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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OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 101991 LR-N970219 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ADEQUACY OF TECHNICAL SPECIFICATION COMPLIANCE SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
At our March 6, 1997 meeting in Rockville Md. to discuss design basis issues for the Salem facilities, a request was made by the NRC that PSE&G provide additional information relative to I
the "Adequacy of Technical Specification Compliance". The requested information is provided in the attachment. Should there be any questions regarding this submittal, please contact us.
Sincerely, David R. Powell Manager-Licensing and Regulation Attachment
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- APR 101991 bocum~nt Control Desk 2 LR-N970219 c Mr. Hubert J. Miller, 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. C. Marschall (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN415 Trenton, NJ 08625
- LR-N970219 ADEQUACY OF TECHNICAL SPECIFICATIONS COMPLIANCE SALEM GENERATING STATION This discussion provides PSE&G's basis for reasonable assurance that compliance with the current Plant Technical Specifications (TS) is adequate to support safe operation of the Salem Units. This basis was discussed with the NRC at the senior management meeting on March 6, 1997, in Rockville, Maryland.
The Salem Units were removed from service in the Spring of 1995 to address long standing problems with plant performance. As part of the Salem Restart Plan, several different reviews have been conducted that included evaluation of Technical Specifications implementation. The results of these reviews and the associated corrective actions provide the basis for reasonable assurance that the plant Technical Specifications Surveillance Requirements are adequately implemented to support restart. The reviews credited include: 1) Phase 1 of the Technical Specifications Surveillance Improvement Program (TS SIP); 2) UFSAR Macro-reviews for Unit 2 Systems as part of the FSAR project; 3) UFSAR Chapter 15 Safety Analysis Input Reviews as part of the FSAR project; 4) UFSAR Vertical Slice Reviews of Selected Systems conducted as part of the FSAR Project; 5) reviews ofrecent Technical Specifications related LERs; and, 6)
Additional technical reviews of master time response test procedures, ventilation system test procedures and, Inservice Test (IST) procedures. Each of these reviews is summarized below:
Technical Specifications Surveillance Improvement Program - Phase 1 Phase 1 ofTSSIP has been completed for Unit 2 and will be completed for Unit 1 prior to restart of the Unit. This review involved a general review of the TS Surveillance Requirements and implementing procedures, along with an evaluation of scheduling controls. The Phase 1 general review included 1) a comparison of the TS Surveillance Requirements to their associated implementing procedure(s) in order to verify that the Purpose Statement of each implementing procedure accurately reflects and references the Surveillance Requirements and, 2) that the stated acceptance criteria are consistent with the associated TS Surveillance Requirements. The scheduling review involved a comparison of surveillance-related Managed Maintenance Information System (MMIS) Recurring Tasks (RTs) against the TS requirements to ensure proper frequencies and mode applicability for the TSs. A detailed evaluation of operating mode transition procedures was completed to ensure the proper surveillances will be completed prior to each mode change. Conditional, or event-driven, TS Surveillance Requirements were reviewed to ensure requirements have a formalized mechanism for recognizing the condition and initiating the appropriate response.
The Phase 1 review resulted in over 750 procedure revision requests and over 2100 MMIS RT surveillance task change requests. While performing the Phase 1 reviews, there were also a number of deficiencies identified that resulted in Action Requests (ARs) to be resolved via the Corrective Action Program. In some cases, additional technical review of the procedure was Page 1of5
performed when there was reason to believe that the procedure was technically inadequate. A total of 77 ARs were generated during Phase 1. These consisted of 14 administrative errors, 1 scheduling issue and 62 procedural adequacy issues. Fourteen of the procedural adequacy issues resulted in LERs, which are included in the discussion ofLERs below. Completion of the TSSIP Phase 1 provides assurance that each TS Surveillance Requirement has an implementing procedure, that the stated purpose and acceptance criteria are consistent with the Technical Specifications and, that the surveillances are scheduled at the appropriate periodicity and performed in the correct modes or conditions.
FSAR Project Reviews The UFSAR Macro-reviews conducted for each of the systems included in the System Readiness Review Program encompassed a review of select design bases parameters and system attributes (flow rates, temperatures, pressures, setpoints, automatic start features, etc.) from the UFSAR.
These parameters and system attributes were reviewed against the appropriate TS and/or plant procedures to determine proper incorporation of the system attributes into these documents.
As part of the UFSAR Chapter 15 Safety Analysis Input Reviews, system and component-related inputs and assumptions to the Salem UFSAR Chapter 15 accident analyses were identified in a matrix with a reference to the licensing basis calculation file that demonstrates the safety limits are met for the analyzed accident. These inputs and assumptions were then reviewed against current plant testing procedures, including applicable Technical Specifications surveillance procedures, to validate that current testing of the parameters is consistent with the assumptions used in the accident analyses. Five input parameters still need to be validated after the applicable vendor calculations are received.
The UFSAR Vertical Slice reviews conducted also assessed adequacy of Technical Specifications implementation for the systems reviewed. During the FSAR project, vertical slice reviews were conducted for the seven safety-significant systems identified below:
- Auxiliary Building Ventilation (ABV)
- Fuel Handling Ventilation (FHV)
- Containment Building Ventilation (CBV)
These vertical slice reviews were multi-disciplinary team reviews starting with the licensing and design bases documents such as the UFSAR and the plant Technical Specifications. Key descriptions, parameters (i.e., setpoints, response times, etc.) and procedures were reviewed to assess whether the plant is operated in accordance with the licensing/design bases.
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There were 16 Technical Specifications related deficiencies identified from the FSAR Project Reviews. The Technical Specifications issues consisted of documentation inconsistencies between reference documents and the Technical Specifications. These Technical Specification reviews did not identify any Technical Specification violations or any safety significant issues. The deficiencies are being addressed in accordance with the Corrective Action Program.
LERReview A review ofrecent LERs (since May, 1995) was conducted to gain a better understanding of past surveillance deficiencies. The problems documented in these LERs consisted of personnel errors, scheduling errors and procedural adequacy problems. Based on the review of these LERs, the TSSIP Phase 1 findings and findings from various restart activities, there were three areas that were considered significant and required further reviews in order to validate the adequacy of Technical Specifications implementation. Thus, additional reviews were initiated for master time response test procedures, ventilation system test procedures and IST procedures. These reviews are discussed separately in the next section below. The deficient Unit 2 surveillances that have been re-performed using the corrected implementing procedures had satisfactory results. The remainder of the deficient Unit 2 surveillances will be re-tested prior to entering the Mode or condition in which they become applicable. The completion ofTSSIP Phase 1, as discussed above, provides assurance that scheduling problems have been identified and corrected.
Additional Technical Reviews As discussed above, additional technical reviews were conducted in three areas based on the number of problems discovered in these areas. Each of these reviews is discussed below.
The master time response review involved a review of the Engineered Safety Features Response Times listed in Table 3.3-5 of the Salem Technical Specifications. This review was initiated as a result of LER 272/96-020-00, Containment Fan Coil Units Outside Plant Design Basis, which identified that the ESF Response Time for the Containment Fan Coil Units (CFCUs) was inadequate. The response time was determined to be approximately 56 seconds which exceeds the 45 second limit specified in TS Table 3.3-5. However, a subsequent analysis (for a License Change Request) using a response time of 60 seconds demonstrated that the containment pressure and temperature remained below their design values.
The master time response review was performed to ensure that all the proper components are tested and the acceptance criteria are consistent with the TS response times. The scope of this evaluation consisted of the following:
- 1) Determine success paths required to support accident mitigation. A success path is comprised of all major plant components required to actuate to support an ESF AS function. Success paths were developed for each ESFAS function. P&IDs, logics, and electrical schematics were used as input.
- 2) Verify success path response time acceptance criteria (from event detection to completion of final element response). TS Table 3.3-5 was the main source of input.
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- 3) Assign, where possible, acceptance criteria to individual components in the success path. The acceptance criteria were based on Technical Specifications and the SAR.
- 4) Confirm these components are included in the Master Time Response procedure.
The deficiencies identified from this review included some components not included in the response time testing, some of the acceptance criteria being incorrect, inconsistencies in documentation and several procedural enhancements. There were no safety significant findings from the review of the ESF master time response testing.
The reviews of the ventilation test procedures included a review of the Auxiliary Building Ventilation, the Control Area Ventilation and the Fuel Handling Building system test procedures.
The purpose of this review was to ensure that the testing methodology and acceptance criteria were consistent with applicable ANSI standards and the plant Technical Specifications. For the Auxiliary Building and the Fuel Handling Building, deficiencies were identified relative to the adequacy of the testing used to meet the Technical Specification requirements. However, after the testing procedures were upgraded as required, most of the suspect surveillance tests were conducted satisfactorily. In one case, where the system bypass limits were tested, some dampers had to be repositioned in order to satisfy the surveillance. However, for this case the amount of bypass measured was still less than that assumed in the dose calculations. Thus, the safety significance of these deficiencies was low. For the control room area, the review focused on developing procedures that were consistent with the new control room design implemented during the current outage and the new requirements contained in a license amendment recently received.
Testing is still in progress to ensure that the control room area ventilation meets the new TS requirements. Prior to startup of the Salem Units, these TS surveillances will be satisfactorily completed.
The IST review consisted of a complete upgrade and verification/validation of the IST program This upgrade included:
- Applicable Codes and Standards, commitments, NRC issued NUREGs, Generic Letters, Information Notices and Bulletins, Technical Specification & UFSAR sections, and applicable Configuration Baseline Documents for IST program development were reviewed.
- Controlled plant P&ID drawings were used to identify those safety related components subject to IST requirements.
- An IST BASIS document was developed for approximately 1800 Salem Unit 1 and Unit 2 pumps and valves identifying applicable component classification and category, safety function, test requirements, and a list of references from which the information was derived.
- Recurring tasks were prepared for applicable IST components and incorporated into MMIS. Additionally, Functional Equipment Groups in MMIS were corrected or are being corrected and cross referenced to specific IST surveillance test procedures.
- IST surveillance procedures were reviewed to ensure correct implementation of applicable component test requirements. Where necessary, procedures were or are Page 4of5
being revised and where necessary new test methodologies and procedures are being developed.
- Currently approved IST Program relief requests were revised or are being revised to enhance the basis for alternative testing. Some Relief Requests were reclassified as Cold Shutdown Justifications and Refueling Outage Justifications. Several new Cold Shutdown Justifications were created and some were eliminated.
- New process procedures were developed to control IST implementation.
From this review, deficiencies were identified relative to improper testing of some IST components and some required components not included in the program. Testing subsequent to procedural upgrades and inclusion of additional required components has proven the components capable of performing their safety functions. There were just a few cases where corrective maintenance was required. In one case a manual isolation valve took longer than expected to close. In another case, the Unit 1 service water pumps failed their surveillance which was expected based on trend data. These pumps were already planned to be replaced during the current outage. Thus, the safety significance of these deficiencies was low. Corrective actions have been taken or are being taken to assure compliance with the Technical Specifications in the three areas of concern discussed above.
Summary The results of the multiple reviews combined with the corrective actions taken to address deficiencies provide reasonable assurance that implementation of the Salem Technical Specifications is adequate to support restart. While there have been many Technical Specification deficiencies identified to date, the issues have generally not had significant plant safety implications. Areas that were deemed to have potential safety significance (e.g., time response testing, ventilation system testing and IST testing ) are being thoroughly evaluated prior to restart.
The large number of deficiencies discovered as part of the various reviews conducted in support of the Salem restart readiness is an indication of the thoroughness of the reviews and provides confidence that most of the significant problems have been identified. Completion ofTSSIP Phase 1 assures that all Surveillance Requirements have an implementing procedure and are properly scheduled. While the reviews discussed are not a complete review of all TS requirements, they do represent a significant sampling to support the basis for reasonable assurance. Phase 2 of TS SIP will continue the review of surveillance procedures for technical adequacy. There are no known deficiencies that could preclude safe plant operation and, while it is expected that additional issues will be identified from the continuing Phase 2 reviews, evidence from the comprehensive reviews conducted to date suggest that it is unlikely that safety significant problems will surface.
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