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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 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 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 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 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. 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 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 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 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 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 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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Public Service Electric and Gas Company Louis F. Storz Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations MAY 101996 E1r-N96081 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR EXEMPTION FROM 10CFR55.3l(a) (5)
SALEM GENERATING STATION UNIT NOS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 In accordance with 10CFR55.11, Public Service Electric and Gas Company (PSE&G) requests an exemption from the provision 10CFR55.31 (a) (5), wherein operator license applicants are required to perform at* least five significant control manipulations which affect reactivity or power level on the facility for which the license is sought.
Specifically, PSE&G requests that the NRC accept the performance of the required manipulations by each applicant on the Salem ANSI certified, plant specific simulator. In addition, PSE&G requests that the NRC accept additional training on the Salem simulator and/or on-the-job ~raining/evaluation in lieu of all or some portion of the NUREG-1021 requirement for the applicants to have spent 13 weeks on shift. This training is performed within the bounds of an NRC approved training program.
The applicants for whom this exemption is being sought are experienced in operation and/or supervision at other commercial nuclear power stations within the United States. Attachment 1 provides the bases for the exemption request. Attachment 2 contains brief resumes of all applicants involved.
Obtaining Hot Licenses for these individuals will significantly contribute to the restart efforts of Salem Units 1 and 2. These applicants will add to the breadth and depth of management and operations experience in the control rooms. Inclusion of these individuals on the Operations staff for restart will facilitate the increased level of safety consciousness, coordinated shift management, and commitment to event free operation PSE&G has committed to achieve as part of the Salem Restart Action Plan.
ATTACHMENT 2 TO THIS LETTER CONTAINS INFORMATION TO BE WITHHELD FROM PUBLIC DISCLOSURE PURSUANT TO 10CFR2.790.
'9605160113 960510 PDR ADOCK 05000272 V PDR
/'1.\ Printed on
~ Recycled Paper
MAY 101996
.Document Control Desk 2 LR-N96081 Please note that PSE&G will not consider the approval of this exemption and approval of these waivers from NUREG-1021 requirements as precedents for future operator licensing activities. These requests are based strictly on the unique-situation presently at Salem and the qualifications of the applicants described herein.
We request that Attachment 2 to this document be withheld from public disclosure in accordance with 10CFR2.790(a) (6). This document has been marked "EXEMPT FROM PUBLIC DISCLOSURE PER 10CFR2.790." This attachment contains personnel files (personal resumes of the license applicants), the disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
Should you have any questions with this submittal or our request for withholding from public disclosure, please do not hesitate to contact us.
Sincerely,
~~
C All without Attachment 2 Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 ATTACHMENT 2 TO THIS LETTER CONTAINS INFORMATION TO BE WITHHELD FROM PUBLIC DISCLOSURE PURSUANT TO 10CFR2.790.
LR-N96081 ATTACHMENT 1 DESCRIPTION AND BASIS FOR EXEMPTION FROM 10CFR55.31(a) (5)
INTRODUCTION Public Service Electric and Gas Company (PSE&G) requests, in accordance with 10CFR55.11, "Specific exemptions," an exemption from certain requirements of 10CFR55.31, "Requirements for Applications for Operators' Licenses," for Salem Generating Stations Unit Nos. 1 and 2. PSE&G requests an exemption from the provisions of 10CFR55.31(a) (5), which requires in part that operator license applicants perform at a minimum five significant control manipulations which affect reactivity or power level on the facility for which the license is sought.
10CFR55.31(a) (5) specifies that for applicants at facilities that are in an extended shutdown (such as the Salem Units) which precludes manipulation of the control of the facility in the Control Room, the NRC may process the application and may administer the written examination and operating test required by 55.41 or 55.43 and 55.45 of this part, but may not issue the license until the required evidence of control manipulations is supplied.
PSE&G requests that the NRC accept the performance of the required manipulations by each applicant on the Salem ANSI certified, plant specific simulator. In addition, PSE&G requests that the NRC accept additional training on the Salem simulator and/or on-the-job training/evaluation in lieu of all or some portion of the NUREG-1021 requirement for the applicants to have spent 13 weeks on shift. This training is performed within the bounds of a NRC approved training program.
CURRENT QUALIFICATION/TRAINING REQUIREMENTS 10CFR55.31(a) (5) requires that applicants for operators' licenses perform five significant control manipulations which affect reactivity or power level on the facility for which the license is sought.
NUREG-1021, Revision 7, references ANSI/ANS 3.1-1981 and Regulatory Guide (RG) 1.8, Revision 2, dated April, 1987. As identified in the Salem Updated Final Safety Analysis Report (UFSAR), Appendix 3A, PSE&G Position on USNRC Regulatory Guides, PSE&G is committed to RG 1.8, Revision 1, dated September, 1975, which endorses ANSI N18.1-1971. The requirements of ANSI/ANS 3.1-1981 exceed the requirements of ANSI N18.1-1971.
- YR-N96081 2 ATTACHMENT 1 For applicants for operators' licenses, NUREG-1021, Revision 7, requires the following: 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of classroom training, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of training on the simulator, and 13 weeks spent on shift. For Senior Reactor Operator (SRO) applicants only, 6 of the 13 weeks on shift should occur during operation above 20% power.
PROPOSED ALTERNATE QUALIFICATION/TRAINING REQUIREMENTS The applicants for whom this exemption is being requested have been separated into Groups A and B based on differences in their existing qualifications and the alternate training they will receive. Group A applicants have passed their examinations and need only to satisfy the at-power operation and/or significant manipulations requirements to be qualified for their licenses.
Group B applicants are currently completing their formal training at this time.
GROUP A The applicants in Group A, both SRO and Reactor Operator (RO) ,
have passed their NRC examinations. Of the two SRO applicants, one has held an SRO license previously and the other has previously completed the training for an SRO certification at another plant. The three RO applicants have all had significant plant operations experience as equipment operators. They were chosen by plant management as the top RO applicants in their class to sit for their NRC examinations, and all three were successful.
The specific 10CFR55 or NUREG-1021 requirement is listed below together with the specifically applicable alternative training received by the Group A applicants. -
10CFR55 requirement for at least five significant control manipulations on Salem shall be met via the following alternative:
o at least five significant control manipulations which affect reactivity or power level performed on Salem's plant-specific simulator.
NUREG-1021 requirement for 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of classroom training shall be met via the following alternative:
o approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> of classroom training as part of an INPO-accr~dited training program.
~R-N96081 3 ATTACHMENT 1 NUREG-1021 requirement for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of simulator training shall be met via the following alternative:
o approximately 580 hours0.00671 days <br />0.161 hours <br />9.589947e-4 weeks <br />2.2069e-4 months <br /> (approximately 14 weeks) of training and evaluation on Salem's plant specific simulator as part of an INPO-accredited training program. (This time is applied to both simulator training and on shift training.)
NUREG-1021 requirements to spend 13 weeks on shift, with 6 of the 13 weeks on shift occurring during operation above 20% power for SRO applicants, shall be met via the following alternatives:
o approximately 580 hours0.00671 days <br />0.161 hours <br />9.589947e-4 weeks <br />2.2069e-4 months <br /> (approximately 14 weeks) of training and evaluation on Salem's plant specific simulator as part of an INPO-accredited training program, (This time is applied to both simulator training and on shift training.),
and o 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br /> (12 weeks) as an extra person on shift in Cold Shutdown or Refueling, and o a special 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at-power program on the Salem simulator specifically designed to facilitate at-power reactivity manipulations under the direct guidance of a Salem Licensed Reactor Operator.
The objective of this program was to provide the applicants with real-time normal operations training under the direction of an experienced reactor operator.
This type of training in the day-to-day routines of performing power changes, surveillance testing, adjusting nuclear instrumentation, and rotating plant equipment has significantly improved the applicants understanding of these types of activities. It also provided the SRO applicants with operational experience from the perspective of the RO.
GROUP B Group B applicants are currently participating in the INPO-accredited SRO training program. The seven Group B applicants have all held SRO licenses previously. When the applicants in Group B have passed their examinations, they will have completed the following training.
The specific 10CFR55 or NUREG-1021 requirement is listed below together with the specifically applicable alternative training received by the Group B applicants.
10CFR55 requirement for at least five significant control manipulations on Salem shall be met via the following alternative:
o at least five significant control manipulations which affect reactivity or power level performed on Salem's plant-specific simulator.
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~R-N96081 4 ATTACHMENT 1 NUREG-1021 requirement for 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of classroom training shall be met via the following alternative:
o approximately 575 scheduled hours of classroom training as part of an INPO-accredited training program.
NUREG-1021 requirement for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of simulator training shall be met via the following alternative:
o approximately 470 scheduled hours (in excess of 11 weeks) of training and evaluation on Salem's plant specific simulator as part of an INPO-accredited training program. (This time is applied to both simulator training and on shift training.)
NUREG-1021 requirements to spend 13 weeks on shift, with 6 of the 13 weeks on shift occurring during operation above 20% power for SRO applicants, shall be met via the following alternatives:
o approximately 470 scheduled hours (in excess of 11 weeks) of training and evaluation on Salem's plant specific simulator as part of an INPO-accredited training program, (This time is applied to both simulator training and on shift training.) and o approximately 270 scheduled hours (in excess of 6 weeks) of on-the-job training and evaluation completing the RO and SRO qualification cards during the current extended shutdowns.
BASIS FOR EXEMPTION Based on a review of the requirements of 10CFR55.3l(a) (5), PSE&G has determined that the requested exemption to the regulations can be granted pursuant to 10CFR55.ll, in that it is authorized by law and will not endanger life or property.
PSE&G is confident that the applicants, for which this exemption from 10CFR55.31(a) (5) and waiver from the NUREG-1021 requirement to spend 13 weeks on shift applies, are qualified to perform their duties as either an SRO or RO, as appropriate. Previous experience identified on Attachment 2 and extensive classroom and simulator training defined previously, provide a satisfactory alternative to the control manipulations required by 10CFR55.31(a) (5) and the on-shift requirements of NUREG-1021.
With respect to the experience of the RO applicants in Group A, all have had significant plant operations experience as equipment operators. They were chosen by plant management as the top RO applicants in their class to sit for their NRC examinations, and all three were successful.
4R-N96081 5 ATTACHMENT 1 With respect to the experience of the SRO applicants in Groups A and B, all, except one applicant, have held SROs at Pressurized Water Reactors (PWRs) other than Salem. The applicant's years of experience as an SRO range from three to over fifteen. These SRO applicants were chosen based on a rigorous screening/interview process. The process supported the selection of applicants with previously demonstrated strong leadership and operations skills.
Also, the process focused on the skills of the individual applicant; the overall operating record of the PWR where the prior experience was gained was a contributing, but not primary factor.
Additionally, to improve the level of plant-specific experience, the SRO applicants will be teamed with a Salem experienced crew.
This crew will have the ability to provide historical information that will further enhance the performance of the SRO and his operating crew.
The two Group A SRO applicants will become Senior Nuclear Shift Supervisors (SNSS) for operating crews which will oversee the startup of Salem Unit 2. On each crew, the Unit 2 Nuclear Shift Supervisor (NSS) has been selected based on the individual's capability to enhance the overall performance of the crew by provision of Salem technical input usually best gained from plant-specific experience. Where possible, the Unit 2 crews have been training together in the positions they will occupy on shift. The Group B applicants will be assigned to various SNSS and NSS positions as necessary to support Unit 2 startup (current plans also have Group B applicants filling SNSS and NSS positions for Unit 1, once decisions are made concerning the schedule for Unit 1 restart) .
Obtaining Hot Licenses for these individuals will significantly contribute to the restart efforts of Salem Units 1 and 2. These applicants will add to the breadth and depth of management and operations experience in the control rooms. Inclusion of these individuals on the Operations staff for restart will facilitate the increased level of safety consciousness, coordinated shift management, and commitment to event free operation PSE&G has committed to achieve as part of the Salem Restart Action Plan.
In conclusion, the proposed alternate qualifications and training will not decrease the capabilities of the licensed operators.
For all of the above reasons, PSE&G believes it to be in the public interest to grant the requested exemption and waiver for issuance of the operators' licenses.