Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 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 LR-N990450, 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 Analyses1999-10-18018 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 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 LR-N990409, Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests1999-10-0707 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 ML18107A5401999-09-24024 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Sngs,Units 1 & 2 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 NTD-99-302, Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)1999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5371999-09-20020 September 1999 Forwards Insp Repts 50-272/99-06 & 50-311/99-06 on 990719-0806 (Region I-Inoffice) 990809-19 & 0901.NRC Has Determined That Three Violations of NRC Requirements Have Occurred.Violations Being Treated as non-cited 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 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 LR-N000420, Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 21999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 LR-N990405, Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources1999-09-13013 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 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 LR-N990392, 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 19991999-09-0808 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 LR-N990406, 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 Examinations1999-09-0808 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 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 LR-N990385, 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 Issues1999-08-26026 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 LR-N990396, Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided1999-08-26026 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 LR-N990363, 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 99-021999-08-23023 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 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 LR-N990389, 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 Bars1999-08-20020 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 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 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 LR-N990375, Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 11999-08-18018 August 1999 Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 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 LR-N990140, Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed1999-08-13013 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 ML18107A4701999-07-30030 July 1999 Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01 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 ML18107A4361999-07-16016 July 1999 Accepts Commitment to NRC Re Licensee Providing Clarification Concerning Licensing & Design Basis for 125 Vdc Battery Margins for Hope Creek & Salem Generating Stations for Meeting SBO & Loca/Loop Loading Requirements 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 ML18107A4251999-07-0606 July 1999 Forwards Insp Repts 50-272/99-04 & 50-311/99-04 on 990419-0529.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 LR-N990251, Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl 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 ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 LR-N990289, 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 & Discussion with NRC1999-06-25025 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 & Discussion with NRC ML18107A4141999-06-23023 June 1999 Forwards SE Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions, for Plant,Units 1 & 2 ML18107A3891999-06-23023 June 1999 Discusses Evaluation of Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Safety Evaluation Encl ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection LR-N990273, Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed1999-06-21021 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 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2101999-10-19019 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 ML18107A5401999-09-24024 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Sngs,Units 1 & 2 ML18107A5371999-09-20020 September 1999 Forwards Insp Repts 50-272/99-06 & 50-311/99-06 on 990719-0806 (Region I-Inoffice) 990809-19 & 0901.NRC Has Determined That Three Violations of NRC Requirements Have Occurred.Violations Being Treated as non-cited ML18107A4701999-07-30030 July 1999 Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01 ML18107A4361999-07-16016 July 1999 Accepts Commitment to NRC Re Licensee Providing Clarification Concerning Licensing & Design Basis for 125 Vdc Battery Margins for Hope Creek & Salem Generating Stations for Meeting SBO & Loca/Loop Loading Requirements ML18107A4251999-07-0606 July 1999 Forwards Insp Repts 50-272/99-04 & 50-311/99-04 on 990419-0529.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A3891999-06-23023 June 1999 Discusses Evaluation of Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Safety Evaluation Encl ML18107A4141999-06-23023 June 1999 Forwards SE Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions, for Plant,Units 1 & 2 ML18107A4201999-06-0404 June 1999 Informs That NRR Reorganized,Effective 990328.Organization Chart Encl ML18107A2751999-05-0303 May 1999 Forwards Insp Repts 50-272/99-03 & 50-311/99-03 on 990315- 19.No Violations Were Identified ML18107A2701999-04-30030 April 1999 Refers to Investigation Conducted by OI After Chemistry Supervisor at Salem Facility Made Change to Procedure Without Proper Review & Signed Record Indicating That Independent Verifications Had Been Performed ML18107A2161999-04-19019 April 1999 Forwards Ltr from Lg Canton,Regional Director,Fema Region II to Hj Miller,Nrc Region I,Forwarding FEMA Final Exercise Rept for 980303 Plume Exposure Pathway Exercise & 980505-07 Ingestion Pathway Exercise for Salem/Hope Creek Stations ML18107A1761999-04-15015 April 1999 Responds to 981019 & s Requesting Approval of Proposed Changes to QA Program,Per Section 17.2 of Respective UFSAR Per 10CFR50.54(a)(3).Forwards SE Re Changes to QA Program IR 05000311/19980121999-04-0707 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-311/98-12.Review of Effectiveness of Corrective Actions in Rept, as Part of Independent Assessment of RCS & LER Completed IR 05000272/19990011999-04-0101 April 1999 Forwards Insp Repts 50-272/99-01 & 50-311/99-01 on 990117-0307.No Violations Identified.Expresses Concern About Two Human Errors That Caused Plant Events,One Which Challenged Safety Sys ML18106B1091999-03-23023 March 1999 Forwards RAI Re NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML18106B0741999-02-18018 February 1999 Provides Authorization to Administer Written Exams to Listed Applicants on 990226 at Salem Generating Station,Hancocks Bridge,New Jersey.Nrc Region I Operator Licensing Staff Will Administer Operating Tests on 990222-25 & 990301-05 ML18106B0731999-02-11011 February 1999 Discusses Closure of TAC Re Generic Implication of part- Length Control Rod Drive Mechanism Housing Leak ML20206S5951999-02-0303 February 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Their Entirety ML18106B0181999-01-0707 January 1999 Forwards Request for Addl Info Re Proposed Amend That Would Modify TS Section 3/4 7.6, Control Room Emergency Air Conditioning Sys ML18106A9921998-12-18018 December 1998 Responds to Re Fire Protection Matl Used at Salem Nuclear Generating Station.In 1993,NRC Identified Deficiencies in Electrical Raceway Fire Barrier Sys at Which Time Compensatory Measures Were Put in Place ML20198H1851998-12-15015 December 1998 Responds to to President Clinton Re Rept by Gao, Issued 970530 on NRC Oversight of Nuclear Power Industry ML18106A9911998-12-0808 December 1998 Forwards Synopsis of Investigation Rept 1-98-013 Re Fire Protection Operator Falsified Six Daily Fire Insp Logs During Feb & March 1998.Concludes That Operator Deliberately Violated Fire Protection Program Procedures ML20198B7611998-12-0303 December 1998 Informs That on 981007,generic Fundamentals Exam Was Administered to 148 Candidates at 21 Facilities.Summary of Statistical Results of Exam Listed.Contents of Exam Along with Associated Input Data Needed for Updating Catalog Encl IR 05000272/19980081998-11-24024 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-08 & 50-311/98-08 ML18106A9751998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without Encl ML20155J7191998-11-0505 November 1998 Fourth Final Response to FOIA Request for Documents.Records Listed in App G Being Released in Entirety.Documents Listed in App H Being Withheld in Part (Ref FOIA Exemption 5) ML18106A9341998-10-22022 October 1998 Forwards SE Related to USI A-46 Program Implementation.Nrc Has Determined That Util Actions Completed & Proposed Resolution of Outlier Items Will Result in Safety Enhancements.Usi A-46 Program Complete IA-98-323, First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3)1998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML20154P4011998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML18106A8981998-10-0505 October 1998 Forwards SRO Initial Exam Repts 50-272/98-302 & 50-311/98-302 for Exams Conducted on 980914-24.All Three SRO Applicants Passed All Portions of Exams ML20154B3781998-09-25025 September 1998 Informs That Facility Scheduled to Administer NRC Generic Fundamentals Exam on 981007.Sonalysts,Inc Authorized Under Contract to Support NRC in Administration of Activities. Ltr & Encls Provide Instructions & Guidelines ML18106A8841998-09-24024 September 1998 Provides Individual Exam Results for Applicants on Initial Written Exam & Operating Tests Conducted at Salem Facility on 980914-17.W/o Encls ML18106A8701998-09-15015 September 1998 Forwards SE Accepting 960518 Request for Approval to Incorporate W WRB-2 Correlation Into Licensing Basis for Plant,Units 1 & 2 ML20151W9711998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Have Been Assigned as SRAs in Region I ML20151V8401998-09-10010 September 1998 Informs That Util Authorized to Administer Initial Written Exams to Listed Applicants on 980917.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 980914- 16 ML18106A8571998-09-0202 September 1998 Informs That Licensee 980310 Response to GL 97-05, Steam Generator Tube Insp Technique, Includes Info Requested. Staff Did Not Identify Any Concerns W/Techniques Employed at Plant Re Conformance W/Current Licensing Basis for Facility ML20238F1581998-08-31031 August 1998 Informs That as Result of Review of Records,Duplication of Costs Charged for Insp Conducted at Salem Unit 2 Was Found. Amount Overcollected Will Be Transferred to Licensee within 10 Days from Date of Ltr IR 05000272/19980051998-08-27027 August 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-05, 50-311/98-05 & 50-354/98-06 ML18106A8311998-08-21021 August 1998 Forwards Insp Repts 50-272/98-06 & 50-311/98-06 on 980622-0801.One Apparent Violation of Maint Procedure Requirements That Led to Failure to Meet TS Operability Requirements for AFW Sys,Identified.Nov Not Encl ML18106A8061998-08-0707 August 1998 Responds to Request for Statistics on Allegations Received by NRC Re Salem & Hope Creek.Encl Tables Provide Comparison to Allegations Received at Other Operating Sites for CY93-97 & First Seven Months of 1998 ML18106A7991998-08-0606 August 1998 Discusses Improved Std TS Guidance for Plants,Per Licensee ML18106A7941998-07-24024 July 1998 Summarizes Discussions Re Salem Units 1 & 2.Based on Discussions NRC Concluded That Plant Units 1 & 2 Have Sustained Improvement to Be Removed from NRC Watch List IR 05000272/19980031998-07-14014 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-03 & 50-311/98-03 ML18106A7031998-07-10010 July 1998 Forwards Insp Repts 50-272/98-05 & 50-311/98-05 on 980504-0621 & Nov.Violations Include Failure of Staff to Adhere to Established Procedures,Including Procedures Requiring 10CFR50.59 Reviews & Test Equipment Calibration IR 05000272/19982021998-07-0909 July 1998 Forwards Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Enclosure Contains Safeguards Info & Being Withheld Ref 10CFR73.21 ML18106A6991998-07-0808 July 1998 Forwards Senior Reactor Operator Retake Exam Repts 50-272/98-301(OL) & 50-311/98-301(OL) on 980626.Staff Administered Exam to One SRO Candidate Who Failed Initial Written Exam in Jan 1998.Candidate Passed & Issued License ML18106A6891998-07-0202 July 1998 Provides Individual Exam Result for Applicant on Initial Retake Written Exam Conducted at Salem Facility on 980626. Info Considered Proprietary in Accordance w/10CFR2.790.W/o Encls 1999-09-24
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Inspection Report - Salem - 1997018 |
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Text
January 8, 1998
SUBJECT:
Combined Inspection Report 50-272/97-18; 50-311/97-18
Dear Mr. Eliason:
This letter refers to your December 16, 1997 correspondence (LR-N970790), in response to our November 18, 1997 letter regarding the Salem Unit 1 & 2 facilities.
Thank you for informing us of the corrective and preventive actions for the Notice of Violation, as documented in your letter. The violation involved the inadvertent isolation of fire protection water to the Unit 1 and 2 auxiliary buildings and containments which degraded the post-fire safe shutdown capability of Salem Unit 2. Your response to the violation will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Docket Nos. 50-272; 50-311 9801160030 980108 PDR ADOCK 05000272 G
PDR
Sincerely, Original Signed By:
James C. Linville, Chief Projects Branch 3 Division of Reactor Projects 111111111111111111111111111111111 Ill llll
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L. Storz, Senior Vice President - Nuclear Operations E. Simpson, Senior Vice President - Nuclear Engineering E. Salowitz, Director - Nuclear Business Support D. Powell, Director - Licensing/Regulation & Fuels A. C. Tapert, Program Administrator J. McMahon, Director - Quality/Nuclear Training/Emergency Preparedness C. Bakken, General Manager - Salem Operations cc w/cy of Licensee's Letter:
A. F. Kirby, Ill, External Operations - Nuclear, Delmarva Power & Light Co.
Jeffrey J. Keenan, Esquire J. A. Isabella, Manager, Joint Generation Atlantic Electric Consumer Advocate, Office of Consumer Advocate William Conklin, Public Safety Consultant, Lower Alloways Creek Township R. Kankus, Joint Owner Affairs Public Service Commission of Maryland State of New Jersey State of Delaware
- Mr. Leon Distribution w/copy of Licensee's Response Letter:
Region I Docket Room (with concurrences)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector PUBLIC M. Leach, OEDO J. Stolz, PD1-2, NRR P. Milano, Project Manager, NRR M. Callahan, OCA J. Linville, DRP S. Barber, DRP D. Screnci, PAO C. O'Daniell, DRP R. Correia, NRR F. Talbot, NRR DOCDESK Inspection Program Branch, NRR (IPAS)
DOCUMENT NAME: G:\\BRANCH3\\9718RESP.LTR To receive a copy of this document, indicate in the box: "C" = Copy without attachmenUenclosure
"E" = Copy with attachmenUenclosure
"N" = No I
copy OFFICE Rl/DRP JI I
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I NAME JLinville/ceoctV I DATE 01/07/98
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01 I /98 01 I /98 01 I 198 01 I /98 OFFICIAL RECORD COPY
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Public Service Electrrc and Gas Company is F. Storz Public Servrce Electric and Gas ComDEC { j* ~gg]6* Hancocks Bridge. NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LR-N970790 RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT 50-272/97-18 AND 50-311/97-18 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
Combined Inspection Report No. 50-272/97-18 and 50-311/97-18 for Salem Nuclear Generating Station Unit Nos. 1 and 2 was transmitted to Public Service Electric & Gas Company (PSE&G) on November 18, 1997. Within the scope of this report, one violation of NRC requirements was cited. The violation involved; the inadvertent isolation of fire protection water to the Unit 1 and 2 auxiliary buildings and containments, which degraded the post-fire safe shutdown capability of Salem Unit 2.
Following the voluntary shutdown of May 1995, PSE&G recognized that a key attribute for a successful restart of the Salem Units, as well as the ability to safely and reliably operate the facilities, depended, in part, on being an Operations led organization. To this extent, PSE&G clearly defined what an Operations led organization meant, and in particular having the Operations Department take ownership and accountability of the Salem Plants. This expectation was clearly communicated to all personnel. To achieve this goal significant programs and actions were developed and implemented to establish and cultivate this new culture within the Operations Department. These programs and actions, which have been extensively shared with the NRC, included reorganizing the Operations Department, and placing new personnel at all levels of the department. The successful restart of Salem Unit 2, was in part due to the success of the Operations Department in having achieved this cultural change.
However, as noted in your inspection report, there have been occasions where individuals have failed to meet these expectations. Specifically, Operations personnel failed to properly control the work that was being performed in the control room by contractor personnel.
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Document Control Desk LR-N970790
DEC 1 6 1997 Although, we will continue to search for ways to improve our processes and programs to ensure safe operation, we will also continue to hold all of our personnel accountable for their actions in accordance with the PSE&G's disciplinary policy, and the Management Associated Results Company (MARC) principles. This positive approach to discipline is primarily focused on improving personnel performance. This is accomplished through a multi-stage approach of providing direct employee feedback for their actions via coaching, counseling, verbal and written feedback. Termination of employment is also an option for failure to meet the fundamental expectations.
Additional corrective actions are included in Attachment I to this letter.
In accordance with 1 O CFR 2.201, PSE&G is submitting its response to the cited violation in Attachment I to this letter. Should there be any questions regarding this submittal, please contact us.
Sincerely, Attacrent ( 1 )
C J 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 Ms. M. Evans - Salem (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering PO Box415 Trenton, NJ 08625
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ATTACHMENT I RESPONSE TO NOTICE OF VIOLATION LR-N970790 Public Service Electric and Gas Company Salem Nuclear Generating Station Docket Nos:
Units 1 and 2 License Nos:
50-272 50-311 DPR-70 DPR-75 During an NRC inspection conducted from September 8, 1997 through October 19, 1997, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
A.
License Conditions 2.C(5) (Unit 1) and 2.C(10) {Unit 2) require that the licensee implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (UFSAR).
UFSAR, Section 9.5.1.4.1, describes systems and components which are necessary for post-fire safe shutdown of Salem Units 1 and 2, including the auxiliary feedwater (AFW) pumps and other safety-related equipment. UFSAR Section 9.5.1. 7.2, describes the water-based fire suppression systems which are utilized at Salem Units 1 and 2, and the components which they protect. For example, the AFW pumps are protected by two water sprinkler systems.
Procedure SC.FP-SV.FS-003(0), "Fire Water Flowpath Verification," requires that the fire protection isolation valves to the Unit 1 and 2 auxiliary building and containments, 1FP186and1FP187, be in the open_position.
Contrary to the above, from approximately September 9-16, 1997, valves 1FP186 and 1FP187 were closed, which isolated all fire protection water to the Salem Unit 1 and 2 auxiliary buildings and containments. This isolated water to the water-based suppression systems in those buildings, rendering the systems inoperable, and adversely affecting the licensee's ability to achieve and maintain safe shutdown in the event of a fire.
This is a Severity Level IV violation (Supplement 1 ).
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ATTACHMENT I RESPONSE TO NOTICE OF VIOLATION LR-N970790 PSE&G concurs with the violation (1)
The reason for the violation.
The exact cause of how the 1FP186 and 1FP187 valves were closed, and could have potentially been closed from September 1, 1997, through September 16, 1997, could not be determined. These dates represent the times when the 1FP186 and 1FP187 valves were field verified open by Loss Prevention personnel. However from a timeline of the events developed during the root cause investigation, the most probable cause for the inadvertent closure of the 1FP186 and 1FP187 valves was rel amping activities on 1 RPS panel on September 9, 1997. Therefore, the cause of this occurrence is attributed to inadequate control of the 1 RPS relamping maintenance activity by Operations.
Shift personnel, particularly the Control Room Supervisor, failed to exercise adequate control over work in the control room. Specifically, the supervisor allowed a contract maintenance technician to relamp control switch assemblies on 1 RPS without direct Operations supervision.
The cause for this condition going unidentified for the period from September 9, 1997, through September 16, 1997 is attributed to human error due to inattention to detail by the Nuclear Control Operators and the Loss Prevention Operators during subsequent panel reviews. The reviews did not focus on valve position indication, but were focused on verification of alarm status and lamp functionality.
(2)
The corrective steps that have been taken.
The valves were opened at 2237 hrs on September 16, 1997, and locally verified open by Loss Prevention personnel at 2243 hrs.
An event notice was issued to Operations, Work Control, Loss Prevention and Station Planning to share the lessons learned from this event.
On September 18, 1997, Loss Prevention personnel completed a lineup verification of Fire Protection valves (C02 and Water) at Salem station, and as a temporary compensatory measure, initiated position verification of the 1FP186 and 1FP187 valves on a twice per shift (every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) basis pending completion of the revision of procedure ND.FP-DD.ZZ-0014(Z), "Conduct of Shift Turnovers."
- ATIACHMENTI RESPONSE TO NOTICE OF VIOLATION LR-N970790 On October 24, 1997, S1.0P-DL.ZZ-0002(Q), "Control Room Log - Mode S, 6 and Defueledn was revised to include a twice per shift verification of the position of 1FP186 and 1FP187 by the Unit 1 Control Room Operator. This corrective action may be removed upon completion of procedure ND. FP-DD.ZZ-0014(Z) revision.
Procedure ND.FP-DD.ZZ-0014(Z), "Conduct of Shift Turnovers" was revised to include verification of the 1FP186 and 1FP187 indicator lamp once per shift at the 1 RPS panel, and a once per shift verification of actual valve position.
In accordance with the PSE&G disciplinary process, Operations personnel involved in allowing maintenance workers to relamp 1 RPS without direct Operations supervision were held accountable for their actions.
(3)
The corrective steps that will be taken to avoid further violations.
Operators received training on the controls associated with the 1FP186 and 1FP187 valves. Additionally, the Nuclear Training Center was requested to provide licensed operators training on the controls associated with Fire Protection equipment and the License Commitments relative to Fire Protection.
The following corrective actions are intended to address the expectations identified in the cover letter for this response.
The Operations Superintendents or appropriate operations personnel will assess shift compliance with SC.OP-AP.ZZ-0114, Rev. 0, "Event Identification and Investigation,"
particularly with regard to the use of critiques and supervisor interviews, and arrange for (or perform) additional training as necessary. This activity will be completed by January 31, 1998.
Appropriate management personnel will discuss with their crews (operations, planning and loss prevention personnel) the lessons learned from this event regarding NC.NA-AP.ZZ-OOOS(Q), "Station Operating Practices," department ownership of the plant and control of maintenance activities. This activity will be completed by January 30, 1998.
(4)
The date when full compliance will be achieved.
PSE&G achieved compliance when the valves were opened at 2237 hrs on September 16, 1997, and locally verified open by Loss Prevention personnel at 2243 hrs.
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