ML13135A492
| ML13135A492 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/15/2013 |
| From: | Mccree V Region 2 Administrator |
| To: | Hobbs T Duke Energy Corp, Florida Power Corp |
| References | |
| Download: ML13135A492 (13) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 May 15, 2013 Mr. Terry Hobbs, Plant General Manager Crystal River Nuclear Plant (NA1B) 15760 West Power Line Street Crystal River, FL 34428-6708
SUBJECT:
NUCLEAR REGULATORY COMMISSION OVERSIGHT OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
Dear Mr. Hobbs:
This letter is to inform you that the U.S. Nuclear Regulatory Commission (NRC) will conduct oversight of licensed activities at the Crystal River Unit 3 Nuclear Generating Plant in accordance with the Decommissioning Power Reactor Inspection Program described in Inspection Manual Chapter 2561. Since Florida Power Corporation certified cessation of power operations and the permanent removal of fuel from the Crystal River Unit 3 reactor vessel by letter to the NRC dated February 20, 2013, the NRC will no longer use the Reactor Oversight Process and the inspection program described in Inspection Manual Chapter 2515, Light Water Reactor Inspection Program - Operations Phase, when conducting oversight activities at Crystal River. Therefore, it is no longer necessary to report Reactor Oversight Process performance indicator data for Crystal River Unit 3 as described in Inspection Manual Chapter 0608, Performance Indicator Program. Although the inspection program for NRC oversight at your facility will change substantially, all license commitments remain in effect until altered by formal action from the NRC.
When Florida Power Corporation certified permanent cessation of power operations to the NRC, it had not yet fully staffed a decommissioning organization and had not formulated a schedule of decommissioning activities. Therefore, the NRC was not able to immediately formulate plans to fully implement the decommissioning inspection program. In order to allow for a reasonable transition from the Reactor Oversight Process to the Decommissioning Power Reactor Inspection Program, NRC Region II will conduct inspections in accordance with the attached inspection plan. NRC Region I will take responsibility for oversight of Crystal River in the near future and will develop a comprehensive inspection plan which will replace the attached transition plan and fully implement Inspection Manual Chapter 2561.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs document system (ADAMS). Adams is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
T. Hobbs 2 Please contact Dan Rich at (404) 997-4721 with any questions you may have regarding this letter.
Sincerely,
/RA/
Victor M. McCree Regional Administrator Docket No. 50-302 License No. DPR-72
Enclosure:
Crystal River Interim Master Inspection Plan cc w/encl: (See page 3)
_________________________ X SUNSI REVIEW COMPLETE XFORM 665 ATTACHED OFFICE RII:DRP RII:DRP NRR:DIRS NSIR:DSO NSIR:DPR RII:DRP RII:DRP SIGNATURE DWR:/RA/ RPC: /RA/ Via email Via email Via email LXW:/RA/ VMM:/RA/
NAME *DRich *RCroteau *HNieh *PHolahan *MThaggard LWert VMcCree DATE 5/8/2013 5/13/2013 5/2/2013 5/10/2013 5/13/2013 5/13/2013 5/14/2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO T. Hobbs 3 cc w/encl:
Lara S. Nichols Daniel R. Westcott Deputy General Counsel Supervisor Duke Energy Corporation Licensing & Regulatory Programs Electronic Mail Distribution Crystal River Nuclear Plant (NA1B)
Electronic Mail Distribution M. Christopher Nolan Director - Regulatory Affairs Joseph W. Donahue General Office Vice President Duke Energy Corporation Nuclear Oversight Electronic Mail Distribution Progress Energy Electronic Mail Distribution Regis T. Repko Senior Vice President David T. Conley Duke Energy Corporation Senior Counsel Electronic Mail Distribution Legal Department Progress Energy Richard A. Wiemann Electronic Mail Distribution Superintendent, Nuclear Oversight Crystal River Nuclear Plant Mark Rigsby Electronic Mail Distribution Manager, Support Services - Nuclear Crystal River Nuclear Plant (NA2C)
Brian C. McCabe Electronic Mail Distribution Manager, Nuclear Oversight Shearon Harris Nuclear Power Plant Senior Resident Inspector Progress Energy U.S. Nuclear Regulatory Commission Electronic Mail Distribution Crystal River Nuclear Generating Plant 6745 N Tallahassee Rd Blair P. Wunderly Crystal River, FL 34428 Director - Engineering Nuclear Crystal River Nuclear Plant (NA2C) Attorney General Electronic Mail Distribution Department of Legal Affairs The Capitol PL-01 R. Alexander Glenn Tallahassee, FL 32399-1050 General Counsel Progress Energy Bryan Koon Electronic Mail Distribution Director Florida Division of Emergency Management Donna B. Alexander Electronic Mail Distribution Manager, Nuclear Regulatory Affairs (interim)
Progress Energy Chairman Electronic Mail Distribution Board of County Commissioners Citrus County Cynthia Becker 110 N. Apopka Avenue (Acting) Chief Inverness, FL 36250 Florida Bureau of Radiation Control Department of Health Electronic Mail Distribution
T. Hobbs 4 Letter to Terry Hobbs from Victor M. McCree dated May 15, 2013.
SUBJECT:
NUCLEAR REGULATORY COMMISSION OVERSIGHT OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT Distribution w/encl:
C. Evans, RII EICS L. Douglas, RII EICS B. Watson, FSME/DWMEP/DURLD/RD M. Ferdas, RI DNMS/DB OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMCrystal River Resource
INTERIM MASTER INSPECTION PLAN Plant: Crystal River Unit 3 Inspection Dates: Inspection under this plan will begin on approval and will continue until administration of the decommissioning inspection program for Crystal River has been transitioned from Region II to Region I.
Documentation: Inspection results will be documented in quarterly integrated inspection reports using the guidance provided by Inspection Manual Chapter 0612, Power Reactor Inspection Reports.
Division of Reactor Safety (DRS) team inspection results may be documented in separate reports.
Inspection Procedures: DRP Inspection Procedures 71111.01 Adverse Weather Protection 71111.04 Equipment Alignment 71111.05 Fire Protection 71111.12 Maintenance Effectiveness 71111.18 Plant Modifications 71111.20 Refueling and Other Outage Activities 71152 Problem Identification and Resolution (PI&R) 71153 Event Follow-up & Notices of Enforcement Discretion 71130.11 Material Control & Accounting (MC&A)
IMC 2515 Plant Status (App. D)
DRS Inspection Procedures 71111.11 Biennial Licensed Operator Requalification 71114 Reactor Safety Emergency Preparedness baseline inspections (entire series) 71124 Radiation SafetyPublic and Occupational baseline Inspections (entire series) 71130 Security baseline inspections Inspectors: Qualified inspectors Licensee
Contact:
Dennis Herrin, Lead Engineer, Licensing 352-563-4633 Inspection Objectives:
- 1. To verify that the licensees activities during the transition to decommissioning are adequate and in conformance with requirements in the facility license, licensing commitments, and regulations.
- 2. To identify declining trends in performance and perform inspections to verify that the licensee has resolved issue(s) before performance declines below an acceptable level.
Enclosure
2
- 3. Verify that activities during the transition to decommissioning maintain adequate radiation protection, security, emergency preparedness, and spent fuel protection controls.
Resource Estimate & T&A: Hours of direct inspection effort will not exceed fiscal year 2013 budget. Inspectors should charge direct baseline inspection effort to the appropriate inspection procedure using task code BI. Time spent preparing for the inspection and entrance meeting is charged to task code BIP and time spent for the exit meeting and all documentation is charged to task code BID. DRS team inspections may require the use of different task codes.
Background:
Crystal River Unit 3 shut down in September of 2009 for a planned steam generator replacement outage. While creating the steam generator opening, workers discovered an unexpected crack in the containment concrete wall. In 2011, after repairing the initial damage and while returning the containment structure to service, additional cracking occurred in other sections of the containment concrete wall. The unit remained shut down, with the reactor core fully off-loaded to the spent fuel pool, while the licensee evaluated whether to repair or retire the unit.
On February 5, 2013, Progress Energy (a subsidiary of Duke Energy) publically announced their intention to retire Crystal River Unit 3 and proceed with decommissioning. The NRC has been conducting ROP baseline inspections at the site in accordance with Inspection Manual Chapter (IMC) 0351, Implementation of the Reactor Oversight Process at Reactor Facilities in an Extended Shutdown Condition for Reasons Other Than Significant Performance Problems.
The latest revision to the inspection plan was approved on January 18, 2013, and is electronically available from the Publicly Available Record (PARS) component of the NRCs document system (ADAMS) under ML13016A115.
On February 20, 2013, Progress Energy certified to the NRC the permanent removal of fuel from the Crystal River Unit 3 reactor vessel. According to IMC 2561, Decommissioning Power Reactor Inspection Program, the decommissioning inspection program is to be implemented following the certification date for the removal of all fuel from the reactor vessel. In order to allow for transition from the Reactor Oversight Process to the Decommissioning Power Reactor Inspection Program, oversight of licensed activities at Crystal River will be accomplished using the IMC 2515 baseline inspection procedures whose inspection objectives are aligned with the core decommissioning inspection procedures specified in IMC 2561. The inspections identified in this plan ensure that activities performed by the licensee are inspected as intended in IMC 2561 and the associated decommissioning core inspection procedures.
Enclosure
3 I. DRP INSPECTION ACTIVITIES The following inspection procedures (IP) will be completed as specified below. The associated decommissioning core inspection procedures should be utilized as additional guidance when planning inspections. Inspection scope and sample selection should be focused on those structures, systems, and components (SSCs) required to maintain the safety of spent fuel and minimize the spread of contamination.
IMC 2515 IMC 2561 Inspection scope Procedures Procedures 71111.01 Conduct one annual review of the sites hurricane 71714 Adverse season preparations prior to the onset of hurricane Cold Weather Weather season. Normally completed 2nd quarter. Preparations Protection Inspector may conduct review(s) of readiness for impending adverse weather conditions (e.g., tornado, high winds, etc.) if an inspector is onsite prior to onset of imminent adverse weather conditions.
Conduct one annual review of the sites readiness for seasonal extreme weather conditions (typically cold weather readiness completed during the 4th or 1st quarters).
71111.04 Perform one annual complete alignment review of 71801 Equipment spent fuel pool (SFP) system or a SFP support Decommissioning Alignment system. Performance and Status Review at PSRs 71111.05 Walk down at least one plant fire area important to 71801 Fire SFP pool safety (per quarter). Decommissioning Protection Performance and Status Review at PSRs 71111.12 Perform one annual maintenance effectiveness 62801 Maintenance review on those structures, systems and components Maintenance and Effectiveness important to spent fuel safety. The review should Surveillance at included in-service test results and system heat PSRs exchanger performance to verify that maintenance has been effective in maintaining the availability and capability of those systems required to remove decay heat from spent fuel.
Enclosure
4 IMC 2515 IMC 2561 Inspection scope Procedures Procedures 71111.18 Review modifications (no minimum specified - as 37801 Plant samples become available). Note: Availability of Safety Reviews, Modifications samples may be limited during the transition period. Design Changes, and Modifications Containment detensioning and stabilization activities at PSRs may be reviewed under this IP since these activities will be implemented via the 10CFR50.59 process.
71111.20 Verify SFP FME controls and SFP protection ( no 60801 Refueling and minimum number of samples required - performed Spent Fuel Pool Other Outage while on-site) Safety at PSRs Activities 71152 Perform routine corrective action program (CAP) 40801 Problem review activities, as applicable, while on-site (no Self-Assessment, Identification minimum number of samples required). Auditing, and and Corrective Action Resolution Note: The annual operator work-around review is not at PSRs applicable with the core fully off-loaded to the spent fuel pool.
71153 Complete as specified by IP (no minimum number of N/A Event Follow- samples required).
up and Notices of Enforcement Discretion 71130.11 Conduct triennial review of Material Control & N/A Material Accounting.
Control and Accounting Last completed 3rd Qtr 2010 (IR 05000302/2010403)
(MC&A)
IMC 2515, Conduct plant status inspection activities, as 71801 App D applicable, focusing on SSCs necessary for the safe Decommissioning Plant Status storage of spent fuel including security, radiation Performance and protection, and emergency preparedness areas. Status Review at PSRs Periodically discuss with licensee representatives the status of decommissioning activities, problems encountered, and performance insights.
Enclosure
5 II. DRS INSPECTION ACTIVITIES The following team inspections will be completed during the transition period (inspection dates TBD):
IP Number Title Comments 71111.11 Biennial Licensed Operator Inspection in this area will Requalification focus heavily on fuel handling activities associated with spent fuel and associated support systems.
71114 Reactor Safety Emergency Adjust schedule and scope Preparedness baseline inspections based on licensees schedule (including all attachments) of decommissioning activities and current licensing basis.
IPs 82301, 82302, and 82701 may be used as additional guidance for these inspections during the transition period.
71124 Radiation SafetyPublic and Adjust schedule and scope Occupational baseline inspections based on licensees schedule (including all attachments) of decommissioning activities.
IMC 2561 decommissioning IPs 83750, 84750, 86750 may be used as additional guidance for these inspections during the transition period.
71130 Security baseline inspections Adjust schedule and scope based on licensees schedule of decommissioning activities and current licensing basis.
INSPECTIONS NOT COMPLETED DURING TRANSITION
- a. The following DRP inspections will not be completed during the transition period:
IP Number Title Comments 71111.06 Flood Protection Measures This inspection focuses on internal flooding which could cause initiating events or cause loss of safe-shutdown equipment. Not applicable for site already in safe-shutdown condition.
Enclosure
6 IP Number Title Comments 71111.07 Heat Sink Performance (annual review) Inspections performed in Section I of this attachment are sufficient to monitor performance issues of heat exchangers important to SFP safety.
71111.11 Licensed Operator Requalification Operator requalification Training & Control Room Observations training program is no longer (Quarterly and Annual Review by applicable. Operators will Residents) ultimately be trained as non-licensed certified fuel handlers for decommissioning. Control Room observations are not applicable due to lack of periods of heightened activity in the control room.
71111.13 Maintenance Risk Assessment & IP is not applicable with all Emergent Work Control fuel off-loaded to the SFP.
71111.15 Operability Determination and Inspections performed in Functionality Assessments Section I of this attachment are sufficient to review degraded equipment issues at the site.
71111.19 Post Maintenance Testing Inspections performed under Section I of this attachment are sufficient to monitor licensee performance in this area.
71111.22 Surveillance Testing Inspections performed under Section I of this attachment are sufficient to monitor licensee performance in this area.
71114.06 Drill Evaluation (resident portion) Inspections performed under Section II of this attachment are sufficient to monitor licensee performance in this area.
71151 Performance Indicator Verification IP is not applicable for a permanently shut down plant Enclosure
7 IP Number Title Comments 71152 PI&R (Biennial) Inspections performed under Sections I and II of this attachment are sufficient to monitor licensee performance in this area.
- b. The following DRS inspections will not be completed during the transition period:
IP Number Title Comments 71111.05 Fire Protection Inspection (Triennial) Inspections performed under Section I of this attachment are sufficient to monitor licensee performance issues.
71111.07 Heat Sink Performance (Biennial) Inspections performed under Sections I of this attachment are sufficient to monitor licensee performance issues.
71111.08 In-service Inspection Activities Inspections performed under (Biennial) Sections I of this attachment are sufficient to monitor licensee performance issues.
71111.17 Evaluations of Changes, Tests and Inspections performed under Experiments and Permanent Plant Section I of this attachment Modifications are sufficient to monitor licensee performance in this area.
71111.21 Component Design Basis Inspection Inspections performed under (Triennial) Sections I of this attachment are sufficient to monitor licensee performance issues.
- c. The following IMC 2561 inspection procedures are not referenced by this interim inspection plan during the transition period:
IP Number Title Comments 36801 Organization, Management, and Cost It is not anticipated that the Controls at Permanently Shutdown site will be at a point in the Reactors (PSRs) decommissioning process where this inspection would be applicable Enclosure
8 IP Number Title Comments 81XXX Physical Security Assessment at PSRs Revisions to this series of inspection procedures are being evaluated. The 71130 series of security baseline inspection procedures are sufficient to verify adequate licensee performance in this area.
83801 Inspection of Final Surveys at PSRs The site will not be at a point in the decommissioning process where this inspection would be applicable Enclosure