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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
+ EnEet-gy I CONDITION REPORT CR-PNP-2002-09283 Originator: Helms,Ralph E Originator Phone: 8957 Originator Group: Maint Mechanical Mgmt Operability Required: Y Reportability Required: Y Supervisor Name: T.Fox Discovered Date: 02/27/2002 01:35 Initiated Date: 02/27/2002 02:23 Condition
Description:
Unable to reassemble E-l22B, "B"TBCCW Heat Exchanger Channel Head end due to leakage at Salt Service Water (SSW) isolation valves. Suspect MO-3805 and / or 29-HO-3833 are leaking by.
(This was problem was originally identified on 2/26/02 (90100 hrs.) First attempt on 2/26/02 (90430 hrs. appeared to stop leakage but the drain path was not checked prior to manipulations so it was unclear whether it was the valve(s) or tide level.
This was during Low Tide.
No further manipulations were conducted and flow was again present at 1000 hrs. during High tide. Attempts to stop SSW leakage during the dayshift through the Low Tide were also unsuccessful.
Lost production time / manhours and increased equipment out of service time (>24 hrs.) due to this issue.
Also, if isolation is obtained during a Low Tide, reassembly will require going through two (2) additional Low Tides due to piping configuration and adequate time for reassembly of Channel Head and Cover onto E-122B.
Immediate Action
Description:
Notified OPS and attempted to stop SSW flow but unsuccessful.
Re-attempt(s) to stop leakage will be perfomed during Low Tide.
Suggested Action
Description:
NESG to review history of maintenance conducted on these valves and forward recommentation for repair / replacement of these valves.
' Entergy I ADMIN CR-PNP-2002-09283 Initiated Date: 2/27/2002 2:23 Owner Group :Eng Sys Mgmt Current
Contact:
Current Significance: C - CORRECTION Closed by: Walker,James 0 4/2/2002 10:12 Summary
Description:
Remarks
Description:
PR=EF E-122B 'B' TBCCW HEAT EXHANGER CHANNEL HEAD SSW MO-3805 29-HO-3833 Closure
Description:
S e e CA#l. Close CR per CRG.
Enfwgy
~~~
OPERABILITY 1 CR-PNP-2002-09283 OperabilityVersion: 1 Operability Code: ADMIN - NA Immediate Report Code: NOT REPORTABLE Performed By: Perry,Douglas C 02/27/2002 04: 11 Approved By: Perry,Douglas C 02/27/2002 04: 16 Operability
Description:
Operability not applicable Approval Comments:
Resolution should include consideration of MO-3805 IST requirements should that valve be determined to be leaking.
- En-w I A SSI GNMENTS I CR-PNP-2002-09283 Version: 1 Significance Code: C - CORRECTION Classification Code: NON-SIGNIFICANT Owner Group: Eng Sys Mgmt Performed By: Buckley,Patricia A 02/28/2002 12:29 Assignment
Description:
Evaluate for corrective action.
- EnfeeY I REPORTABILITY I CR-PNP-2002-09283 Reportability Version: 1 Report Number:
Report Code: NOT REPORTABLE Boilerplate Code: NOT REPORTABLE Performed By : Brennion,Carl S 02/27/2002 10:13 Reportability
Description:
Not reportable - This event does not meet the screening criteria of WI 3.06-01.
CA Number: 1
~ Group I!
I Name I Assigned By: CRG Mgmt Assigned To: Eng Sys Mech Staff Lamoureux,Joseph R Subassigned To : Eng Sys Mech Staff GaedtkeJoseph R Originated By: Buckley,Patricia A 2/28/2002 12:35:57 Performed By: Gaedtke,Joseph R 3/29/2002 13:06:28 Subperformed By:
Approved By:
Closed By: Gaedtke,Joseph R 3/29/2002 13:06:28 Current Due Date: 03/30/2002 Initial Due Date: 03/30/2002 CA Type: CORRECTIVE ACTION Plant Constraint: NONE CA
Description:
Review the issues regarding the inability to reassemble E-l22B, "B" TBCCW Heat Exchanger Channel Head end. Develop an action plan and assign required corrective actions as appropriate to address this issue.
Response
Please review issues and assign corrective actions as required to other NESG groups, such as components, to ecaluate valves to assist in dvelopment of plan.
Enftygy CORRECTIVE ACTION CR-PNP-2002-09283 Complete isolation of E-122B for maintenance was primarily affected by leakage past the seat of MO-3805 ("B" TBCCW/SSW Discharge Valve). This leakage was previously identified on 5/7/00 under MR10001079 by the SSW System Engineer during troubleshooting for macrofouling concerns of E-209A, E-209B, E-122A & E-122B Heat Exchangers. A TIC was submitted by the SSW System Engineer to recommend replacement of this valve during RF0#13. The TIC was later rejected and the valve was not replaced. The SSW System "B" Loop was drained during RF0#13 a replacement valve was on-hand and this valve could have been replaced without impacting the Outage Schedule.
MR02101255 - PERFORM 2.2.31.1, EVALUATED LEAKAGE PAST MO-3805 - This M R was closed on 1/30/02 -
Leakage was found to be acceptable - Operations performing leak verification indicated by hearing a vacuum vs. experiencing a fluid leak, and determined that this leakage would not affect the isolation of E-122B for maintenance.
MR10001079 - VALVE LEAKS BY ITS SEAT - This MR was later cancelled on 1/29/02. It was cancelled due to evaluation results of MR02101255 above CANCEL, VALVE WAS TESTED UNDER MR02101255 BY O P S WHICH DETERMINED/VERIFIED LEAKAGE TO BE ACCEPTABLE.
B. COOLIDGE/R.W. M CCUE 01/29/2002.
M R #02104125 written on 2/28/02 to identify seat leakage and the difficulty obtaining isolations of E-122B.
MO-3805 LEAKED BY IT'S SEAT WITH IT TAKEN UP TIGHT MANUALLY WITH HANDWHEEL SEAT LEAKAGE This MR has been approved by Outage Management to replace this leaking valve in RF0#14.
PM#POOOO715 Scheduled for (10/20/04 due & dead) - MOV PM ON MO-3805 IAW 8.4.3-8.1 (SMB-000).
can be worked at the same time that the valve is being replaced. This task and the replacement of the valve can be worked together and the valve seat limit stops can be set with the valve out of the adjacent piping spools. This work will assist the craft in verifying that the limit stops are properly set and that the seat did not travel beyond its normally closed position.
This valve as last replaced on 11/1/94 under MR19300991. It is possible that the limit stops were improperly set and the valve disc traveled beyond its closed position. If this was the case, damage to the Rubber Lined body (seat) could have occurred. Inspection of the existing valve when it is removed should indicate this condition.
In Summary: Replacement of this valve (MO-3805) during RF0#14 should address future on-line isolations of SSW to E-122B "B"TBCCW Leakage past this valve will not affect its safety function to go to 10% open durning in an acident condition.
This CA has been presented to CRG for closure to MR02104125. CRG has approved this CA to be closed to MR02104125.
No further action is required.
Closure Comments: