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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML16067A1442016-01-28028 January 2016 SEP-ISI-PNPS-002, Rev 2, Pilgrim, Fifth Ten-Year Interval Inservice Inspection (Isi/Iwe) Program Plan. ML15237A2582015-08-20020 August 2015 Refueling Outage (RFO)-20, In-Service Inspection (ISI) Owners Activity Report (OAR-1) Submittal ML14091A4072014-03-25025 March 2014 Relief Request PRR-25 Rev. 1, Proposed Alternative, Request for Relief for Temporary Acceptance of a Flaw in Salt Service Water (SSW) System Pipe Spool JF29-8-4 ML11230A9192011-08-0505 August 2011 Revised Relief Request (PRR)-21, Contingency Repair Plan for Reactor Pressure Vessel (RPV) Standby Liquid Control Nozzle Weld, RPV-N14-1 ML11235A7292011-07-27027 July 2011 Refueling Outage (RFO)-18 In-Service Inspection (ISI) Owner'S Activity Report (OAR-1) Submittal ML0924505922009-08-24024 August 2009 Submittal of Refueling Outage (RFO) -17 In-Service Inspection (ISI) Owners Activity Report (OAR)-1 CNRO-2009-00003, Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activ2009-03-17017 March 2009 Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activities ML0811507162008-04-16016 April 2008 Request for Approval of Proposed Relief Request VR-4A to Extend 5-Year Test Interval on a One-Time Basis for One Main Steam Safety Valve RV-203-4A, Transmittal of Inservice Testing Relief Request No. RV-07, Letter No. 2.08.021 ML0721802372007-07-31031 July 2007 Refueling Outage 16, Inservice Inspection (ISI) Summary Report ML0714301882007-05-16016 May 2007 Third Ten-Year ISI Interval Relief Request, PRR-42, Examinations of Component Welds with Less than Essentially 100% Examination Coverage ML0521602742005-07-29029 July 2005 Inservice Inspection Summary Report for Refuel Outage 15 ML0507404042005-03-0707 March 2005 2005 On-Line and Refueling Outage (RFO) - 15 Inservice Inspection (ISI) Plan ML0506303972005-02-24024 February 2005 Fourth Ten-Year In-service Testing (IST) Program, IST Relief Request PR-03 (TAC N0.MB8779) ML0416203922004-06-0202 June 2004 Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Fourth Ten-Year In-service Testing (IST) Program, IST Relief Requests: PR-03 (TAC No. MB8779), VR-03 (MB8777), VR-04 (MB8778), and VR-06 (MB8780) JPN-04-010, Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs2004-04-14014 April 2004 Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs ML0325911412003-09-0808 September 2003 Startup Test Report Cycle 15 ML0322500572003-08-0101 August 2003 Refueling Outage (RFO) - 14 Inservice Inspection (ISI) Summary Report ML0707902282003-07-0808 July 2003 RF014 ISI Summary Report for NRC Submittal with Attachment ML0715602512003-04-27027 April 2003 CR-PNP-2003-01618 with Supporting Report (with Redacted Notes) 1st Page for Inspector ML0311301182003-04-14014 April 2003 2003 On-Line and Refueling Outage (RFO) - 14 Inservice Inspection (ISI) Plan 2016-01-28
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Ente#g-y CORRECTIVE ACTION CR-PNP-2003-01618 Approved By:
Closed By: Pace,Raymond M I 2 Current Due Date: 05/05/2003 Initial Due Date: 05/05/2003 I\
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CA Type: CORRECTIVE ACTION Plant Constraint: RFO14D- DRN DWN VSSL CA
Description:
IS1 has completed the IWE Containment Examination in accordance with procedure 2.1.8.7. This examination was compared to the previous as documented in PR 99-1 145 and no significant changes are apparent however some added indications were reported. This CR documents that coating threshold failures as described in 2.1.8.7 have been exceeded. This examination is documented on QC Inspection Report 03-0283. One area that was not reported with rusting i s the CRD penetration area which is at 35 foot elevation and azimuths of 290 and 265 dergees.
Validate the problem statement and determine corrective actions to resolve the adverse condition. Perform troubleshootinghepairs as required.
Response
The sub-response given below is adequate for closure of the CA and the CR in accordance with the requirements of LI-102.
Ray Pace 07/01/03 Subresponse :
The findings of QC Inspection Report 03-0283 were reviewed and there are no significant corrosion issues. Most areas appear to be similar to that documented in PR 99-1 145.
ted for long periods This CR can be closed and no other action is required.
Closure Comments:
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Dryweli elevation (rollout)
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Flengg DRYWELL 83 933-3134 0 0 371-1
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NORTH DRYWELL 74 8 0
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180 Drywell elevation (rollout)
Area No.
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Blister-Ing Flaking Peeling Cfack-ing Pitt-hg Rust-Inn Disc*
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Damage Un-coated Arc SLrikes Dents Dlsk No Photo No.
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I I I EXAMINER S I G N A T U R E S - . q/z r / n DATE q-a 2.1.8.7 Rev. 3 pqEv//LU /#H/c&*-.g- .yG-,T fi; . 7&?- fl--
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All Prerequisites (basedocument Section 6.0) met.
inittais Orvwell F l a m DRYWELL 41
90 180 270 270
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Prvwell Flanae DRYWELL41 93'-3 314" NORTH 0
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PEZl Sheet 1 of 1 AU Prerequisites (base document Section 6.0) met. %dEd E .
Name (print)
& Initials TORUS EXTERIOR (LOWER HALF1 BAY # 2 Torus outboard Torus centerline EXAMINEfi SIGNATURES
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TORUS EXTERlOR (LOWER HALF) BAY # &
Torus outboard
____-___ side at El. (-)03" Torus centerline Torus Exterior .
Lower Half Rollout
Torus outboard side at El. (-)03"
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Torus Exterior Lower Half Rollout