generating Station Unit Nos. 1 and 2 was transmitted to Public Service Electric & Gas Company (PSE&G) on July 10, 1998. Within the scope of this report, two violations of NRC requirements were cited. The violations were cited against Technical Specification 6.8.1.a, and involved failures to (1) implement procedures; and (2) establish written procedures to collect drinking water, fish, and invertebrate samples.
Violation Bas stated in Appendix A to Inspection Report 50-272/98-05 and 50-311/98-05 is also described within the body of the Inspection Report as applicable to the Hope Creek Generating Station and identified as VIO 50-354/98-06-01. Therefore the response to violation B is applicable to all three-docket numbers.
In accordance with 10 CFR 2.201, PSE&G is submitting its response to the cited violations in Attachment 2 to this letter. Attachment 1 contains the Notice of Violation as cited by the NRC. Should there be any questions regarding this submittal, please contact us.
Attachments (2) ----11,;D I \ \
9808110027 980803 PDR ADOCK 05000272 G
Printed on
~ Recycled Paper PDR
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AUG 03 1998 Document Control Desk LR-N980367 C Mr. Hubert J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission
- One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. R. Ennis, Licensing Project Manager - Hope Creek U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. S. Morris - Salem (X24)
USNRC Senior Resident Inspector Mr. S. Pindale - Hope Creek (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trentqn, NJ 08625
ATTACHMENT 1 LR-N980367 APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Docket Nos:50-272 Salem Nuclear Generating Station 50-311
. Units 1 and 2 License Nos: DPR-70 DPR-75 During an NRC inspection conducted between May 24, 1998 and June 21, 1998, violations of NRC requirements were identified. In accordance with the General Statement of Policy and Procedure for NRC Enforcement Actions, NUREG-1600, the violations are listed below:
A Technical Specification 6.8.1.a requires in part that written procedures shall be implemented covering the activities described *in Appendix A of Regulatory Guide (RG) 1.33, Revision 2, dated February 1978. RG 1.33 requires procedure review and approval, safety-related equipment control, and measuring and test equipment calibration procedures. The following PSE&G procedures implement.these RG requirements, respectively:
NC.NA-AP.ZZ-0059 (NAP-59), section 5.2 requires that 10 CFR 50.59 applicability reviews be performed for proposed procedure revisions to determine whether a safety evaluation is necessary.
NC.NA-AP.ZZ-0083 (NAP-83), section 5.2 requires that free-standing equipment in safety-related areas be either restrained or evaluated for use under design basis seismic conditions.
- NC.NA-AP.ZZ-0022 (NAP-22), section 3.7 requires that the calibration of measuring and test equipment be current prior to use.
Contrary to the above, on May 4, 1998, NRC inspectors identified examples of failures to implement these procedures, specifically:
Procedure writers failed to perform a 10 CFR 50.59 applicability review and safety evaluation for a revision to procedure SC.MD-CM.ZZ-0024, lnservice Single Cell Battery Charging, as required by NAP-59 .
ATTACHMENT 1 LR-N980367 Maintenance technicians failed to ensure that a portable battery charger used for a single cell charge on a vital DC battery was properly restrained in or evaluated for use in this safety-related area as required by NAP-83.
Maintenance technicians failed to ensure that voltage and current meters on a portable battery charger used for a single cell charge on a vital DC battery were properly calibrated as required by NAP-22.
This is a Severity Level IV violation (Supplement I).
B. Technical Specification (TS) 6.8.1.i requires in part that written procedures shall be established for Offsite Dose Calculation Manual (ODCM) implementation. Section 4.1 of the ODCM describes the sampling program objectives of the Radiological Environmental Monitoring Program (REMP), and states that the operational phase of the REMP is conducted in accordance with the requirements of TS 3.12. TS 3.12 requires that drinking water, fish, and invertebrate samples be collected.
Contrary to the above, prior to June 12, 1998, PSE&G had not established written procedures to collect drinking water, fish, and invertebrate samples.
This is a Severity Level IV violation (Supplement IV) .
ATTACHMENT 2 LR-N980367 RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT 50-272/98-05, 50-311/98-05 AND 50-354/98-06 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 PSE&G RESPONSE TO VIOLATION A PSE&G concurs with the violation.
(1) The reason for the violation.
The reason for the violation is attributed to personnel error, in that personnel involved in these events failed to properly implement and follow the applicable procedures.
A. NC.NA-AP.ZZ-0059 (NAP-59) example.
Personnel failed to perform adequate 10CFR50.59 applicability reviews during past revisions of the maintenance procedure for single cell battery charging. Although the isolation requirements in the original Salem single cell charging procedure may not
- have been adequate, 10CFR50.59 applicability reviews for changes to the isolation requirements during past procedure revisions* did not adequately assess all requirements for connecting a non class-1 E battery charger to an operable class-1 E battery. Although this event is attributed to personnel error, a contributing factor to this violation was a weak 10CFR50.59 program when these revisions took place in 1994.
Since then, improvements have been made to the 10CFR50.59 program B. NC.NA-AP.ZZ-0083 (NAP-83) example.
Maintenance technicians and supervisors failed to properly implement the requirements of NAP-83, in that the battery charger was not properly restrained, or evaluated for its impact on the safety related battery. A contributing factor to this violation was weak knowledge of the requirements of NAP-83 by maintenance personnel, including supervision.
C. NC.NA-AP.ZZ-0022 (NAP-22), example.
Maintenance technicians failed to properly implement the requirements of NAP-22, in that they did not ensure that the installed instrumentation was properly calibrated prior to its use. A contributing factor to this violation was the lack of clarity in the requirements of procedure SC.MD-CM.ZZ-0024(0), "lnservice Single Cell Battery Charging." Specifically, the procedure did not clearly identify the Measuring and Test Equipment (M&TE) instrumentation requirements for voltage and current readings.
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ATTACHMENT 2 LR-N980367 RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT 50-272/98-05, 50-311/98-05 AND 50-354/98-06 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 The maintenance technicians properly recorded the voltage reading using the proper M&TE instrumentation called for by the maintenance procedure, which is the reading taken to determine proper charging of the battery cell. However, the current readings, which are taken in accordance with Attachment 4 of the procedure, and are taken for trending purposes only (and not part of the acceptance criteria), were taken utilizing the installed amp meter without verifying proper calibration.
(2) The corrective steps that have been taken.
Personnel involved in all examples and still employed by PSE&G have been held or will be held accountable in accordance with PSE&G policies.
Example A - NC.NA-AP.ZZ-0059 (NAP-59)
- 1. A self-assessment of the 50.59 process was performed in early 1996 to address concerns relative to the quality and overall condition of the 50.59 program. As result of the self-assessment, and other continuing improvements to the program a number of corrective actions have been implemented. These actions improved the quality of the process. Some of these actions are listed below:
The administrative procedure was revised to eliminate misleading examples and to include good practices from other facilities, and 10CFR50.59 process has been improved by establishing formal training and
. requalification requirements for 10CFR50.59 preparers, peer reviewers, and approvers.
- 2. The failure to perform an adequate 50.59 review was included in the June 1998 50.59 Newsletter for general communication purposes.
Example B - NC.NA-AP.ZZ-0083 (NAP-83)
The battery charger was promptly removed from the battery room on May 4, 1998.
ATTACHMENT 2 LR-N980367 RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT 50-272/98-05, 50-311/98-05 AND 50-354/98-06 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Example C - NC.NA-AP.ZZ-0022 (NAP-22)
- Procedure SC.MD-CM.ZZ-0024 (Q) was placed on administrative hold on May 11, 1998, to prevent use of the procedure. This procedure will remain inactive until satisfactory resolution *Of the proper isolation of the single cell battery charger from the Class -1 E battery.
(3) The corrective steps that will be taken to avoid further violations.
Example A- NC.NA-AP.ZZ-0059 (NAP-59)
- 1. This issue will be included* in the next two-year cycle of 10CFR50.59 refresher training starting in July 1998.
- 2. The "10CFR50.59 Program Guidance" procedure, NC.NA-AS.ZZ-0059, will be revised to include examples concerning the connection of temporary equipment to operable systems as added guidance, when performing 10CFR50.59 reviews. The procedure will be revised by August 31., 1998.
- 3. A review of maintenance procedures is being performed to determine if other procedures allow temporary equipment to be installed on operable systems. If maintenance procedures exist that connect temporary equipment to operable systems, a review will be performed to determine if the effect of the temporary equipment on system operation has been properly evaluated. This review will be completed by August 7, 1998.
Example B - NC.NA-AP.ZZ-0083 (NAP-83)
The requirements of NAP-83 will be reviewed in the in-service training of maintenance personnel. This training will be completed by S~ptember 30, 1998.
Example C - NC.NA-AP.ZZ-0022 (NAP-22)
Procedure SC.MD-CM.ZZ-0024 (Q) will be revised to clarify the M&TE requirements for voltage and current readings. This revision will be in place prior to SC.MD-CM.ZZ-0024 (Q) being re-activated.
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ATTACHMENT 2 LR-N980367 RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT 50-272/98-05, 50-311/98-05 AND 50-354/98-06 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 (4) The date when full compliance will be achieved.
PSE&G achieved compliance on May 4, when the battery charger was removed from the battery room and achieved full compliance on May 11, 1998, when procedure SC.MD-CM.ZZ-0024 (Q) was placed in an inactive status.
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ATTACHMENT 2 LR-N980367 RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT 50-272/98-05, 50-311/98-05 AND 50-354/98-06 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 PSE&G RESPONSE TO VIOLATION B PSE&G concurs with the violation (1) The reason for the violation.
The apparent cause for the violation is attributed to an organizational deficiency in the implementation of the Offsite Dose Calculation Manual/Rad.iological Effluent Monitoring Program (ODCM/REMP). The organizations responsible for the implementation of the ODCM did not ensure that the Technical Specification required procedures for compliance with the sampling program objectives of the REMP were in place for the portions of the ODCM that were implemented by vendors Although written procedures had not been established to collect drinking water, fish, and invertebrate samples, none of these samples were missed.
(2) The corrective steps that have been taken.
- 1. The ODCM has been reviewed, and procedures exist to implement the remainder of the ODCM.
- 2. The organizational deficiency has been addressed via our Corrective Action Program, clear program oversight and ownership has been established.
(3) The corrective steps that will be taken to avoid further violations.
A procedure will be developed to provide direction to vendors for use in collecting drinking water, fish, and invertebrate samples. This procedure will be issued by September 30, 1998 prior to the next scheduled sample collection.
(4) The date when full compliance will be achieved.
PSE&G will achieve full compliance by September 30, 1998, when the procedure to provide direction to vendors for use in collecting drinking water, fish, and invertebrate samples will be issued prior to the next scheduled sample collection.
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