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 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 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 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 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 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. 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 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 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 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 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 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 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 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 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 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 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 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 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 ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 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 ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 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 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 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 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) 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 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 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 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 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 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 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 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 ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek 1999-09-08
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- Louis F. Storz Senior Vice President - Nuclear Operations Public Service Electric and Gas Company Public Service Electric and Gas Company SEP 2 8 1995 P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 LR-N95162 United States Nuclear Regulatory Commission Document *control Desk Washington, DC 20555 Gentlemen:
REQUALIFICATION TRAINING PROGRAM INSPECTION INSPECTION REPORT 50-272/95-08 AND 50-311/95-08 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In NRC Inspection Report Nos. 50-272/95-08 and 50-311/95-08, dated June 2, 1995, the NRC expressed.concern over the manner in which, during the development of the annual operator examinations, an individual- signed an examin~tion security agreement which the individual and his supervisor did not fully
Public Service Electric & Gas (PSE&G) was requested to provide it's evaluation of this incident, including the root cause, and corrective actions to address this concern. Accordingly, in the attachment to this letter, PSE&G has provided the requested information.
Should you have any questions regarding this submittal, we will be pleased to discuss them with you.
Sincerely,
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Document Control Desk SEP 2 8 1995 LR-N95162 Attachment (1)
C Mr. T. T. --Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. D. H. Jaffe Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. S. Marschall (S09)
USNRC Senior Resident Inspector - Salem Mr. R. W. Summers (S09)
USNRC Senior Resident Inspector - Hope Creek Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933
Document Control Desk LR-N95162 ATTACHMENT 1 REQUALIFICATION TRAINING PROGRAM INSPECTION I. BACKGROUND While preparing for the Salem Operator Requalif ication exam, it was identified that recent personnel assignments and staffing changes had created a condition where two normally exclusive tasks needed to be accomplished by one ind_i vi dual. The two tasks were the development and validation of operator requalif ication exams and instruction of the requalification class.
Identification of this condition prompted a meeting between the Principal Training Supervisor and Principal Trainer - *operations Training. They discussed current personnel assignments and qualifications. It was determined that one instructor could perform both tasks without compromising examination integrity. The following actions were taken:
The instructor would validate several examination scenarios for the requallfication cycle. The instructor would not kno~ specifically what scenarios would be given to which crew .
- The instructor was provided verbal instructions on which modules and activities he could teach. The instructor was told that questions on material not identified for him to teach would have to be referred to other individuals on the instruction staff.
The above solution was proposed to the Manager - Nuclear Training who agreed to the arrangement. The Manager - Nuclear Training based this decision on a *review of ES-601 NRC Examiners Standards.
- I t was known that this document did not apply but, it was reviewed for guidance purposes. A review of form ES-601-1 was not part of this review. Additional considerations by the Manager - Nuclear Training included his knowledge of similar arrangements in use at other utilities and that the proposed plan was reasonable for preventing a compromise of examination security.
During the NRC inspection of the Requalif ication Training Program, an NRC Inspector noted the situation where the instructor was involved in validation of operator requalification exams and instruction of the requalification class. However, the inspectors discovered that the ES-601-1 security agreement form (which was signed by the instructor) specifically prohibited an individual from participating in the validation and training process.
Document Control Desk LR-.N95162 Until noted by the NRC inspector, the Principal Training Supervisor, Principal Trainer - Operations Training and the instructor were not aware of any restrictions on form ES-601-1 which specifically precluded an individual from participating in the validation and training process.
- II. ROOT CAUSE/CORRECTIVE ACTIONS The Barrier Analysis method was used to determine root cause based on the guidance provided in PSE&G procedure NC.NA-BP.ZZ-0002(Z),
Root Cause Analysis Guideline. Barrier Analysis was chosen because people committed inappropriate actions relative to procedural controls.
A. ROOT CAUSE Repetitive use of the ES-601-1 security agreement form for non-NRC administered requalif ication exams has resulted in a casual acceptance of the intent of the form. This helped to promote an atmo$phere where specific form content was not thoroughly reviewed when making decisions concerning examination security.
This event is categorized as a procedure noncompliance issue due to overconfidence by the individuals involved with respect to the form content and intent.
- 1. Supervisory personnel did not review the ES-601-1 security agreement when deciding on their course of action concerning the responsibilities of the instructor.
- 2. Several personnel stated they knew that they could not discuss exam content with individuals as part of the ES-601-1 security agre~ment. However, at the time of this event, they could not have specifically identified the ES-601-1 security agreement for instruction restriction after test validation. *some of these individuals had signed recent security agreements as part of the requalification examination administration.
- 3. Current practices require some individuals to sign the ES-601-1 security agreement several times during the conduct of the requalification cycle. This may help promote an atmosphere where only a cursory review of specific form content is done.
Page 2 of 7
Document Control Desk LR-.N95162 CORRECTIVE ACTIONS TO AVOID RECURRENCE
- 1. Public Service Electric & Gas (PSE&G) Nuclear Training Center (NTC) Management will discuss this event with all NTC instructional staff and their supervision.
Discussions will emphasize expectations for attention to detail, proper record keeping and documentation, significance of an individuals signature and the need for a questioning attitude. This discussion will include emphasis on the need for increased vigilance on tasks of a repetitive nature. Emphasis will also be placed on the need for a review of applicable guidance documents (e.g.
procedures, guidelines, regulatory documents, etc.) when making decisions that alter current established practices.
This action will be completed by October 26, 1995.
- 2. Training for all operations training instructors on examination security requirements will be completed prior to the .next operator requalif ication examination. This training will be based on the requirements from training center procedures for licensed operator requalif ication examination development and administration. This action will be completed by October 27, 1995 .
4.
The instructor and his supervisor were counselled for their failure to identify and initiate corrective actions for an administrative deficiency in the exam security process. This action was completed on May 18, 1995.
A security agreement was generated to document the requirements that were verbally agreed upon between the instructor and supervisor. This was completed on April 19, 1995.
There are no previous occurrences of this event or similar events concerning instructor violations of operator requalification examination security requirements. This event is generic to the extent that Hope Creek Operations Training uses this methodology for examination security.
III. CONTRIBUTING CAUSAL FACTORS/CORRECTIVE ACTIONS The following are the contributing causal factors along with corrective actions:
A. Based on a review of applicable procedures, it was determined that there was a lack of guidance on examination security requirements for operator requalification examinations.
Document Control Desk LR-N95162 CORRECTIVE ACTIONS TO AVOID RECURRENCE
- 1. The NTC will develop a common (Hope Creek & Salem Generating Station) procedure for the development and implementation of Licensed Operator Requalif ication examinations. This procedure will ensure exam security requirements required by 10CFR55.49 and present industry standards are met. Specific training will be required for all licensed operator instructors prior to the implementation of this procedure. Training will also be required for initial operations instructor qualifications and be a requirement for members of an examination development team. This procedure also meets our commitment to a previous Hope Creek NRC Licensed Operator Inspection and response (see Contributing Cause III.B).
This will be completed by October 18, 1995.
B.. Inadequate implementation and tracking of an NRC commitment (reference NLR-N89228) resulted in a previou$ly issued document, "Guideline for Developing and Conducting Licensed Operator Requalification Exams" becoming outdated and ineffective. This document was issued in response to an NRC Requalification Program. Evaluation, Report Number 50-354/89-12.
- 1. The above guideline was initially issued in 1989 to
- provide specific guidance to NTC staff to aid in the -*
development of examination materials for requalif ication examinations. It was subsequently revised and reissued as Revision 0 in March of 1991. However, this guideline '!Vas never proceduralized or identified as fulfilling an NRC commitment. Apparent causes for the failure to properly implement and track this requiremen.t include:
This document was not incorporated into the NTC procedure system and therefore was not tracked.
There was no identification of this guideline as fulfilling an NRC commitment, either in the document or by reference in an approved training procedure.
Several personnel involved in development and initial piloting of the methodology in the guideline have been .
transferred to other positions or temporarily reassigned.
Page 4 of 7
Document Control Desk LR~N95162 CORRECTIVE ACTIONS TO AVOID RECURRENCE
- 1. The NTC will develop a common (Hope Creek & Salem Generating Station) procedure for Licensed Operator Requalification examinations *(This is noted in Corrective Action III.A.1). This procedure will include sample plan development, open reference test item requirements and Job Performance Measure (JPM) development to meet current industry standards and *NRC requirements for a satisfactory requalification program. Specific training will be required for all licensed operator instructors prior to the implementation of this procedure. Training will also be required for initial operations instructor qualifications and be a requirement for members of an examination development team. This will be completed by October 18, 1995.
- 2. The NTC will develop a specific qualification task in ~he Licensed Operator Instructor's training matrix. This task would require knowledge and understanding of .NRC requirements for requalif ic.ation exam development and implementation. The training qualification will also include all required exam security requirements. This task will be based on the procedure referenced in Corrective Action III.A.1. This will be completed by October 18, 1995.
- 3. The procedure noted in Corrective Action III.A.1 will be noted as an NRC commitment. In addition, NTC procedure ND.TQ-TC.ZZ-OlOO(Z) Revision 1, Development and Revision of Training Procedure, will be revised to include a requirement to identify commitments in training center procedures. This will be completed by October 18, 1995.
C. Inadequate NTC Management follow-up to ensure proper implementation of expectations on licensed operator requalification examination security.
- 1. The instructor's supervisor recognized that the arrangement in question was unusual and had not been used in the past. However, no attempt to document the specifics of the arrangement were made until the NRC raised a concern.
- 2. The Manager NTC reviewed ES-601 and it was realized that this document was not applicable to the examinations to be given. However, a review of other procedural guidance to determine what requirements existed or practices were in
Document Control Desk LR-.N95162 place was not performed. Also, the ES-601-1 form was not noted during the review of the ES-601 document.
- 3. Operations Training Supervision modified the standard practices used for examination security without ensuring these modifications did not conflict with the ES-601-1 form.
- 4. The guidance provided to the instructor by his supervisor helped to provide ~ mind set that examination security issues were adequately addressed. Also, failure of the instructor to identify a difference between the ES-601-1 security agreement and the verbal instructions indicates a lack of a questioning attitude.
CORRECTIVE ACTIONS TO AVOID RECURRENCE Corrective actions for II.A.l, II.A.2, II.A.3, II.A.4, II.A.5, III.A.l, III.B.l, III.B.2 and III.B.3 address this issue.
D. Less than adequate training for examination team members.
- 1. The Instructor Training Program which provides training on examination security, as defined in ND.TQ-IP.ZZ-0017(Z)
Revision 2, Examination Security, does not provide ~
guidance on requalification examination security measures . ' ___,,..
or security agreements.
- 2. No specific training or qualification requirements are identified for those individuals tasked with overall assembly, generation and administration of licensed operator requalification examinations.
CORRECTIVE ACTIONS TO AVOID RECURRENCE Corrective actions for III.A.l, III.B.l, III.B.2 and III.B.3 address this issue.
E. Less than adequate resource planning by management resulted in an insufficient manning level of qualified instructors in the Salem Operations Training Group.
- 1. Four instructors were transferred to Salem Operations and adequate replacements were not in place for the NTC. This created a situation of over-reliance on one instructor for licensed operator requalif ication training due to his ca*pabilities and qualifications.
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Do~ument Control Desk LR-N95162
- 2. The class requests and their sizes placed additional staff requirements on the Salem Operations Training Group.
CORRECTIVE ACTIONS TO AVOID RECURRENCE Additional permanent staff is currently being qualified. This will be completed by April 1996. In the interim, supplemental staff is in place to ensure adequate .resources are available for operator training.and requalification.
IV. SIGNIFICANCE OF EVENT PSE&G management considers this issue to be important in that an evolution in the continuing evaluation and qualification of operations personnel was not adequately controlled. Although there was no compromise of examination security in this instance, the appearance of impropriety is unacceptable. Establishing and
- enforcing performance standards which meet or exceed industry* and regulatory requirements are key ini_tiatives within the NBU.
Completion of the corrective actions identified herein, as well as other performance improvement initiatives currently underway at the NTC and within the NBU are a necessary first step towards this objective .
3
PUBLIC S. Quinn, Vice President - Nuclear Power P. Eddy, New York State Public Service Department State of New York
- Regional Administrator Secretary, RI Deputy Regional Administrator Secretary, RI DRP Division Secretary, RI DRS Division Secretary, RI DRSS Division Secretary, RI DRMA Division Secretary, RI Region I Receptionist Distribution by fax:
Honorable Sandra Galef, New York State Assembly
~
October 27, 1995 Licensee:
U.S. NUCLEAR REGULATORY COMMISSION REGION I .
NOTICE OF SIGNIFICANT MEETING No. 95-96*
Consolidated Edison Company of New York, Inc.
Facility: Indian Point Unit 2 Docket No.: 50-247 Time and Date: 9:30 a.rn., November 8, 1995 Location: Indian Point Unit 2 Station Energy Education Center Broadway and Bleakley Avenues Buchanan, New York 10511
Purpose:
SALP Managment Meeting NRC Attendees: W. Kane, Deputy Regional Administrator C. Cowgill, Chief, Reactor Projects Branch 2, DRP Licensee Attendees: S. Bram, Senior Vice President, Central Operations S. Quinn, Vice President - Nuclear Power J. McAvoy, Plant Manager NOTE: Th.is meeting is open to the public. Attendance by additional NRC
- personnel should be made known by November 6, 1995, via telephone
- call to Mr. Curtis J. Cowgill~ Region I, at 610-337-5233. Handicapped persons requiring assistance to attend or participate in the meeting shall make their requests known to Mr. Curtis J. Cowgill, USNRC, Region I; 475 Allendale Rd., King of Prussia, PA 19406, (610) 337-5233, no later than two business days prior to the meeting.
Prepared by: