RNP-RA/02-0172, Steam Generator Tube Plugging During Refueling Outage 21
ML023170211 | |
Person / Time | |
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Site: | Robinson |
Issue date: | 11/11/2002 |
From: | Baucom C Carolina Power & Light Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
RNP-RA/02-0172 | |
Download: ML023170211 (3) | |
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Category:Letter type:RNP
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Robinson Steam Electric Plant ML12068A1332012-02-23023 February 2012 Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant.2009-07-31031 July 2009 WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant. RNP-RA/09-0054, Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation2009-06-19019 June 2009 Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 RNP-RA/06-0081, Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet, WCAP-16627-NP2006-08-31031 August 2006 Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet, WCAP-16627-NP RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.2006-03-31031 March 2006 ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis. ML0507004082004-02-20020 February 2004 EMF-3030(NP), Revision 0, Robinson Nuclear Plant, Realistic Large Break LOCA Analysis, February 2004, Non-Proprietary Version RNP-RA/03-0075, Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-62003-07-31031 July 2003 Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6 RNP-RA/03-0031, Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 5042003-04-28028 April 2003 Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504 ML0311207052003-04-18018 April 2003 Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001 ML0305202692003-02-15015 February 2003 Follow-up Report, Reference Event #39516 RNP-RA/03-0012, Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent2003-02-11011 February 2003 Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent RNP-RA/02-0172, Steam Generator Tube Plugging During Refueling Outage 212002-11-11011 November 2002 Steam Generator Tube Plugging During Refueling Outage 21 RNP-RA/02-0164, Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License2002-11-0606 November 2002 Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License ML0230402682002-09-19019 September 2002 Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual ML0221103432002-01-31031 January 2002 Caldon, Inc Engineering Report: ER-267N, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM Check Plus System ML18288A3691990-10-31031 October 1990 ANF-88-054(NP)(A), PDC-3: Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2. NRC Generic Letter 1979-451979-09-25025 September 1979 NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences 2023-07-12 |
Text
TS 5.6.8a SCP&L SProgress Energy , , ,:,
Serial: RNP-RA/02-0172 NOV I 12002 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 STEAM GENERATOR TUBE PLUGGING DURING REFUELING OUTAGE 21 Ladies and Gentlemen:
In accordance with the H. B. Robinson Steam Electric Plant, Unit No. 2, Technical Specifications Section 5.6.8, "Steam Generator Tube Inspection Report," Paragraph a, Carolina Power & Light Company submits the attached report on steam generator tube plugging during Refueling Outage 21.
The steam generator tube plugging was completed on October 29, 2002.
If you have any questions concerning this matter, please contact me.
Sincerely, C. T. Baucom Supervisor - Licensing and Regulatory Programs CAC/cac Attachment c: NRC Resident Inspector, HBRSEP L. A. Reyes, NRC, Region II R. Subbaratnam, NRC, NRR
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0172 Page 1 of 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 STEAM GENERATOR TUBE PLUGGING DURING REFUELING OUTAGE 21 Steam Generator Tube Comments A R37C50 Wear is at top of tubesheet at hot leg side due to transient loose part. No loose part was determined to be present. This tube was last examined during Refueling Outage (RO) 19 in 1999 and there has been a slight change in the indication. The indication depth is below plugging limit required by the Technical Specifications. The indication was bounded by inspection of the surrounding tubes. The tube was preventatively plugged.
A R38C50 Wear is at top of tubesheet at hot leg side due to transient loose part. No loose part was determined to be present. This tube was last examined in 1999 (RO-19) and there has been a slight change in the indication. The indication depth is below plugging limit required by the Technical Specifications. The indication was bounded by inspection of the surrounding tubes. The tube was preventatively plugged.
A R37C51 Wear is at top of tubesheet at hot leg side due to transient loose part. No loose part was determined to be present. This tube was last examined in 1996 (RO-17) and there was no indication present. The indication depth is below plugging limit required by the Technical Specifications. The indication was bounded by inspection of the surrounding tubes. The tube was preventatively plugged.
A R4C39 Indication is attributed to mechanical wear. No loose part was determined to be present. This tube was last examined in 1996 (RO-17) and there was no indication present. The indication depth is below plugging limit required by the Technical Specifications. The tube was preventatively plugged.
B R1C27 Peripheral tube in blowdown lane with mechanical wear. The cause of this indication was attributed to impact by maintenance equipment. The indication correlates with equipment insertion down the blowdown lane.
The tube was preventatively plugged.
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/02-0172 Page 2 of 2 Steam Generator Tube Comments B R34C43 Indication is attributed to wear due to loose part. The loose part was determined to be still present. The indication was bounded by examining surrounding tubes, with no other indications found. The tube was preventatively plugged and staked.
B R24C65 Indication is attributed to wear at the flow distribution baffle on hot leg side. No loose part was determined to be present. This tube was last examined in 1998 (RO-18) and there was no indication present. The indication depth is below plugging limit required by the Technical Specifications. The tube was preventatively plugged.
C R45C41 Wear is below the 6"' support plate on the hot leg side and is indicative of transient loose part wear. No loose part was determined to be present.
This tube was last examined in 2001 (RO-20) and there was no indication present. Adjacent tubes were examined, with no indications or loose parts found.