IR 05000334/2013001

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ROP-14 2013 Beaver Valley Power Station Units 1 and 2, Annual Assessment Letter, Report 05000334/2013001 and 05000412/2013001, and Inspection Plan
ML14062A090
Person / Time
Site: Beaver Valley
Issue date: 03/04/2014
From: Michael Scott
Division Reactor Projects I
To: Emily Larson
FirstEnergy Nuclear Operating Co
MANGAN, KA
References
IR-13-001
Download: ML14062A090 (6)


Text

March 4, 2014

SUBJECT:

ANNUAL ASSESSMENT LETTER FOR BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (REPORT 05000334/2013001 AND 05000412/2013001)

Dear Mr. Larson:

On February 12, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Beaver Valley Power Station, Unit Nos. 1 and 2. The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from January 1, 2013 through December 31, 2013. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.

The NRC determined that overall, Beaver Valley Power Station, Unit Nos. 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. Beaver Valley Power Station, Unit Nos. 1 and 2 were in the Regulatory Response Column of the NRCs Reactor Oversight Process Action Matrix until the third quarter of 2013, due to one or more greater-than-green security cornerstone inputs as described in inspection report 05000334/2012404 and 05000412/2012404 dated August 16, 2012 (ML12229A425)1. The NRC determined that Beaver Valley Power Station, Unit Nos. 1 and 2 returned to the Licensee Response Column in the third quarter of 2013 because a supplemental inspection was successfully completed for the greater-than-green security inputs on May 31, 2013, as documented in supplemental inspection report 05000334/2013406 and 05000412/2013406, dated July 8, 2013 (ML13190A417). Subsequently, Beaver Valley Power Station, Unit Nos. 1 and 2 remained in the Licensee Response Column because all inspection findings had very low (i.e., Green) safety significance and all performance indicators demonstrated that your performance was within the nominal, expected range (i.e., Green). Therefore, the NRC plans to conduct Reactor Oversight Process baseline inspections at your facility.

1 The NRCs Agencywide Document Access and Management System (ADAMS) accession number for the referenced document. The report cover letter summarizing the inspection results is publicly available and retrievable through the ADAMS hyperlink provided at the end of this letter using this number. The referenced inspection report contains Security-Related information in accordance with 10 CFR 2.390(d)(1) and is not publicly available. As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in calendar year (CY) 2014 will reflect this revision to Inspection Manual Chapter (IMC) 0310. The CY 2013 end-of-cycle assessments were conducted using the IMC 0310 guidance in effect in CY 2013 (dated October 28, 2011). Cross-cutting aspects identified in 2013 using the 2013 terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305.

The enclosed inspection plan lists the inspections scheduled through June 30, 2015. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the mid-cycle performance review. In addition to baseline inspections, the NRC will perform Inspection Procedure (IP) 60854.1, Preoperational Testing of ISFSI at Operating Plants, IP 60855.1, Operation of an ISFSI at Operating Plant, IP 60856.1, Review of 10 CFR 72.212 Evaluation at Operating Plants, and IP 71003, Post-Approval Site Inspection for License Renewal. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.

This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.

Additionally, an NRC audit of licensee efforts towards compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events is ongoing. This audit includes an onsite component in order for the NRC to evaluate mitigating strategies as described in licensee submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The date for the onsite component at your site is being coordinated with your staff. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Document Access and Management System (ADAMS).

ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact Kevin Mangan at (610)337-5234 with any questions you have regarding this letter.

Sincerely,

/RA/

Michael L. Scott, Acting Director Division of Reactor Projects

Docket Nos.: 50-334, 50-412 License Nos.: DPR-66, NPF-73

Enclosure: Inspection Plan

cc w/encl: Distribution via ListServ

ML14062A090

SUNSI Review

Non-Sensitive Sensitive

Publicly Available Non-Publicly Available

OFFICE RI/DRP RI/DRP RI/DRP

NAME mmt LCline/ AD for KMangan/ AD for MScott/ MLS

DATE 02/26 /14 02/26/14 03/03//14

Page 1 of 2 02/28/2014 13:02:48 Report 22 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Beaver Valley Inspection / Activity Plan 01/01/2014 - 06/30/2015 71152

- PIR SAMPLE: PART 21 AND VENDOR BULLETIN

1, 2 IP Problem Identification and Resolution 71152 01/21/2014 01/24/2014 7/7EXAM

- BV1 INITIAL OL EXAM

1 FY14 -BEAVER VALLEY 1 INITIAL OPERATOR LICENSING EXAM U01884 06/09/2014 06/13/2014

FY14 -BEAVER VALLEY 1 INITIAL OPERATOR LICENSING EXAM U01884 07/07/2014 07/16/2014 71124

- OCC RADIATION SAFETY

1, 2 IP Radiological Hazard Assessment and Exposure Controls 71124.01 03/03/2014 03/07/2014 1, 2 IP Occupational ALARA Planning and Controls 71124.02 03/03/2014 03/07/2014 71124

- OCC RADIATION SAFETY

1, 2 IP Radiological Hazard Assessment and Exposure Controls 71124.01 04/21/2014 04/25/2014 1, 2 IP Occupational ALARA Planning and Controls 71124.02 04/21/2014 04/25/2014 1, 2 IP In-Plant Airborne Radioactivity Control and Mitigation 71124.03 04/21/2014 04/25/2014 1, 2 IP Occupational Dose Assessment 71124.04 04/21/2014 04/25/2014 1, 2 IP Performance Indicator Verification 71151 04/21/2014 04/25/2014 EP EXER

- EP EXERCISE INSPECTION

1, 2 IP Exercise Evaluation - Hostile Action (HA) Event 7111407 06/16/2014 06/20/2014 7111108P

- U2 INSERVICE INSPECTION

2 IP Inservice Inspection Activities - PWR 7111108P 04/28/2014 05/09/2014 ISFSI

- ISFSI CRANE AND HSM INSPECTION

1 IP On-Site Fabrication Of Components And Construction On An ISFSI 60853 05/12/2014 05/15/2014 71124

- OCC RADIATION SAFETY

1, 2 IP Radiation Monitoring Instrumentation 71124.05 06/09/2014 06/13/2014 7111111B

- BV1 REQUAL INSPECTION WITH P/F RESULTS

1 IP Licensed Operator Requalification Program 7111111B 08/04/2014 08/08/2014 ISFSI

- DRY RUN & INITIAL ISFSI INSPECTION

1, 2 IP Preoperational Testing Of An ISFSI 60854 09/01/2014 09/19/2014

IP Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants 60854.1 09/01/2014 09/19/2014 1, 2 IP Operation Of An ISFSI 60855 09/01/2014 09/19/2014 1, 2 IP Review of 10 CFR 72.212(b) Evaluations 60856 09/01/2014 09/19/2014

IP Review of 10 CFR 72.212(b) Evaluations at Operating Plants 60856.1 09/01/2014 09/19/2014

IP Operation of an Independent Spent Fuel Storage Installation at Operating Plants 60855.1 09/22/2014 09/26/2014 CDBI

- CDBI

1, 2 IP Component Design Bases Inspection 7111121 11/03/2014 11/07/2014 1, 2 IP Component Design Bases Inspection 7111121 11/17/2014 11/21/2014 This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures.

Page 2 of 2 02/28/2014 13:02:48 Report 22 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Beaver Valley Inspection / Activity Plan 01/01/2014 - 06/30/2015 CDBI

- CDBI

1, 2 IP Component Design Bases Inspection 7111121 12/01/2014 12/05/2014 71124.08

- RADWASTE

1, 2 IP Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124.08 11/17/2014 11/21/2014 71124

- OCC RADIATION SAFETY

1, 2 IP Radioactive Gaseous and Liquid Effluent Treatment 71124.06 12/15/2014 12/19/2014 1, 2 IP Performance Indicator Verification 71151 12/15/2014 12/19/2014 71003

- LR COMMITMENTS PHASE I OUTAGE INSP

1 IP Post-Approval Site Inspection for License Renewal 71003 04/13/2015 04/17/2015 7111108P

- U1 INSERVICE INSPECTION

1 IP Inservice Inspection Activities - PWR 7111108P 04/13/2015 04/24/2015 71124

- RAD SAFETY INSPECTION

1, 2 IP Radiological Hazard Assessment and Exposure Controls 71124.01 04/20/2015 04/24/2015 1, 2 IP Occupational ALARA Planning and Controls 71124.02 04/20/2015 04/24/2015 1, 2 IP In-Plant Airborne Radioactivity Control and Mitigation 71124.03 04/20/2015 04/24/2015 1, 2 IP Occupational Dose Assessment 71124.04 04/20/2015 04/24/2015 This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures.