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MONTHYEAR3F0608-05, Response to Request for Additional Information Regarding Relief Requests 07-001-SS, Revision 0, Alternate Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 Areas 120 Degrees Apart .2008-06-0505 June 2008 Response to Request for Additional Information Regarding Relief Requests #07-001-SS, Revision 0, Alternate Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 Areas 120 Degrees Apart . Project stage: Response to RAI 3F0808-03, Relief Request 07-001-SS, Revision 1, Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on Three Areas 120 Degrees Apart on the Inside Surface..2008-08-14014 August 2008 Relief Request #07-001-SS, Revision 1, Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on Three Areas 120 Degrees Apart on the Inside Surface.. Project stage: Request ML0822103922008-09-0909 September 2008 Request for Relief No. 07-001-SS Regarding the Fourth 10-Year Interval Inservice Inspection Visual Examination of the Reactor Vessel Support Skirt Project stage: Other 2008-08-14
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Category:- No Document Type Applies
MONTHYEARML21288A4302021-10-18018 October 2021 Enclosure - Crystal River Unit 3 Nuclear Generating Plant - Correction to Safety Evaluation Related to the Issuance of Amendment No. 259 Approving the Independent Spent Fuel Storage Installation Only Emergency Plan ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status RA-11-025, Enclosure 1, Attachment 2 - Duke Energy Corporation and Progress Energy, Inc. Organization Charts Post Merger2011-09-0202 September 2011 Enclosure 1, Attachment 2 - Duke Energy Corporation and Progress Energy, Inc. Organization Charts Post Merger ML1116400572011-06-0707 June 2011 Public Meeting - Crystal River Nuclear Plant - Attendees 3F0311-07, Attachment B, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models2011-03-15015 March 2011 Attachment B, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models ML1027201382010-10-29029 October 2010 Williams Q&A - Request #3 Info-Pugh-PART 6 ML1027201152010-10-29029 October 2010 Williams Q&A- Request #3 Info-Pugh-PART 5 ML1029200682010-09-20020 September 2010 Ncr Number 358724, Assignment Number 23, Crystal River, Unit 3 Containment ML1029200642010-09-20020 September 2010 Petrographic Studies of Concrete for Construction Engineering Consultants ML1029205062010-09-20020 September 2010 Adverse Condition Investigation Form, CAP-NGGC-0200-3-18 ML1023504542010-08-18018 August 2010 P11 Company Background ML1020303412010-07-28028 July 2010 Nuclear Generating Plant - Preliminary Review of Progress Energy'S 10 CFR 50.59 Evaluation ML1020303522010-07-28028 July 2010 Nuclear Generating Plant - Preliminary Review of Progress Energy'S 10 CFR 50.59 Evaluation 3F0610-08, Pef Letter to FDEP NPDES Permit Renewal App CR 4 & 5 January 25, 20102010-06-28028 June 2010 Pef Letter to FDEP NPDES Permit Renewal App CR 4 & 5 January 25, 2010 ML1019303152010-06-0909 June 2010 Onsite Ground/Surface Water Monitoring Questionnaire for Crystal River ML1013200412010-05-12012 May 2010 Crystal River Public Meeting Attendees Sheet ML1010603282010-04-0909 April 2010 Talking Points ML1029903622010-03-0404 March 2010 6.1 Uneven Force Along Tendon ML1007504222010-03-0404 March 2010 Sgr Action Plan for Concrete Cracks ML1028709882010-01-11011 January 2010 5.4 Concrete Form Release ML1028710452010-01-0404 January 2010 6.2 Inadequate Tendon ML1028710472010-01-0101 January 2010 5.5 Exhibit 1 Permeability V w2c from Mehta ML1028710972010-01-0101 January 2010 5.5 Exhibit 2 Mix Design from Dome Repair ML1029202952009-11-27027 November 2009 Item 176 1992 Bs Event RB Temperature (4 Pages) ML1027203852009-11-0202 November 2009 Calculation S07-0033, Revision 0, NRC SIT Member Questions to Licensee (Request 43 Response Information, Attachment 2, Part 2 of 3 ML1027206552009-10-30030 October 2009 Williams Q&A - Request #24 - Q18 RFO14-IWE Exam ML1027208212009-10-30030 October 2009 Williams Q&A- Request #24 - Q18 RFO15-IWE Exam Liner UT ML1027208232009-10-30030 October 2009 Williams Q&A - Request #24 - Q18RFO15-IWE Exam Liner Containment Inspection ML1027300762009-10-30030 October 2009 WR 341602 6th-Surv.pdf ML1027201932009-10-29029 October 2009 Williams Q&A - Request #22 - Q16 Response ML1027201482009-10-29029 October 2009 Williams Q&A - Request #3 Info-Pugh-PART 7 ML1027201702009-10-29029 October 2009 Williams Q&A - Request #3 Info-Pugh-PART 8 ML1027302522009-10-29029 October 2009 Williams Q&A - Request #3 Info-Pugh-PART 4 ML1027201982009-10-28028 October 2009 Williams Q&A - Request #30 - Question 24 ML1029107252009-10-28028 October 2009 Interview Cliff Peters Gary Goetsch ML1029107542009-10-24024 October 2009 Interview Gary Goetsch ML1029107562009-10-23023 October 2009 Iwl of 10-25-09 ML1027202052009-10-22022 October 2009 NRC SIT Member Questions to Licensee (Request 42 Q36 Response Information) ML1007504152009-10-14014 October 2009 Update for 10/14/09 from Plant Issue Tracking Application ML1007502742009-10-0707 October 2009 Plant Issue Tracking, Crystal River Information for 10/7/09 ML1007504232009-10-0505 October 2009 Action Request: CR3 Sgr Hydrodemolition Exposed Cracks ML1013903992009-05-11011 May 2009 Attachment to E-mail from Paul Roberts, May 11, 2009, Questions on the Use of Carborundum Neutron Absorbing Material in the Spent Fuel Pool ML0914607852009-04-16016 April 2009 Utility Element and Generalized Future Land Use Map Received for Gary W. Maidhof, Dept Director, Dept of Development Services, Citrus County, Gov'T at April 16, 2009, Scoping Meeting in Crystal River, Fl ML1027103312009-02-0101 February 2009 Document CR-N1002-504, Revision 1, Final Report for the 30th Year Containment Iwl Inspection, Fm 6.5 Exhibit 6 ML0906404392009-01-28028 January 2009 Enclosure 5: Case Study 1: Structure of TS for Ultrasonic Flow Meters - Meeting Summary of the January 27 & 28 Meeting with Nrc/Tstf 3F0608-05, Response to Request for Additional Information Regarding Relief Requests 07-001-SS, Revision 0, Alternate Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 Areas 120 Degrees Apart .2008-06-0505 June 2008 Response to Request for Additional Information Regarding Relief Requests #07-001-SS, Revision 0, Alternate Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 Areas 120 Degrees Apart . ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0634705992006-12-14014 December 2006 Plant Service List ML0527000442005-09-21021 September 2005 Attachment 10, FAQ Log 9/21/05 ML0404104922004-02-20020 February 2004 Order EA-03-009 Service List 2021-10-18
[Table view] Category:Letter type:
MONTHYEAR3F0623-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-06-0101 June 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0423-03, 2022 Annual Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Annual Radiological Environmental Operating Report 3F0423-02, 2022 Annual Radioactive Effluent Release Report2023-04-18018 April 2023 2022 Annual Radioactive Effluent Release Report 3F0423-01, 2022 Individual Monitoring NRC Form 5 Report2023-04-0404 April 2023 2022 Individual Monitoring NRC Form 5 Report 3F0323-03, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2023-03-31031 March 2023 Decommissioning Funding Plan for Independent Spent Fuel Storage Installation 3F0323-02, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20222023-03-29029 March 2023 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2022 3F0323-01, Onsite Property Insurance Coverage2023-03-0202 March 2023 Onsite Property Insurance Coverage 3F0123-01, Proof of Financial Protection2023-01-26026 January 2023 Proof of Financial Protection 3F1222-01, Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan2022-12-12012 December 2022 Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan 3F0522-03, Notification of Revised Decommissioning Cost Estimate2022-05-26026 May 2022 Notification of Revised Decommissioning Cost Estimate 3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20222022-05-17017 May 2022 Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022 3F0422-02, 2021 Annual Radiological Environmental Operating Report2022-04-0606 April 2022 2021 Annual Radiological Environmental Operating Report 3F0322-01, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20212022-03-30030 March 2022 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2021 3F0322-03, Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1)2022-03-10010 March 2022 Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1) 3F0322-02, 2021 Individual Monitoring NRC Form 5 Report2022-03-0707 March 2022 2021 Individual Monitoring NRC Form 5 Report 3F0222-01, ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2022-02-0909 February 2022 ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb) 3F0222-02, Onsite Property Insurance Coverage2022-02-0909 February 2022 Onsite Property Insurance Coverage 3F0122-01, License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications2022-01-26026 January 2022 License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications 3F0122-02, Proof of Financial Protection2022-01-17017 January 2022 Proof of Financial Protection 3F0122-03, Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report2022-01-17017 January 2022 Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report 3F1021-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-10-21021 October 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0921-02, Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004 (Minor) (Rev. C)2021-09-29029 September 2021 Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004 (Minor) (Rev. C) 3F0921-01, to License Amendment Request, Revision 0, ISFSI Security Plan, Revision a2021-09-14014 September 2021 to License Amendment Request, Revision 0, ISFSI Security Plan, Revision a 3F0721-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-07-13013 July 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0621-02, Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004-001-IW1S2021-06-16016 June 2021 Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004-001-IW1S 3F0421-05, 2020 Individual Monitoring NRC Form 5 Report2021-04-27027 April 2021 2020 Individual Monitoring NRC Form 5 Report 3F0421-04, ADP CR3, LLC - Supplement to Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2021-04-13013 April 2021 ADP CR3, LLC - Supplement to Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization 3F0421-03, Proof of Financial Protection2021-04-0707 April 2021 Proof of Financial Protection 3F0421-01, 2020 Annual Radioactive Effluent Release Report2021-04-0606 April 2021 2020 Annual Radioactive Effluent Release Report 3F0421-02, 2020 Annual Radiological Environmental Operating Report2021-04-0606 April 2021 2020 Annual Radiological Environmental Operating Report 3F0321-07, (XEG)-DOE/NRC Forms 741 742 and 743C2021-03-30030 March 2021 (XEG)-DOE/NRC Forms 741 742 and 743C 3F0321-06, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20202021-03-29029 March 2021 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2020 3F0321-01, License Amendment Request, Revision to Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Draft a, and ISFSI Only Emergency Action Level Bases Manual2021-03-17017 March 2021 License Amendment Request, Revision to Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Draft a, and ISFSI Only Emergency Action Level Bases Manual 3F0321-02, License Amendment Request, Rev. 0, ISFSI Security Plan, Rev. a2021-03-17017 March 2021 License Amendment Request, Rev. 0, ISFSI Security Plan, Rev. a 3F0321-05, Onsite Property Insurance Coverage2021-03-15015 March 2021 Onsite Property Insurance Coverage 3F0321-03, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-03-0909 March 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0221-02, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-02-17017 February 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0221-01, ADP CR3, Llc., Crystal River Energy Complex - Environmental Protection Plan Report: 2020 Sea Turtle Rescue and Recovery Summary Report2021-02-0202 February 2021 ADP CR3, Llc., Crystal River Energy Complex - Environmental Protection Plan Report: 2020 Sea Turtle Rescue and Recovery Summary Report 3F0121-02, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2021-01-19019 January 2021 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E 3F0121-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-01-19019 January 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F1120-02, and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2020-11-19019 November 2020 and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization 3F0920-02, Request to Transfer the Quality Assurance Program Approval Form for Radioactive Material Packages2020-09-15015 September 2020 Request to Transfer the Quality Assurance Program Approval Form for Radioactive Material Packages 3F0920-01, License Transfer - Notification of Transfer Date2020-09-15015 September 2020 License Transfer - Notification of Transfer Date 3F0720-03, ISFSI Only Emergency Plan and Implementing Procedure2020-07-21021 July 2020 ISFSI Only Emergency Plan and Implementing Procedure 3F0720-02, License Transfer - Insurance Required of a Licensee Under 10 CFR 140.11(a)(4) and 10 CFR 50.54(w)2020-07-15015 July 2020 License Transfer - Insurance Required of a Licensee Under 10 CFR 140.11(a)(4) and 10 CFR 50.54(w) 3F0520-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20202020-05-18018 May 2020 Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020 3F0420-03, Supplemental Information in Support of Crystal River Unit 3 License Transfer Application - Amended License Conditions2020-04-22022 April 2020 Supplemental Information in Support of Crystal River Unit 3 License Transfer Application - Amended License Conditions 3F0420-01, 2019 Annual Radioactive Effluent Release Report2020-04-0707 April 2020 2019 Annual Radioactive Effluent Release Report 3F0420-02, 2019 Radiological Environmental Operating Report2020-04-0707 April 2020 2019 Radiological Environmental Operating Report 3F0320-04, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2020-03-19019 March 2020 Decommissioning Funding Plan for Independent Spent Fuel Storage Installation 2023-06-01
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k Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: IOCFR50.55a June 5, 2008 3F0608-05 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - Response to Request for Additional Information Regarding Relief Requests #07-001-SS, Revision 0, Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 areas 120 Degrees Apart on the Inside Surface in Accordance with 10 CFR 50.55a(a)(3)(i), TAC No.
MD7737
Reference:
Crystal River Unit 3 to NRC letter, 3F1207-04, dated December 21, 2007, "Crystal River Unit 3 - Inservice Inspection Program Plan, Ten Year Update," Accession No. ML073650362
Dear Sir:
Pursuant to 10 CFR 50.55a(a)(3)(i), Florida Power Corporation (FPC) doing business as Progress Energy Florida, Inc., Crystal River Unit 3 (CR-3) is hereby submitting the response to a Nuclear Regulatory Commission (NRC) request for additional information (RAI) received by email on May 14, 2008. This request for additional information is based on Relief Request #07-001-SS, Revision 0.
In addition, Attachment 3 is providing a revised page 7-14 of the Ten Year Inservice Inspection (ISI)
Program Plan for the Fourth Interval, as line item El.30 was discovered missing during a review subsequent to the referenced submittal.
Regulatory commitments are identified in Attachment 4.
If you have any questions regarding this submittal, please contact Dennis Herrin, Acting Supervisor, Licensing and Regulatory Programs at (352) 563-4633.
Sincerely, SteC ahilll Engineering Manager SJC/par Attachments: 1. Response to Request For Additional Information
- 2. Drawings
- 3. Revised Page 7-14 of the Ten Year ISI Inspection Program Plan
- 4. List of Regulatory Commitments xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida, Inc.
,Au47 Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT 1 Response to Request for Additional Information
U. S. Nuclear Regulatory Commission Attachment 1 3F0608-05 Page 1 of 2 Response to Request for Additional Information NRC Request (1) Relief Request #07-001-SS, Revision 0 The American Society of Mechanical Engineers (ASME) Code, Section Xl, Examination Category F-A, Item F.130 requires a 100% VT-3 visual examination of weld and mechanical connections at intermediate joints in multi-connected integral and non-integralsupports, as defined by Figure IWF-1300-1. The licensee has proposed performing an alternative VT-3 visual examination on 10% of the reactor vessel (RV) support skirt for the fourth 10-year inspection interval for CR3. The proposed approach utilizes the identical approach from previous inspection intervals. The RR (98-003-11) for the third CR3 10-year ISI interval was authorized in the Safety Evaluation Report dated August 5, 1999. Relief was requested based on the radiation conditions below the RV, which would result in significant radiation exposure to inspection and support personnel. Because there have been substantial improvements in inspection techniques since the previous inspection interval, the staff requests that the licensee address the potential for increase in visual examination of the RV skirt through the use of improved state-of-the-artinspection techniques.
FPC Response Even with the improvements in the inspection techniques since the last inspection period, there are dose and other limitations, due to the physical configuration of under vessel area, which prevent a 100% VT-3 visual inspection from being performed. The area under the reactor vessel is a high radiation area, and the Crystal River Unit 3 (CR-3) commitment to ALARA requires minimization of time spent in this area.
The outside surface of the weld is restricted from access by a welded seal plate in the refueling cavity.
This plate would have to be removed and a person would have to be lowered down between the reactor vessel and the shield wall to remove the insulation and perform the inspection of the support skirt weld. An optional access point for the inspection would be to remove the concrete plug allowing access from below. This option involves the removal of 42 cubic feet of 5000 psi concrete, which is further complicated by the fact that the plug is overhead and there is insufficient room for jackhammers to be used. Therefore, only the inside surface of the support skirt weld is reasonably accessible, which automatically limits the examination to no more than 50%.
Additionally, removing the insulation panels on the bottom of the reactor vessel is not easily performed due to the number of incore monitoring tubing interferences in the bottom head. The panels are 30 inches in length and the physical shape of each panel is such that there would be significant difficulty in maneuvering them in the cramped area without potentially impacting one or more of the thin wall incore monitoring tubing. Since any leakage in one of these thimbles would be un-isolable, any activity that could potentially cause potential leakage at this location should be avoided.
The areas inspected are reviewed each time to note any trends of degradation. Any mechanism which could damage the vessel would be evident at these three locations examined and not confined to small areas around the vessel. If the entire vessel shifted, then the damage to the bolting, support skirt or associated weld would be visible over a majority of the examination area.
It is expected that more than 10% of the inside support skirt weld is inspected during the required VT-3 visual examination, but there is no accurate method of measurement. Therefore, CR-3 cannot commit to a larger percentage of the inspection area. The area is too confined to get a measurement device in place. The last time this examination was performed was in conjunction with the bare metal visual inspection of the bottom reactor vessel head during Refuel Outage 13 in 2003.
U. S. Nuclear Regulatory Commission Attachment 1 3F0608-05 Page 2 of 2 CR-3 will perform a VT-3 examination of the reactor vessel support skirt weld, to the extent practical, when maintenance or other activities remove the insulation covering the support skirt weld. This can be performed in conjunction with the bare metal visual inspection of the bottom reactor vessel head.
The inspection is performed with a pole mounted camera and enables a long reach around the circumference of the support skirt.
In summary, Florida Power Corporation recognizes that inspection and examination techniques have improved in the last ten years, but considers the relief request as valid due to the same concerns that were the basis for the previous interval relief requests from this requirement. It is expected that shifts in the reactor vessel, due to undetected cracks in the support skirt weld, would be noted in the VT-3 examination of those areas within the inspection scope.
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT 2 Drawings
REACTOR PRESSURE VESSEL MK36 TO 81.121 IE SECTION X NDE PROGRAMI INSTRUMENTATION CR3-P-SK-lACI 2 NOZZLES N/A
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT 3 Revised Page 7-14 of the Ten Year ISI Inspection Program Plan
U. S. Nuclear Regulatory Commission Attachment 3 3F0608-05 Page 1 of 1 ISIPrograin Plan Crystal River Unit 3, Fourth Interval TABLE 7.1-1 INSERVICE INSPECTION
SUMMARY
TABLE Examination Category (with Item Description Exam Total Number of Relief Request/ Notes Examination Category Number Requirements Components TAP Number Description)
E-A El. 11 Containment Vessel Pressure Retaining Boundary General Visual Liner Plates: 26 4 Containment Surfaces Accessible Surface Areas Penetrations: 155 Attachments: 867 EL.11 Containment Vessel Pressure Retaining Boundary Visual, VT-3 7 4 Bolted Connections, Surfaces E1.12 Containment Vessel Pressure Retaining Boundary Visual, VT-3 Sump: 1 5 Wetted Surfaces of Submerged Areas Penetrations: 2 Attachments: 0 EI.30 Moisture Barriers General Visual I E-C E4.11 Containment Surface Areas -Visible Surfaces Visual, VT-l1 0 6 Containment Surfaces E4.12 Containment Surface Areas -Surface Area Grid Volumetric 0 7 Requiring Grid Line Intersections and Minimum (Thickness)
Augmented Examination Wall Thickness Locations 7-14 PENO1. G03 Revision 0
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT 4 List of Regulatory Commitments
U. S. Nuclear Regulatory Commission Attachment 4 3F0608-05 Page 1 of 1 LIST OF REGULATORY COMMITMENTS The following table lists regulatory commitments identified by Florida Power Corporation (FPC), in this document. Any other actions discussed in the submittal represent intended or planned actions by FPC.
They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Supervisor, Licensing and Regulatory Programs of any questions regarding this document.
Regulatory Commitments Due Date CR-3 will perform a VT-3 examination of the reactor vessel support skirt weld, to the 09/30/2008 extent practical, when maintenance or other activities remove the insulation covering the support skirt weld.