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MONTHYEARML0616403482006-06-0505 June 2006 Response to NRC Request for Additional Information Regarding Unresolved Inspection Item 05000293/2005003-01 from NRC Integrated Inspection Report 05000293-05-003 Project stage: Response to RAI ML0629104322006-11-17017 November 2006 Final Response to Task Interface Agreement 2006-01 Related to the Adequacy of Emergency Diesel Generator and Shutdown Transformer Load Testing at Pilgrim Nuclear Power Station Project stage: Other 2006-11-17
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Category:Memoranda
MONTHYEARML22321A1042022-12-0101 December 2022 Lessons Learned Recommendations Effectiveness Review ML21060B1152021-03-31031 March 2021 Memo to File: Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Pilgrim ISFSI ML19274B6662019-11-13013 November 2019 Summary of Public Meeting Near the Pilgrim Nuclear Power Station Regarding the Establishment and Operation of Community Advisory Boards ML19182A3562019-07-23023 July 2019 Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019 ML18158A1302018-06-0707 June 2018 Evaluation - Memorandum Regarding Licensee Event Report Safety Significance Review in Response to Findings Associated with Inspection Procedure 95003; Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML18157A0402018-06-0606 June 2018 Inspection Procedure 95003: Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML18158A1332018-06-0606 June 2018 Extent of Condition Review in Response to Findings Associated with Inspection 95003: Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML16153A2762016-06-20020 June 2016 Memo - Transmittal of the Final Pilgrim Nuclear Power Station Accident Sequence Analysis ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML14294A5712014-11-0404 November 2014 Memo - Transmittal of the Final Pilgrim Nuclear Power Station Accident Sequence Analysis ML14300A0962014-10-28028 October 2014 Staff Review of the Pilgrim Physical Security Plan (Revision 12) for the Independent Spent Fuel Storage Installation Security and Verification of ASM Incorporation (TAC L24940) ML14232A3012014-08-20020 August 2014 Memo s Wastler, Technical Assistance Request - Review of Physical Security Plan for the Pilgrim Nuclear Power Stations (TAC No. L24940) Docket Nos. 72-1044, 50-293 ML14086A2912014-04-22022 April 2014 Summary of Telephone Conference Regarding the Verbal Authorization of Relief Request PRR-25, Revision 1 ML13351A2732014-01-0909 January 2014 G20130846/LTR-13-0911 - James Brett, the New England Council Ltr. Chairman'S Recent Tour and the Council'S Support for the Pilgrim Nuclear Power Station - Response ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13267A2342013-08-30030 August 2013 G20130629 - Pilgrim Watch'S 2.206 Petition to Pilgrim'S Emergency Preparedness Plans (MF2656) ML13108A3282013-04-22022 April 2013 Notice of Forthcoming Meeting with Petitioners Requesting Action Against Entergy Nuclear Operations, Inc., Regarding Operations at FitzPatrick, Pilgrim, and Vermont Yankee Nuclear Power Stations (TAC Nos. MF1092, MF1093, and MF1094) ML13196A2202012-06-0606 June 2012 Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon ML12137A0602012-05-29029 May 2012 Nuclear Regulatory Commission'S Analysis of Entergy Nuclear Operations, Inc. Decommissioning Funding Status Report for Indian Point Nuclear Generating Station, Units 1, 2 & 3; and Pilgrim Nuclear Power Station ML12090A2122012-03-30030 March 2012 Referring Jones River Watershed Association Petition to Intervene and Request to File New Contentions, or in Alternative, Jones River Watershed Association and Pilgrim Water Motion to Reopen the Pilgrim Nuclear Power Station, Docket No. 50- ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML11174A3252011-06-30030 June 2011 Memo Forwarding of Supplement 2 to NUREG-1891, SER Related to the Lr of Pilgrim Nuclear Power Station, Docket No. 50-293, to the Advisory Committee on Reactor Safeguards ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML1109700342011-04-19019 April 2011 Summary of Tele Conf Call Held on 4/6/11, Between the USNRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1108206892011-04-19019 April 2011 February 24, 2011, Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1108202082011-04-11011 April 2011 Summary of Telephone Conference Call Held on March 23, 2011, Between the USNRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1100404192011-02-15015 February 2011 Summary of Telephone Conference Call Held on December 6, 2010, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operating, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application (Tac No. MC9669) ML1018900452010-07-0808 July 2010 Notification of Information in the Matter of Pilgrim Nuclear Power Station ML0927301372009-10-0909 October 2009 Safety Evaluation by the Office of Nuclear Reactor Regulation Corporate Restructuring Conversion of Companies and Stock Split-Off by Entergy Nuclear Operations, Inc and Subsidiaries ML1029505722009-01-23023 January 2009 Task Interface Agreement - Evaluation of Application of Technical Specification 4.0.3, Surveillance Requirement Applicability, at Pilgrim ML0836601742009-01-23023 January 2009 TIA - Task Interface Agreement - Evaluation at Pilgrim of Application of TS 4.0.3, 12/31/08 ML1029505762009-01-23023 January 2009 Task Interface Agreement Evaluation of Application of Technical Specification 4.0.3, Surveillance Requirement Applicability, at Pilgrim ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0718400342007-07-0606 July 2007 ACRS Review of the Pilgrim Nuclear Power Station License Renewal Application - Safety Evaluation Report ML0713100692007-06-0808 June 2007 Summary of Conference Call on May 10, 2007, with Entergy Nuclear Operations, Inc., Regarding the Pilgrim License Renewal Application ML0708104422007-03-15015 March 2007 Request for Additional Information on Time-Limited Aging Analyses for the Reactor Vessel and Internals, Pilgrim Nuclear Power Station, License Renewal Application ML0706402522007-03-0606 March 2007 ACRS Review of the Pilgrim Nuclear Plant Station Renewal Application - Safety Evaluation Report ML0705402052007-03-0101 March 2007 01/24/2007 Summary of Meeting with Pilgrim on the Draft Supplemental Environmental Impact Statement Regarding Pilgrim License Renewal Review ML0700501532007-01-0808 January 2007 01/24/2007 Notice of Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Pilgrim Nuclear Power Station ML0634800242006-12-13013 December 2006 Drop-In Visit from Entergy (Pilgrim) ML0633406952006-11-28028 November 2006 Memorandum to Levin from Albert, Access to Security, Radiological, Vital and Protected Areas of the Pilgrim Nuclear Station ML0629104322006-11-17017 November 2006 Final Response to Task Interface Agreement 2006-01 Related to the Adequacy of Emergency Diesel Generator and Shutdown Transformer Load Testing at Pilgrim Nuclear Power Station ML0627605082006-11-0707 November 2006 Summary of Conference Call on September 25, 2006, with Entergy Nuclear Operations, Inc ML0628504072006-10-23023 October 2006 2006/10/23-Summary of Conference Call on October 10, 2006 with Entergy Nuclear Operations. Inc., to Clarify Information Sent to the NRC in Response to Requests for Additional Information Regarding the Pilgrim License Renewal Application ML0625801622006-09-15015 September 2006 Audit Trip Report Regarding Entergy Nuclear Operations Inc. License Renewal Application for Pilgrim Nuclear Power Station, Dated January 25, 2006 ML0617000552006-07-13013 July 2006 2006/07/13-Summary of Public Scoping Meetings Conducted Related to the Review of the Pilgrim Nuclear Power Station, License Renewal Application ML0618104242006-06-30030 June 2006 2006/06/30- 07/19/2006 Notice of Forthcoming Exit Meeting with Entergy Nuclear Operations, Inc., on License Renewal Scoping and Screening Methodology and the Aging Management Program / Aging Management Review Audits for Pilgrim Nuclear Powe 2022-12-01
[Table view] Category:Report
MONTHYEARL-21-078, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2021-07-0606 July 2021 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML18158A1332018-06-0606 June 2018 Extent of Condition Review in Response to Findings Associated with Inspection 95003: Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML19056A1932017-08-17017 August 2017 Attachment 2 Design Input Record ML17212A5712017-07-28028 July 2017 Recovery Plan ML16153A3722016-06-20020 June 2016 Final ASP Analysis Pilgrim (LER 293-15-001) ML15043A7542015-03-24024 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 1 of Order EA-13-109 (Severe Accident Capable Hardened Vents) ML15075A0822015-03-12012 March 2015 Entergy'S Required Response of the Near-Term Task Force Recommendation 2.1: Flooding-Hazard Reevaluation Report ML14294A5912014-11-0404 November 2014 Final ASP Analysis - Pilgrim Nuclear Power Station (LER 293-13-009) ML14171A2002014-06-26026 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0264) ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14324A0402014-04-17017 April 2014 HI-2104715, Seismic Analysis of the Loaded HI-TRAC in the SFP and SFP Slab Qualification. ML14092A0232014-03-31031 March 2014 Entergy'S Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima... ML13338A6672013-12-0909 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Pilgrim Nuclear Power Station, TAC No.: MF0777 ML13232A1322013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment C, Page C85 of C413 Through Page C173 of C413 ML13232A1342013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment C, Page C174 of C413 Through Page C250 of C413 ML13232A1352013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment C, Page C251 of C413 Through Page C331 of C413 ML13232A1372013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment C, Page C332 of C413 Through Page C413 of C413 ML13232A1382013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment D, Page D1 of D127 Through Page D73 of D127 ML13232A1402013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment D, Page D74 of D127 Through Attachment H, Page H12 of H12 ML13232A1412013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment I, Page I1 of I9 Through Attachment J, Page J77 of J134 ML13232A1312013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment C, Page C1 of C413 Through Page C84 of C413 ML13232A1302013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment a Through Attachment B ML13232A1292013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment J, Page J78 of J134 Through End ML13232A1282013-06-17017 June 2013 PNPS-CS-12-00001, Rev. 1, Pilgrim Station Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page 37 of 37 ML12342A3862012-12-0606 December 2012 Fifth Ten-Year Inservice Testing Program and Request for Approval of IST Relief Requests, PR-03 and PR-05 ML12333A3212012-11-27027 November 2012 Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12160A3712012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to Fukushima Daiichi Nuclear Plant Accident ML13196A1892012-04-12012 April 2012 Email from B. Balsam, NRR to J. Crocker, NOAA Pilgrim: NRC Complete Responses to 4-9-12 NMFS Questions ML13196A2362012-04-12012 April 2012 Email from M. Smith, OGC to S. Uttal OGC Et Al., on Additional Pilgrim Exhibits ML12047A1192012-02-29029 February 2012 Request to Include Atlantic Sturgeon in Ongoing Informal Section 7 Consultation for Pilgrim Nuclear Power Station ML1204403512012-02-27027 February 2012 Acknowledgement of Withdrawal and Results of Acceptance Review Proposed License Amendment Request for Rod Withdrawal Minimizer Bypass Allowance to Allow Reactor Startup ML11346A5682011-12-0909 December 2011 Report Entitled - Regulatory Meltdown: How Four Nuclear Regulatory Commissioners Conspired to Delay and Weaken Nuclear Reactor Safety in the Wake of Fukushima ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML14086A5022011-06-13013 June 2011 Enclosure 1 to PNPS Letter 2.14.027 - Entergy Nuclear Engineering Report No. PNPS-RPT-11-00001, Re-assessment of Pilgrim Seismic Core Damage Frequency ML1104203062011-01-31031 January 2011 GE Hitachi Nuclear Energy Report, NEDC-33532, Revision 2, Pilgrim Nuclear Power Station Safety Valve Setpoint Increase, Enclosure 4 to 2.11.007 ML1007704512010-03-31031 March 2010 NEDO-33532, Rev 0, Pilgrim Nuclear Power Station Safety Valve Setpoint Increase. ML1019004142009-03-12012 March 2009 Condition Report, CR-PNP-2009-00879 ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0712300162007-05-0202 May 2007 FSEIS Reference - Nonradioactive Waste Information ML0712102522007-04-21021 April 2007 Weld Filler and Welding Electrode Materials for Structural Weld Overlays within the Scope of Pilgrim Relief Request, PRR-15 ML0711303842007-04-10010 April 2007 GE-NE-0000-0066-0380-R1-NP, Pilgrim Nuclear Power Station, Torsion Arm Clamp Stress Evaluation Report. ML0710802222007-04-10010 April 2007 Repair of the Core Shroud Stabilizer Assemblies - Torsion Arm Clamp Stress Evaluation Report ML0708701322007-03-22022 March 2007 Request for Authorization Under the Provision of 10 CFR 50.55a(a)(3)(i) for Modification of the Core Shroud Stabilizer Assemblies ML0708701342007-03-21021 March 2007 GE-NE-000-0064-9392-R2-NP, Pilgrim Unit 1, IGSCC Assessment of Shroud Repair X-750 Component Other than the Replacement Upper Support Assembly and Tie Rod Nut. ML0709303132007-03-14014 March 2007 GE-NE-0000-0061-6306-R4-NP, Pilgrim Nuclear Power Station, Shroud Repair Replacement Upper Support Assembly-Stress Analysis Report. ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007 Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006 ML0629104322006-11-17017 November 2006 Final Response to Task Interface Agreement 2006-01 Related to the Adequacy of Emergency Diesel Generator and Shutdown Transformer Load Testing at Pilgrim Nuclear Power Station ML0634804022006-11-0606 November 2006 E-MAIL: (PD) Fwd: Entergy Nuclear Cultural Resources Protection Plan ML0707901202006-10-0606 October 2006 CR-PNP-2006-03702, an Issue Was Raised During the Region I Inspection for License Renewal Regarding the Expected Service Life of a Protective Coating for Buried Piping ML0707901152006-10-0404 October 2006 CR-PNP-2006-03677, Controls to Prevent and Monitor for Corrosion of the Drywell Shell Need to Be Assessed and Strengthened 2021-07-06
[Table view] Category:Miscellaneous
MONTHYEARL-21-078, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2021-07-0606 July 2021 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML18158A1332018-06-0606 June 2018 Extent of Condition Review in Response to Findings Associated with Inspection 95003: Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML17212A5712017-07-28028 July 2017 Recovery Plan ML16153A3722016-06-20020 June 2016 Final ASP Analysis Pilgrim (LER 293-15-001) ML15043A7542015-03-24024 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 1 of Order EA-13-109 (Severe Accident Capable Hardened Vents) ML15075A0822015-03-12012 March 2015 Entergy'S Required Response of the Near-Term Task Force Recommendation 2.1: Flooding-Hazard Reevaluation Report ML14171A2002014-06-26026 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0264) ML12342A3862012-12-0606 December 2012 Fifth Ten-Year Inservice Testing Program and Request for Approval of IST Relief Requests, PR-03 and PR-05 ML12333A3212012-11-27027 November 2012 Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12160A3712012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to Fukushima Daiichi Nuclear Plant Accident ML13196A1892012-04-12012 April 2012 Email from B. Balsam, NRR to J. Crocker, NOAA Pilgrim: NRC Complete Responses to 4-9-12 NMFS Questions ML11346A5682011-12-0909 December 2011 Report Entitled - Regulatory Meltdown: How Four Nuclear Regulatory Commissioners Conspired to Delay and Weaken Nuclear Reactor Safety in the Wake of Fukushima ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1019004142009-03-12012 March 2009 Condition Report, CR-PNP-2009-00879 ML0712300162007-05-0202 May 2007 FSEIS Reference - Nonradioactive Waste Information ML0712102522007-04-21021 April 2007 Weld Filler and Welding Electrode Materials for Structural Weld Overlays within the Scope of Pilgrim Relief Request, PRR-15 ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007 Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006 ML0629104322006-11-17017 November 2006 Final Response to Task Interface Agreement 2006-01 Related to the Adequacy of Emergency Diesel Generator and Shutdown Transformer Load Testing at Pilgrim Nuclear Power Station ML0707901202006-10-0606 October 2006 CR-PNP-2006-03702, an Issue Was Raised During the Region I Inspection for License Renewal Regarding the Expected Service Life of a Protective Coating for Buried Piping ML0707901152006-10-0404 October 2006 CR-PNP-2006-03677, Controls to Prevent and Monitor for Corrosion of the Drywell Shell Need to Be Assessed and Strengthened ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006 Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006 ML0622806022006-07-31031 July 2006 Groundwater Protection - Data Collection Questionnaire CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee ML0630603022006-07-11011 July 2006 Email: (PA-LR) FW: Pilgrim Document 83 ML0704404792006-05-18018 May 2006 CR-PNP-2006-01914 - Pilgrim ML0634701762006-03-29029 March 2006 Pilgrim: NRC Contact Report - Arrange Meeting with Town Officials During Site Audit (Intergovernmental) BVY 06-016, Entergy Nuclear Northeast - Fitness-for-Duty Program Performance Report for the Period July 2005 - December 20052006-02-27027 February 2006 Entergy Nuclear Northeast - Fitness-for-Duty Program Performance Report for the Period July 2005 - December 2005 BVY 05-089, Entergy Nuclear Northeast - Proof of Financial Protection2005-09-28028 September 2005 Entergy Nuclear Northeast - Proof of Financial Protection BVY 05-078, Fitness-for-Duty Program Performance Report for the Period January - June 20052005-08-29029 August 2005 Fitness-for-Duty Program Performance Report for the Period January - June 2005 ML0707901612005-05-16016 May 2005 CR-PNP-2005-02621, Rollup CR with Various Problems Inservice Inspection Related BVY 05-018, Fitness-for-Duty Program Performance Report for the Period July - December 20042005-02-28028 February 2005 Fitness-for-Duty Program Performance Report for the Period July - December 2004 BVY 03-069, Fitness-for-Duty Program Performance Report for Period January - June 20032003-08-18018 August 2003 Fitness-for-Duty Program Performance Report for Period January - June 2003 ML0707901832003-08-12012 August 2003 CR-PNP-2003-02976, Pilgrim Construction Activity and Damage to Underground Utilities ML0707806532003-04-22022 April 2003 CR-PNP-2003-01471, Primary Containment Isolation Valve (PCIV) 262-F-013A Experienced Increased But Acceptable Local Leak Rate Test Results ML0707806242003-04-19019 April 2003 CR-PNP-2003-01413, Secondary Containment Leakrate Testing Was Aborted ML0707806322003-04-19019 April 2003 CR-PNP-2002-01414, the Concrete Shield Block for the Drywell Equipment Hatch Was Removed Prior to the Reactor Being Less than 212F ML0707806152003-04-17017 April 2003 CR-PNP-2002-01411, Secondary Containment Leakrate Testing Was Aborted ML0308403822003-03-17017 March 2003 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request JPN-03-004, Fitness-for-Duty Program Performance Report for the Period July - December 20022003-02-26026 February 2003 Fitness-for-Duty Program Performance Report for the Period July - December 2002 ML0707806032002-12-13013 December 2002 CR-PNP-2002-12941, P-208D (D Salt Service Water Pump) Shaft Had Pitting JPN-02-024, Fitness-for-Duty Program Performance Report for the Period January - June 20022002-08-15015 August 2002 Fitness-for-Duty Program Performance Report for the Period January - June 2002 ML0707805642002-06-19019 June 2002 CR-PNP-2002-10639, Received Blackout Diesel Generator Alarm (C3L-A4) Several Times During Shift on 06/19/2005 ML0707805452002-02-27027 February 2002 CR-PNP-2002-09283, Unable to Reassemble E-122B, B Tbccw Heat Exchanger Head JPN-02-002, Entergy Nuclear Northeast'S Submittal of Fitness-for-Duty Program Performance Report for the Period July - December 20012002-02-25025 February 2002 Entergy Nuclear Northeast'S Submittal of Fitness-for-Duty Program Performance Report for the Period July - December 2001 ML0707805082001-11-0808 November 2001 CR-PNP-2001-04779, T- 112 Cation Regen Tank Found Second Leak ML0707906032001-10-10010 October 2001 Pr 01.4238, Tour Operator Reported That HCU 50-31 Leak Appears Worse - Closure ML0707804912001-09-27027 September 2001 CR-PNP-2001-04238, HCU 50-31 Leak ML0707905962001-09-25025 September 2001 Pr 01.4171, Tour Operator Found Alarm C190-D3 on D# SBO DG Fuel Tank Leakage in Alarm. Panel Indicates Probe #1 Wet Alert Water Detected Alarm ML0707804532001-09-20020 September 2001 CR-PNP-2001-04171, Alarm C190-D3 SBO DG Fuel Tank Leakage in Alarm ML0707905832001-09-17017 September 2001 Pr 01.4048, Received Sdo DG Fuel Tank Leakage Alarm Alert Wet Probes 1 2021-07-06
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November 17, 2006 MEMORANDUM TO: A. Randolph Blough, Director Division of Reactor Safety Region I FROM: John Lubinski, Deputy Director /RA/
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
FINAL RESPONSE TO TASK INTERFACE AGREEMENT 2006-01 RELATED TO THE ADEQUACY OF EMERGENCY DIESEL GENERATOR AND SHUTDOWN TRANSFORMER LOAD TESTING AT PILGRIM NUCLEAR POWER STATION (TAC NO. MD0178)
By your memorandum dated January 4, 2006, Region I submitted a request for a Task Interface Agreement (TIA) related to the adequacy of Emergency Diesel Generator (EDG) and Shutdown Transformer Load Testing at Pilgrim Nuclear Power Station (Pilgrim). The purpose of the TIA request is to determine whether the EDG load sequence testing conducted during the last refueling outage met Technical Specification (TS) and regulatory requirements.
The inspector questioned the adequacy of Entergys testing as it relates to the Pilgrim TS Surveillance Requirements (SRs). Pending further review, the inspectors documented this as an unresolved item in NRC Inspection Report No. 05000293/2005003.
Specifically, Region I requested a determination, from the NRC Office of Nuclear Reactor Regulation (NRR), of the following issues:
- 1. Is testing of the EDG with some loads in conjunction with overlap testing acceptable to meet the requirements of this SR? Specifically, can sequencer testing for timing; individual start and run of equipment, while being supplied by offsite power; full load testing of the diesel; and the Special Test for Automatic ECCS Load Sequencing of Diesels and Shutdown Transformer with Simulated Loss of Offsite Power and Special Shutdown Transformer Load Test show that the conditions under which the diesel generator is required ... accept the emergency loads within the specified time sequence.
- 2. Is Entergys position, i.e., that small loads added to the diesel will not impact diesel performance as long as the total load placed on the diesel is below its rated load, acceptable? If so, what constitutes a small load?
- 3. If it is determined that from a technical aspect the testing performed by the licensee does ensure that the diesel and sequencer will fulfill their design functions, does the licensee need to amend their TS to ensure compliance with the words in the SR?
R. Blough Based on additional information submitted by the licensee, NRR, Division of Engineering, Electrical Engineering Branch and Division of Inspection and Regional Support, Technical Specifications Branch has completed its evaluation of the above technical issues. A summary of the staffs determination is as follows:
The purpose of SR 4.9.A.1.b is to verify:
- 1) EDG performance (voltage and speed) under transient conditions, and
- 2) operability of the EDG load sequence logic Operability of the diesel engine and ac generator under simulated emergency conditions is demonstrated through surveillance testing. Pilgrim SR 4.9.A.1.b is used to verify that the diesel engine can provide the load capacity and torque needed to maintain generator speed (frequency) and that the voltage regulator and excitation system can provide the high reactive power necessary to maintain terminal voltage within acceptable limits. If these capabilities are not periodically demonstrated, the technical bases for declaring the EDG to be operable lack credibility.
The staff concludes that testing of the EDG without sequencing all the emergency connected loads as defined by the licensee final safety analysis report (FSAR) Table 8.5.1, is not in compliance with the stated TS SR 4.9.A.1.b. The staff expects the licensee to follow its FSAR Section 8.5.5 which states that Readiness can be demonstrated by periodic testing which insofar as practical, simulates actual emergency conditions. Overlap testing of the emergency connected loads should be limited to small loads such as motor operated valves (MOVs) and other similar load capacity components which would cause damage or undesirable consequences if actuated during testing.
The current Pilgrim TSs adequately provide the sequence load testing expected by the NRC staff. Pilgrim SR 4.9.A.1.b is similar to the standard technical specification (STS) SR 3.8.1.11 and SR 3.8.1.19 for BWR/4 (NUREG - 1433, R3.1).
The draft TIA response was issued for Region I comments on September 29, 2006. Based on a teleconference with the Region on October 16, 2006, Region I had no comments. NRRs final TIA response is attached. There were additional comments from the NRC Staff that were incorporated in this final response, these changes did not substantially alter the NRC staff conclusions from the draft response.
Docket No. 50-293
Enclosure:
As stated
R. Blough Based on additional information submitted by the licensee, NRR, Division of Engineering, Electrical Engineering Branch and Division of Inspection and Regional Support, Technical Specifications Branch has completed its evaluation of the above technical issues. A summary of the staffs determination is as follows:
The purpose of SR 4.9.A.1.b. is to verify:
- 1) EDG performance (voltage and speed) under transient conditions, and
- 2) operability of the DG load sequence logic Operability of the diesel engine and ac generator under simulated emergency conditions is demonstrated through surveillance testing. Pilgrim SR 4.9.A.1.b is used to verify that the diesel engine can provide the load capacity and torque needed to maintain generator speed (frequency) and that the voltage regulator and excitation system can provide the high reactive power necessary to maintain terminal voltage within acceptable limits. If these capabilities are not periodically demonstrated, the technical bases for declaring the EDG to be operable lack credibility.
The staff concludes that testing of the EDG without sequencing all the emergency connected loads as defined by the licensee final safety analysis report (FSAR) Table 8.5.1, is not in compliance with the stated TS SR 4.9.A.1.b. The staff expects the licensee to follow its FSAR Section 8.5.5 which states that Readiness can be demonstrated by periodic testing which insofar as practical, simulates actual emergency conditions. Overlap testing of the emergency connected loads should be limited to small loads such as motor operated valves (MOVs) and other similar load capacity components which would cause damage or undesirable consequences if actuated during testing.
The current Pilgrim TSs adequately provide the sequence load testing expected by the NRC staff. Pilgrim SR 4.9.A.1.b is similar to the standard technical specification (STS) SR 3.8.1.11 and SR 3.8.1.19 for BWR/4 (NUREG - 1433, R3.1).
The draft TIA response was issued for Region I comments on September 29, 2006. Based on a teleconference with the Region on October 16, 2006, Region I had no comments. NRRs final TIA response is attached. There were additional comments from the NRC Staff that were incorporated in this final response, these changes did not substantially alter the NRC staff conclusions from the draft response.
Docket No. 50-293
Enclosure:
As stated DISTRIBUTION:
Non-Public RidsNrrDe RidsNrrDorlLpl1-1 APal LPLI-1 Reading RidsNrrPMJShea RidsNrrDorlLpdi1 RClark RidsNrrDorl RidsNrrLASLittle MThorpe-Kavanaugh TKobetz GWilson ACCESSION No.: Ml062910432 OFFICE LPLI-1/PM LPLI-1/LA ITSB/BC EEEB/BC LPLI-1/BC DORL/DD NAME JShea CRaynor for SLittle TKobetz GWilson RLaufer JLubinski DATE 11/16/06 10/27/06 9/22/06 9/26/06 11/16/06 11/17/06 OFFICIAL RECORD COPY
STAFF ASSESSMENT BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR TASK INTERFACE AGREEMENT 2006-01 RELATED TO THE ADEQUACY OF EMERGENCY DIESEL GENERATOR AND SHUTDOWN TRANSFORMER LOAD TESTING AT PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 BACKGROUND
On March 10, 2005, Entergy Nuclear Operations, Inc. (Entergy or the licensee) approved a change to Procedure No. 8.M.3-1, Special Test for Automatic ECCS [Emergency Core Cooling System] Load Sequencing of Diesels and Shutdown Transformer with Simulated Loss of Offsite Power and Special Shutdown Transformer Load Test, using Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59 process. This licensee procedure is used to fulfill the requirements of Technical Specification (TS) Surveillance Requirement (SR) 4.9.A.1.b. One aspect of the change involved removing the automatic sequencing of the reactor building closed cooling water (RBCCW) and salt service water (SSW) pumps (both of which are emergency connected loads) during the simulated loss-of-coolant accident (LOCA)/loss-of-offsite power (LOOP) testing.
Pilgrim SR 4.9.A.1.b, states Once per operating cycle the condition under which the diesel generator is required will be simulated and test conducted to demonstrate that it will start and accept the emergency loads within the specified time sequence.... and SR 4.9.A.1.c, states Once per operating cycle with diesel loaded per 4.9.A.1.b verify that on diesel generator trip, secondary (offsite) AC power is automatically connected within 11.8 to 13.2 seconds to the emergency service buses and emergency loads are energized through the load sequencer in the same manner as described in 4.9.A.1.b.1...
The inspector questioned the adequacy of Entergys testing as it relates to the requirements of the TS SRs. Entergy justified the change to the testing based, in part, on the TS 4.9.A.1 bases wording which discusses start and run time requirements for the core spray and residual heat removal pumps sequence timing to verify safety analysis assumptions described in the Pilgrim Updated Final Safety Analysis Report (UFSAR). The licensee stated that to meet the SRs they combined the results of the test in question with their existing load sequencer testing, amperage loading calculations and full-load diesel testing. The inspectors found that this testing does not actually verify the complete loading sequence following an emergency diesel generator (EDG) start from ambient conditions as prescribed by TS 4.9.A.1.b nor shutdown transformer loading following an EDG trip as prescribed by TS 4.9.A.1.c. As a result, the inspectors questioned whether Entergy could make this change without prior Nuclear Regulatory Commission (NRC) approval.
Enclosure
2.0 EVALUATION By this Task Interface Agreement, the NRC Region I office requested answers to the following questions:
- 1. Is testing of the EDG with some loads in conjunction with overlap testing acceptable to meet the requirements of this SR? Specifically, can sequencer testing for timing; individual start and run of equipment, while being supplied by offsite power; full load testing of the diesel; and the Special Test for Automatic ECCS Load Sequencing of Diesels and Shutdown Transformer with Simulated Loss of Offsite Power and Special Shutdown Transformer Load Test show that the conditions under which the diesel generator is required ... accept the emergency loads within the specified time sequence.
The purpose of TS SRs 4.9.A.1.b and 4.9.A.1.c is to demonstrate the operation of the EDG during LOCA/LOOP. Although Pilgrim has custom TSs, these TS SRs 4.9.A.1.b and 4.9.A.1.c are equivalent to the Standard Technical Specification (STS) (NUREG-1433, R3.1) SR 3.8.1.11, and SR 3.8.1.19. The bases for the STS states: The requirement to verify the connection and power supply of permanent and auto-connected loads is intended to satisfactorily show the relationship of these loads to the EDG loading logic (emphasis added).
In certain circumstances, many of these loads cannot actually be connected or loaded without potential for undesired operation. For instance, emergency core cooling systems (ECCS) injection valves are not desired to be stroked open, high pressure injection systems are not capable of being operated at full flow, or shutdown cooling systems performing a decay heat removal functions are not desired to be realigned to the ECCS mode of operation. In lieu of actual demonstration of connection and loading of loads, testing that adequately shows the capability of the EDG system to perform these functions is acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified. The STSs provide these provisions for conducting such overlapping tests for small loads which are typically loads associated with motor operated valves (MOVs) and other similar load capacity components because operating these components could cause undesirable effects such as ECCS injection.
The Pilgrim bases is similar except in the description of what may not be practical for sequencing emergency connected loads. The Pilgrim bases states in part, The test of the diesel generator during the refueling outage will be more comprehensive in that it will functionally test the system; i.e., it will check diesel generator starting, closure of the diesel generator breaker, and sequencing of load on the diesel generator.
On April 24, 2006, the NRC staff asked the licensee to provide the basis for determining the inability to sequence one RBCCW and one SSW pump on the EDG during surveillance testing of TS SRs 4.9.A.1.b and 4.9.A.1.c. By letter dated June 5, 2006, the licensee stated that B trains of RBCCW and SSW were not available during the SRs of the B EDG conducted on April 28, 2005. The RBCCW and SSW were not available since the RBCCW heat exchanger was out of service for channel repairs and eddy current testing. The SSW and RBCCW systems were returned to service on April 29, 2005, at 12:00 pm and on April 30, 2005, at 4:00 am, respectively.
On April 24, 2006, the NRC staff asked the licensee to explain why starting the last sequenced loads, RBCCW and SSW pumps, will not adversely affect the performance of the EDG.
On June 5, 2006, the licensee provided the EDG performance impact of starting the last sequenced load(s) RBCCW and SSW. The licensee stated that in the SR, the core spray pump and two residual heat removal pumps are running at minimum flow. Actual loading on the EDG at the point when all three of these pumps are running (which includes all other loads normally powered in this configuration) is 1053 kW [1.7321 x 180 (measured current) x 4222 (measured voltage) x 0.8 (assumed power factor)]. The EDG power margin available is 1547 kW [2600 (EDG continuous rating) -1053] for starting of SSW and RBCCW pumps. The inrush and steady state power requirements for the SSW pump are 560 kW [100 (HP) x 0.746 (kW/HP) x 6 (inrush factor) / 0.8 (efficiency)] and 93.25 kW [100 (HP) x 0.746 (kW/HP) /
0.8(efficiency)], respectively.
The starting and steady state power requirements for the RBCCW pump are 336 kW
[60 (HP) x0.746 (kW/HP) x 6 (inrush factor) / 0.8 (efficiency)], and 55.95 kW
[60 (HP) x 0.746 (kW/HP) /0.8(efficiency)], respectively. With 1547 kW available, there is sufficient capacity on the EDG to start the SSW pump, which develops 560 kW inrush, then 93.25 kW during steady state. After the SSW pump is started, the available margin is 1453.75 kW (1547-93.25) to start the RBCCW pump load of 336 kW during inrush, then 55.95 kW during steady state. The licensee further demonstrated that the EDG has sufficient kVA margin to start and run both RBCCW and SSW pumps. The NRC staff finds that overlap testing auto-connected loads including the RBCCW and SSW pumps could technically justify the diesel load sequence design function however, overlap testing could not demonstrate the EDG performance under transient conditions, and does not satisfy the Pilgrim SR requirement to demonstrate the emergency load sequence.
- 2. Is Entergys position, i.e., that small loads added to the diesel will not impact diesel performance as long as the total load placed on the diesel below its rated load, acceptable? If so, what constitutes a small load?
Overlapping tests for small loads which are loads primarily associated with some specific MOVs and other similar load capacity components are allowed by the STS, because operating these components could cause undesirable effects such as ECCS injection. The staff expects the licensee to follow its TSs which states that The condition under which the diesel generator is required will be simulated and test conducted to demonstrate that it will start and accept the emergency load within the specified time sequence. This would include all emergency connected loads that would not result in an undesirable consequence or equipment damage.
Undersirable consequence would not include schedule inconvenience or plant maintenance priorities that would prevent testing emergency connected loads.
Entergys position that small loads will not impact EDG performance, is not acceptable to the NRC staff. The above position does not address the starting requirements of the small loads and available margin on the EDG. The addition of small loads will have no impact on the performance of EDG if the available margin (kW and kVA) on the EDG before the addition of the small loads is greater than the starting requirements (kW and kVA) of the small loads.
However, in order to simulate actual conditions the test should include all loads practical including small loads that would not produce undesirable operational effects.
- 3. If it is determined that from a technical aspect the testing performed by the licensee does ensure that diesel and sequencer will fulfill their design functions, does the licensee need to amend their TS to ensure compliance with the words in the SR?
In response to question 1, the NRC staff has determined that from a technical aspect the testing performed by the licensee provides some assurance that the EDG and sequencer could fulfill their design functions. However, the licensee should follow its TSs and the Final Safety Analysis Report (FSAR) Section 8.5.5 which states that Readiness can be demonstrated by periodic testing which insofar as practical, simulates actual emergency conditions. The licensee is not in compliance with its custom TS modifying the test to exempt RBCCW and SSW loads. We understand that the A trains of RBCCW and SSW systems were available and were included in the surveillance test of the A EDG.
The current Pilgrim TSs adequately provide the sequence load testing expected by the NRC staff. Pilgrim SR 4.9.A.1.b is similar to STS for BWR/4 SR 3.8.1.11 and SR 3.8.1.19.
3.0 Conclusion The NRC staff concludes that testing of the EDG without sequencing all the emergency connected loads as defined by the licensee in its UFSAR Table 8.5.1, is not in compliance with the stated TS SR 4.9.A.1.b. The licensee is expected to comply with its licensing basis in UFSAR Section 8.5.5 which states that Readiness can be demonstrated by periodic testing which insofar as practical, simulates actual emergency conditions. Overlap testing of the emergency connected loads should be limited to MOVs and other similar load capacity components which would cause damage or undesirable consequences if actuated during testing.
The addition of small loads which are identified in the STS as MOVs and other similar load capacity components do not have a great impact on the performance of an EDG as long as the available margin (kW and kVA) on the EDG before the addition of the small loads is greater than the starting requirements (kW and kVA) of the small loads.
The current Pilgrim TSs adequately provide the sequence load testing expected by the NRC staff. Pilgrim SR 4.9.A.1.b is similar to the STS SR 3.8.1.11 & 19.
Principal Contributors: A. Pal R. Clark Date: November 17, 2006