ML14065A253

Summary of Category 1 Public Meeting with Omaha Public Power District to Discuss Status of Oversight Activities at Fort Calhoun Station

ML14065A253
Person / Time
Site:	Fort Calhoun
Issue date:	03/05/2014
From:	NRC Region 4
To:
Hay M
References
Download: ML14065A253 (11)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD.

ARLINGTON, TX 76011-4511 March 5, 2014 LICENSEE: Omaha Public Power District (OPPD)

FACILITY: Fort Calhoun Station

SUMMARY

OF FEBRUARY 27, 2014 MEETING WITH OMAHA PUBLIC POWER DISTRICT On February 27, 2014 a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD) in Blair, Nebraska.

The NRC presented the status of oversight activities at Fort Calhoun Station (Enclosure 1).

OPPD presented their actions for continued performance improvement following the plant restart in December 2013 (Enclosure 2). The slides from the presentations are available electronically from the NRCs Agency wide Documents Access and Management System (ADAMS) and are enclosed in this notice.

A video of the public meeting will be posted on the website devoted to the special oversight at Fort Calhoun Station, available at:

http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of ADAMS. ADAMS is accessible from the Public Electronic Reading Room page of the NRCs public web site at:

http://www.nrc.gov/readingrm/adams.html.

To receive a summary of future meetings and other plant-specific e-mail distributions, you must subscribe to the Operating Reactor Correspondence electronic distribution for this plant via:

http://www.nrc.gov/public-involve/listserver/plants-by-region.html Once subscribed, if you wish to discontinue receiving electronic distribution, you may unsubscribe at any time by visiting the same web address above.

CONTACT: Michael Hay, RIV/DRP (817) 200-1147 Docket No.: 50-285 : NRC Presentation Slides : OPPD Presentation Slides

Introductions

Fort Calhoun Station Public Meeting

• Welcome Nuclear Regulatory Commission

• Introduction of NRC personnel February 27, 2014 Blair, Nebraska 1 2 Purpose of Meeting Opening Remarks

• NRC will present status of regulatory activities associated with the Fort Calhoun Station Marc Dapas - Regional Administrator

• OPPD will present details of Fort Calhoun Station performance improvement initiatives

• Public comments and questions 4

1

NRC Actions Completed NRC Actions Completed

• NRC determined plant safe for restart and closed Confirmatory Action Letter December NRC completed inspection, assessment, and 17, 2013 licensing activities associated with the Confirmatory Action Letter Restart Checklist

• NRC issued PostRestart Confirmatory Action Letter December 17, 2013 5 6 PostRestart CAL PostRestart CAL PostRestart commitments consist of:

OPPD committed to the NRC to continue implementing improvement initiatives in key - Key areas for sustained performance improvement areas and address specific technical items - Long term flood recovery items

- High energy line break corrective actions associated with the Auxiliary Steam System

- Containment internal structure corrective actions to restore design margins 7 8 2

NRC Assessment Activities In Summary

• Routine inspections

• Increased NRC oversight activities remain

- Resident Inspectors

- Regional inspections

• Team inspection (Summer 2014)

• NRC continues to implement independent and

- Assess Corrective Action Process effectiveness thorough inspection activities to assess station

- Assess PostRestart Confirmatory Action Letter performance improvement progress items 9 10 OPPD Presentation Contacting the NRC

• Report an emergency

- (301) 8165100 (call collect)

• Report a safety concern

- (800) 6957403

- Allegation@nrc.gov

• General information or questions

- www.nrc.gov 11 12 3

Topics for Discussion OPPDs Fort Calhoun Station

• Safety Culture Driving To Excellence

• Problem Identification and Resolution

• Design and Licensing Basis Control and Use Public meeting with the U.S. Nuclear Regulatory Commission

• Site Operational Focus

• Programs - Engineering Focus Areas

- Flooding Recovery Action Plans

- Beyond Design Basis Flood Mitigation

- Fukushima Response Project

- Tornado-Borne Missiles

- High-Energy Line Break

- 10 CFR 50.59

- Containment Internal Structures

• Nuclear Oversight February 27, 2014

• Integration into the Exelon Nuclear Fleet 1 2 Safety Culture What People Are Saying

• Safety Culture Monitoring and Improvements Continue

- Initial and continuing Safety Culture/SCWE Thinking back over the past six months, Better Better 70%

training for leaders and site personnel Same Same 28%

is Safety Conscious Work Environment

- Continue to utilize the 2Cs meetings (compliments and concerns) (SCWE) at FCS Worse Worse 2%

- Implemented a Site Employee Issues Advisory Committee

- Continue our monthly Safety Culture Pulse Better Better 77%

Survey Thinking back over the past six months, Same Same 23%

- Weekly leadership and station alignment is nuclear safety culture at FCS meetings to discuss survey results Worse Worse 1%

- OPPD can determine both station safety culture trends and department level trends for departments of ten people or larger 3 4 1

Problem Identification and Resolution Problem Identification and Resolution

• Corrective Action Program (CAP) changes implemented to

• Observations improve OPPDs detection and correction of plant issues - Areas that have shown improvement in last quarter Open corrective actions (Oct: 3,229 / Current: 2,124)

- Streamlined CAP procedures and guidance Open report evaluations (Oct: 617 / Current: 410)

Established expectations - managers, supervisors and staff trained Open correction action prevent recurrences (CAPRs) (Oct:

Accountability reinforced 33 / Current: 25)

- Added staff - CAP Coordinators (CAPCOs) RCA/ACA Rejection Rates (1st Two Quarters: 47% / Last Two Quarter: 24%)

- Implemented detailed Exelon Nuclear performance monitoring tools

- Conducted oral board interviews to assess & reinforce understanding - Areas where we are still being challenged Number of overdue CAP items

• Results RCA / ACA timeliness

- Station has seen a reduction in the number of open Corrective - Actions addressing challenges Actions and Causal Analyses over the last quarter Common Factors Analysis required for department with five or more overdue CAP items

- CAP performance indicators are showing improvements due to Increased Management Oversight of open Causal Analysis.

better alignment of the Senior Leadership Team (SLT) Developed Engineering recovery plan to reduce analysis

- Through performance data trending, the station has identified volume and increase qualified analysts needed improvements in Causal Analysis quality

• Problem Identification and Resolution Inspection scheduled for the weeks of June 23 and July 14, 2014 5 6 Design and Licensing Basis Design and Licensing Basis Control and Use Control and Use

• OPPDs post restart commitment states that:

• January 2014: Commenced review of key calculation

- Pre-restart 93 calculations were reviewed with 45 revisions for administrative corrections

- After restart, OPPD will complete a significant effort to perform a risk-

- 78 of 351 key calculations were reviewed with 33 revisions required for administrative focused reconstitution of the: corrections Design basis,

• February 7, 2014 - Issue project request for proposal to vendors (COMPLETE)

Licensing basis, and

• March 28, 2014 - Vendor proposals due Updated Safety Analysis Report

• April 30, 2014 - Award project contract

• As part of this project, OPPD will:

• May 5, 2014 - Commence pilot project Ensure proper classification of equipment,

• August 1, 2014 - Complete project status assessment Convert to a safety-related Q List approach for equipment

• December 31, 2014 - Complete pilot project (NRC commitment) classification, and

• February 1, 2015 - Complete project status assessment Complete a key calculation review

• February 28, 2015 - Implement lessons learned from pilot project

- A pilot program will be completed during 2014 on a selected system to

• March 1, 2015 - Commence remainder of project check and adjust the process, scheduling and resource allocation

• December 31, 2018 - Complete reconstitution project (NRC commitment)

- Complete the reconstitution project before the end of 4th quarter 2018

• Approximately every six months between March 1, 2015 and December 31, 2018 - Complete project status assessments 7 7 8 8 2

Site Operational Focus Site Operational Focus

• Site Operational Focus combines the awareness of

• Elements of Operational Focus include:

plant and equipment performance, knowledge of the (continued) plant design and licensing basis, with qualified - Actual and potential issues screened using personnel and procedures supporting sustained formal systematic decision-making process operations

- CAP used to support trending, investigations

• Elements of Operational Focus include: and causal analysis

- Shift Managers leads the station's Plan of the - Operator rounds and monitoring plans to trend Day providing oversight and setting the priorities performance for the station

- Plant Health Committee reviews equipment

- Daily activities are assessed for impact to the status against expected performance station based on risk

- Exelon Fleet provides a suite of Performance

- Risk assessment includes ensuring activities are Indicators resource-loaded (compatible work bundled, parts

- Fleet resources available for support needed procured and personnel support) 9 10 Site Operational Focus Site Operational Focus

• Traveling screen sluice gate shaft was found damaged by

• Fort Calhoun has resumed safe operations Operations personnel.

Commenced Breakers Reactor Reactor Heatup Closed Critical Critical

• The shaft was bent by moving the gate with heavy ice Nov. 24, 2013 Dec. 21, 2013 Jan. 12, 2014 Jan. 13, 2014

@1432 @2100 @0308 @0136 buildup, caused by a leak above from a backwash pipe

• Root Cause from CAP analysis Reactor Reactor Manual Breakers - Motor torque settings allowed the stem to be bent Critical Shutdown Reactor Closed Dec. 18, 2013 (CW-14C) Shutdown Jan. 13, 2014

@1848 Jan. 9, 2014 (CEA-41) @1411

• Corrective Actions

@0900 Jan. 12, 2014

@0323 - The stem has been replaced

1. Heat-up performed to support testing and equipment verifications - Motor torque settings were verified and reset

- The pipe leak is being repaired

2. Reactor startup only after conditions confirmed and commitments met

3. Unit returned to service

4. Forced outage to repair river sluice gate

5. Control rod issue identified during unit startup; unit shut down to support repairs

6. Reactor restarted after repairs made and returned to service 11 12 3

Site Operational Focus Flooding Recovery Action Plans

• Organizational Changes:

Enhanced operator rounds to monitor for ice on

• Flooding Recovery Post-Restart Action Plan status gates beneath catwalk over the river - There are five Flooding Recovery Post-Restart Action commitments outlined in section 2 of the Confirmatory Action Letter (CAL)

Inspect other motor actuator torque settings - Three Flooding Recovery Post-Restart Action commitments have been submitted to the NRC resident inspectors GATES at INTAKE STRUCTURE - Two Flooding Recovery Post-Restart Action commitments are on-going File photo of Gates 13 14 Beyond Design Basis Flood Mitigation Fukushima Response Project

• Interim action currently in place

• Project scope

• New portable system - Flooding reevaluation and seismic evaluation

• Mitigates effects of floods above 1,014 elevation Portable Submersible - Flooding and seismic walkdowns

• Designed and tested for beyond design basis Pumps Results submitted to the NRC conditions Actions ongoing

• NRC approved license amendment for minimum - Mitigating strategies for beyond design basis external events river level Portable Skids for Water Portable Diesel - Strategy developed and submitted to NRC Generators Portable equipment pre-staged at FCS and Power Distribution Procedures (Admin/Operations/PM/Testing)

Staffing Communications (internal and external)

- Spent Fuel Pool Instrumentation (SFPI)

SFPI modifications submitted to the NRC 15 16 4

Tornado-Borne Missiles High-Energy Line Break

• Protection of key equipment from potential tornado-borne missiles

• High-Energy Line Break (HELB) Piping Changes

- Established a clear licensing basis

• Used 250 tons of steel - Reassessed all high-energy systems

- Revised over 30 design documents

• Completed 37 modifications - Completed over 30 hardware changes

- Post-Restart Action commitments outlined in section 3 of the CAL Redundancy to Improved Piping Supports HELB Flood Barriers Mitigate HELBs 17 18 10 CFR 50.59 Containment Internal Structures

• Summary of actions taken regarding 10 CFR 50.59:

- Reduced population of individuals qualified to perform Section 50.59

• OPPD committed to:

Screens and Evaluations - Evaluate the structural design margin for the containment internal structure,

- Provided vendor training for the reduced population of qualified individuals. and reactor cavity and compartments, and resolve any deficiencies in This training was specifically developed for FCS by utilizing examples of accordance with FCSs CAP station products. A custom exam was also created. The training has two - Regarding Beams 22A and Beam 22B under Safety Injection Tanks 6B/D, purposes: resolve any deficiencies in accordance with the CAP

1. Develop subject matter experts and alternates for Section 50.59, which

• Significant effort and resources utilized to analyze the containment internal will be able to give the initial and requalification training.

structure and develop resolution strategies.

2. Increase the level of knowledge of individuals that will be mentoring our

• Resolution Strategy less-experienced engineers in Section 50.59 screens and evaluations

- Implemented the Engineering Assurance Group (EAG). All Screens and - Reactor Vessel Head stand Evaluations are required to be reviewed by EAG prior to issuance - Replace current existing pedestal supports with deep beams that span

- Completed focused briefings on specific deficiencies seen through EAG the floor to take the load to adjacent walls and columns reviews

- Implementing Exelons Quality Review Team, which will review Section 50.59 products as part of the review scope 19 20 5

Nuclear Oversight The Exelon Nuclear Management Model Independent Assessment

• Transition in five phases

- Framework development Organization, Procedures, Performance Indicators, Information Technology

• Plant Startup - Analysis Gap analysis of 27 functional areas

- Design

• Post-Restart Recommendations to address key gaps

- Implementation planning Schedule development to include change management

- Implementation - Majority of activities due for completion in 2015 completed over 2000 activities as of today Approved by OPPD and Exelon executives 21 22 The Exelon Nuclear Management Model What it Took - So Far

• Check and adjust approach using weekly status meetings

• 8,000,000 person-hours and workload look-aheads to maintain schedule adherence

• 69,000 task completions

- Review progress

• 20-year operating

- Defined process for any schedule changes agreement with Exelon

• Monthly Executive Status Meetings

• More than 450 restart

• Fleet - Corporate Functional Area Manager Peer Support checklist items closed

• Independent oversight

• Industry-leading

- NSRB - Station visits with report outs to the OPPD board measurement of safety culture 23 24 6

What it Took - The Details What it Took - The Details

• Tasks complete: 69,032

• CAP items assigned: 51,726

• Person-hours worked: 8,027,621

• Root Cause Analyses (RCAs) assigned: 77

- Work orders planned: 26,956

- Work order tasks completed: 50,197

• Apparent Cause Analyses (ACAs) assigned: 287

- Engineering changes completed: 187

• Simple Causes assigned: 16,742

- NRC yellow sheets addressed: 1,885

- Modifications installed: 90

• D-level Condition Reports (CRs) assigned: 34,384

- Modification tasks: 11,614

- Parts issued: 50,317

- Radiography exams (RT shots): 474

- Clearances used: 7,906

- Clearance tags hung and removed: 34,547

- Dose to complete the work:180.113 REM 25 26 Closing Remarks Tonight, we updated you on

• Safety Culture

• Problem Identification and Resolution

• Design and Licensing Basis Control and Use

• Site Operational Focus

• Programs - Engineering Focus Areas

- Flooding Recovery Action Plans

- Beyond Design Basis Flood Mitigation

- Fukushima Response Project

- TornadoBorne Missiles

- HighEnergy Line Break

- 10 CFR 50.59

- Containment Internal Structures

• Nuclear Oversight

• Integration into the Exelon Nuclear Fleet 27 7