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| Line 16: |
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| =Text= | | =Text= |
| {{#Wiki_filter:~ Entergy I CONDITION REPORT Originator: | | {{#Wiki_filter:I |
| CONVERTED DATA Originator Group: CONVERTED DATA Supervisor Name: CONVERTED DATA Discovered Date: I 1/27/1996 0O:OO CR-PNP-199609593 Originator Phone: | | ~ |
| 0 Operability Required:
| | Entergy CONDITION REPORT CR-PNP-199609593 Originator: CONVERTED DATA Originator Phone: 0 Originator Group: CONVERTED DATA Operability Required: N Reportability Required: N Supervisor Name: CONVERTED DATA Discovered Date: I 1/27/1996 0O:OO Initiated Date: 11/27/1996 0O:OO Condition |
| N Reportability Required:
| |
| N Initiated Date:
| |
| 11/27/1996 0O:OO Condition | |
|
| |
|
| == Description:== | | == Description:== |
|
| |
|
| DURING SHOP WORK ON THE OLD MOV HOUSING FOR MO-1001-34A, A CRACK WAS FOUND ON ONE WPPER HOUSING FLANGE BOLT HOLE. THE ACTUATOR HOUSING WAS BEING REFURBISHED PER P2403876 FOR RE-USE AS MO-1201-85 IN RFO #I I. Immediate Action | | DURING SHOP WORK ON THE OLD MOV HOUSING FOR MO-1001-34A, A CRACK WAS FOUND ON ONE WPPER HOUSING FLANGE BOLT HOLE. THE ACTUATOR HOUSING WAS BEING REFURBISHED PER P2403876 FOR RE-USE AS MO-1201-85 IN RFO #I I. |
| | Immediate Action |
|
| |
|
| == Description:== | | == Description:== |
| | |
| Suggested Action | | Suggested Action |
|
| |
|
| Line 33: |
Line 32: |
|
| |
|
| EQUIPMENT: | | EQUIPMENT: |
| Tag Name REFERENCE ITEMS: TvPe Code CONVERTED PR Tag Suffix Name Component Code Process System Code 99 Description PR.96.9593 | | Tag Name Tag Suffix Name Component Code Process System Code 99 REFERENCE ITEMS: |
| 'I I I 1 ADMIN CR-PNP-1996-09593 Initiated Date: 11/27/1996 0:OO Owner Group | | TvPe Code Description CONVERTED PR PR.96.9593 |
| :CA&A Staff Current Contact: WALKER, J. Current Significance: | | |
| D - ADMIN CLOSE Closed by: WALKER, J. 12/4/1996 0:OO I ~ Summary | | ' I I I 1 ADMIN CR-PNP-1996-09593 Initiated Date: 11/27/1996 0:OO Owner Group :CA&A Staff Current Contact: WALKER, J. |
| | Current Significance: D - ADMIN CLOSE Closed by: WALKER, J. 12/4/1996 0:OO I ~ |
| | Summary |
|
| |
|
| == Description:== | | == Description:== |
|
| |
|
| DURING SHOP WORK ON THE OLD MOV HOUSING FOR MO-1001-34A9 A CRACK WAS FOUND ON ONE UPPPER HOUSING FLANGE BOLT HOLE. THE ACTUATOR HOUSING WAS BEING REFURBISHED PER P2403876 FOR RE-USE AS MO-1201-85 IN RFO #11. Remarks | | DURING SHOP WORK ON THE OLD MOV HOUSING FOR MO-1001-34A9A CRACK WAS FOUND ON ONE UPPPER HOUSING FLANGE BOLT HOLE. THE ACTUATOR HOUSING WAS BEING REFURBISHED PER P2403876 FOR RE-USE AS MO-1201-85 IN RFO #11. |
| | Remarks |
|
| |
|
| == Description:== | | == Description:== |
| Line 49: |
Line 51: |
|
| |
|
| EVALUATION COMPLIANCE REVIEW EVALUATION AND CORRECTIVE ACTION COMPLETE. | | EVALUATION COMPLIANCE REVIEW EVALUATION AND CORRECTIVE ACTION COMPLETE. |
| Entergy ASSIGNMENTS Version: 1 Significance Code: D - ADMIN CLOSE Classification Code: NON-SIGNIFICm Owner Group: CA&A Staff Performed By: Shatas,Albert A Assignment
| |
|
| |
|
| ==
| | Entergy ASSIGNMENTS CR-PNP-1996-09593 Version: 1 Significance Code: D - ADMIN CLOSE Classification Code: NON-SIGNIFICm Owner Group: CA&A Staff Performed By: Shatas,Albert A 11/27/1996 0O:OO Assignment |
| Description:==
| |
| SCREEN IAW NOP92A1 CR-PNP- 1996-09593 11/27/1996 0O:OO Enterrrv CORRECTIVE ACTION I CR-PNP-1996-09593 I CA Number: 1 - - - - - _- I__ l__ __I .-_. ~ - r- -- -- SHATAS, A. Shatas,Albert A Group I Name Assigned By: CA&A Staff Assigned To: CA&A Staff Subassigned To
| |
| : ~ Originated By: SHATAS, A. Performed By: SHATAS, A. Subperformed By: Approved By: Closed By: SHATAS, A. 11/27/1996 0O:OO:OC 11/27/1996 0O:OO:OC 11/27/1996 0O:OO:OC Current Due Date: 12/04/1996 CA Type: GENERAL Plant Constraint:
| |
| NONE CA
| |
|
| |
|
| == Description:== | | == Description:== |
|
| |
|
| SCREEN IAW NOP92A1 Response: | | SCREEN IAW NOP92A1 |
| Subresponse
| | |
| : CONVERTED DATA Closure Comments: | | Enterrrv I CORRECTIVE ACTION I CR-PNP-1996-09593 CA Number: 1 |
| PAC APPROVED NOP92A1 EXHIBIT 3 Initial Due Date: | | - - - _- .-_. - - - |
| 12/04/1996 CORRECTIVE ACTION I CR-PNP-1996-09593 CA Number: 2 r--- Name I KEENE, J. Haladyna,Robert A Assigned By:
| | I__ |
| Regulatory | | Group l__ __I ~ |
| & Industry Affairs Staff Assigned To: Regulatory | | r-I |
| & Industry Affairs Staff Subassigned To : Originated By: KEENE, J. Performed By: HALADYNA, R. Subperformed By: Approved By: | | -- -- Name Assigned By: CA&A Staff SHATAS, A. |
| Closed By: KEENE, J. 11/27/1996 0O:OO:OC 12/30/1996 0O:OO:OC 12/30/1996 0O:OO:OC Current Due Date: 12/10/1996 Initial Due Date: 12/10/1996 CA Type: GENERAL Plant Constraint: | | Assigned To: CA&A Staff Shatas,Albert A Subassigned To : |
| NONE CA | | ~ |
| | Originated By: SHATAS, A. 11/27/1996 0O:OO:OC Performed By: SHATAS, A. 11/27/19960O:OO:OC Subperformed By: |
| | Approved By: |
| | Closed By: SHATAS, A. 11/27/19960O:OO:OC Current Due Date: 12/04/1996 Initial Due Date: 12/04/1996 CA Type: GENERAL Plant Constraint: NONE CA |
| | |
| | == Description:== |
| | |
| | SCREEN IAW NOP92A1 |
| | |
| | ===Response=== |
| | CONVERTED DATA Subresponse : |
| | Closure Comments: |
| | PAC APPROVED NOP92A1 EXHIBIT 3 |
| | |
| | CORRECTIVE ACTION I CR-PNP-1996-09593 CA Number: 2 r--- Name I Assigned By: Regulatory & Industry Affairs Staff KEENE, J. |
| | Assigned To: Regulatory & Industry Affairs Staff Haladyna,Robert A Subassigned To : |
| | Originated By: KEENE, J. 11/27/19960O:OO:OC Performed By: HALADYNA, R. 12/30/19960O:OO:OC Subperformed By: |
| | Approved By: |
| | Closed By: KEENE, J. 12/30/19960O:OO:OC Current Due Date: 12/10/1996 Initial Due Date: 12/10/1996 CA Type: GENERAL Plant Constraint: NONE CA |
|
| |
|
| == Description:== | | == Description:== |
|
| |
|
| CONDUCT A 10CFR50.73 REVIEW FOR THE CONDITIONS IDENTIFIED IN THIS PROBLEM REPORT. | | CONDUCT A 10CFR50.73 REVIEW FOR THE CONDITIONS IDENTIFIED IN THIS PROBLEM REPORT. |
| Response: | | |
| Subresponse | | ===Response=== |
| : CONVERTED DATA Closure Comments: COMPLETE 10CFR50.73 REVIEW.
| | CONVERTED DATA Subresponse : |
| 10 CFR 50.73 REPORTING APPLICABLE? | | Closure Comments: |
| NO BASIS: THE PROBLEM REPORT IS NOT REPORTABLE BECAUSE IT DID NOT MEET THE REPORTING THRESHOLD ESTABLISHED IN 10CFR50.73 AND IT IS NOT A REPEAT OCCURRENCE. | | COMPLETE 10CFR50.73REVIEW. |
| THE PROBLEM WAS EVALUATED REGARDING POSIBLE OVERTHRUST OF VALVE MO-100 1 -34A WHILE THE HOUSING OPERATOR WAS INSTALLED ON MO-1001-34A. | | 10 CFR 50.73 REPORTING APPLICABLE? NO BASIS: THE PROBLEM REPORT IS NOT REPORTABLE BECAUSE IT DID NOT MEET THE REPORTING THRESHOLD ESTABLISHED IN 10CFR50.73 AND IT IS NOT A REPEAT OCCURRENCE. THE PROBLEM WAS EVALUATED REGARDING POSIBLE OVERTHRUST OF VALVE MO- 1001-34A WHILE THE HOUSING OPERATOR WAS INSTALLED ON MO-1001-34A. IN |
| IN | |
|
| |
|
| ==SUMMARY== | | ==SUMMARY== |
| , THE EVALUATION CONCLUDED THERE WAS NO ADVERSE IMPACT ON VALVE MO-1001-34A WHILE THE OPERATOR WAS INSTALLED ON MO-1001-34A. (NCR 96-44 ALSO DOCUMENTED THE PROBLEM FOR MO-1201-85).}} | | , THE EVALUATION CONCLUDED THERE WAS NO ADVERSE IMPACT ON VALVE MO-1001-34A WHILE THE OPERATOR WAS INSTALLED ON MO-1001-34A. |
| | (NCR 96-44 ALSO DOCUMENTED THE PROBLEM FOR MO-1201-85).}} |
|
|---|
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
[Table view] |
Text
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Entergy CONDITION REPORT CR-PNP-199609593 Originator: CONVERTED DATA Originator Phone: 0 Originator Group: CONVERTED DATA Operability Required: N Reportability Required: N Supervisor Name: CONVERTED DATA Discovered Date: I 1/27/1996 0O:OO Initiated Date: 11/27/1996 0O:OO Condition
Description:
DURING SHOP WORK ON THE OLD MOV HOUSING FOR MO-1001-34A, A CRACK WAS FOUND ON ONE WPPER HOUSING FLANGE BOLT HOLE. THE ACTUATOR HOUSING WAS BEING REFURBISHED PER P2403876 FOR RE-USE AS MO-1201-85 IN RFO #I I.
Immediate Action
Description:
Suggested Action
Description:
EQUIPMENT:
Tag Name Tag Suffix Name Component Code Process System Code 99 REFERENCE ITEMS:
TvPe Code Description CONVERTED PR PR.96.9593
' I I I 1 ADMIN CR-PNP-1996-09593 Initiated Date: 11/27/1996 0:OO Owner Group :CA&A Staff Current Contact: WALKER, J.
Current Significance: D - ADMIN CLOSE Closed by: WALKER, J. 12/4/1996 0:OO I ~
Summary
Description:
DURING SHOP WORK ON THE OLD MOV HOUSING FOR MO-1001-34A9A CRACK WAS FOUND ON ONE UPPPER HOUSING FLANGE BOLT HOLE. THE ACTUATOR HOUSING WAS BEING REFURBISHED PER P2403876 FOR RE-USE AS MO-1201-85 IN RFO #11.
Remarks
Description:
MOV HOUSING MO-1001-34A P9403876 MO-1201-85 LIMITORQUE ACTUATOR Closure
Description:
EVALUATION COMPLIANCE REVIEW EVALUATION AND CORRECTIVE ACTION COMPLETE.
Entergy ASSIGNMENTS CR-PNP-1996-09593 Version: 1 Significance Code: D - ADMIN CLOSE Classification Code: NON-SIGNIFICm Owner Group: CA&A Staff Performed By: Shatas,Albert A 11/27/1996 0O:OO Assignment
Description:
SCREEN IAW NOP92A1
Enterrrv I CORRECTIVE ACTION I CR-PNP-1996-09593 CA Number: 1
- - - _- .-_. - - -
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Group l__ __I ~
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-- -- Name Assigned By: CA&A Staff SHATAS, A.
Assigned To: CA&A Staff Shatas,Albert A Subassigned To :
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Originated By: SHATAS, A. 11/27/1996 0O:OO:OC Performed By: SHATAS, A. 11/27/19960O:OO:OC Subperformed By:
Approved By:
Closed By: SHATAS, A. 11/27/19960O:OO:OC Current Due Date: 12/04/1996 Initial Due Date: 12/04/1996 CA Type: GENERAL Plant Constraint: NONE CA
Description:
SCREEN IAW NOP92A1
Response
CONVERTED DATA Subresponse :
Closure Comments:
PAC APPROVED NOP92A1 EXHIBIT 3
CORRECTIVE ACTION I CR-PNP-1996-09593 CA Number: 2 r--- Name I Assigned By: Regulatory & Industry Affairs Staff KEENE, J.
Assigned To: Regulatory & Industry Affairs Staff Haladyna,Robert A Subassigned To :
Originated By: KEENE, J. 11/27/19960O:OO:OC Performed By: HALADYNA, R. 12/30/19960O:OO:OC Subperformed By:
Approved By:
Closed By: KEENE, J. 12/30/19960O:OO:OC Current Due Date: 12/10/1996 Initial Due Date: 12/10/1996 CA Type: GENERAL Plant Constraint: NONE CA
Description:
CONDUCT A 10CFR50.73 REVIEW FOR THE CONDITIONS IDENTIFIED IN THIS PROBLEM REPORT.
Response
CONVERTED DATA Subresponse :
Closure Comments:
COMPLETE 10CFR50.73REVIEW.
10 CFR 50.73 REPORTING APPLICABLE? NO BASIS: THE PROBLEM REPORT IS NOT REPORTABLE BECAUSE IT DID NOT MEET THE REPORTING THRESHOLD ESTABLISHED IN 10CFR50.73 AND IT IS NOT A REPEAT OCCURRENCE. THE PROBLEM WAS EVALUATED REGARDING POSIBLE OVERTHRUST OF VALVE MO- 1001-34A WHILE THE HOUSING OPERATOR WAS INSTALLED ON MO-1001-34A. IN
SUMMARY
, THE EVALUATION CONCLUDED THERE WAS NO ADVERSE IMPACT ON VALVE MO-1001-34A WHILE THE OPERATOR WAS INSTALLED ON MO-1001-34A.
(NCR 96-44 ALSO DOCUMENTED THE PROBLEM FOR MO-1201-85).