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| {{Adams | | {{Adams |
| | number = ML14063A628 | | | number = ML14072A571 |
| | issue date = 03/04/2014 | | | issue date = 03/13/2014 |
| | title = Annual Assessment Letter for Wolf Creek Generating Station (Report 05000482/2013001) | | | title = Errata For Wolf Creek Generating Station Annual Assessment Letter For (Report 05000482-13-001) |
| | author name = Dapas M L | | | author name = Dapas M L |
| | author affiliation = NRC/RGN-IV/ORA | | | author affiliation = NRC/RGN-IV |
| | addressee name = Heflin A C | | | addressee name = Heflin A C |
| | addressee affiliation = Wolf Creek Nuclear Operating Corp | | | addressee affiliation = Wolf Creek Nuclear Operating Corp |
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| | license number = NPF-042 | | | license number = NPF-042 |
| | contact person = O'Keefe N F | | | contact person = O'Keefe N F |
| | case reference number = IR-13-001 | | | document report number = IR-13-001 |
| | document type = Inspection Plan, Letter | | | document type = Letter |
| | page count = 6 | | | page count = 6 |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter: |
| [[Issue date::March 4, 2014]] | | [[Issue date::March 13, 2014]] |
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| Mr. Adam C. Heflin, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 | | Mr. Adam C. Heflin, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 |
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| SUBJECT: ANNUAL ASSESSMENT LETTER FOR WOLF CREEK GENERATING STATION (REPORT 05000482/2013001) | | SUBJECT: ERRATA FOR WOLF CREEK GENERATING STATION ANNUAL ASSESSMENT LETTER FOR (REPORT 05000482/2013001) |
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| ==Dear Mr. Heflin:== | | ==Dear Mr. Heflin:== |
| On February 12, 2014, the NRC completed its end-of-cycle performance review of Wolf Creek Generating Station. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2013, through December 31, 2013. This letter informs you of the NRC's assessment of Wolf Creek Generating Station during this period and its plans for future inspections at that facility. The NRC determined that overall, Wolf Creek Generating Station was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Wolf Creek Generating Station during the most recent quarter was within the Licensee Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., Green) safety significance, and all PIs indicated that plant performance was within the nominal, expected range (i.e., Green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility. Although plant performance was within the Licensee Response Column, the NRC has not yet finalized the significance of a preliminary Greater-than-Green finding in the physical security cornerstone documented in NRC Inspection Report 05000482/2013403 (ML13346A227). The final safety significance determination may affect the NRC's assessment of plant performance and the enclosed inspection plan. You will be notified by separate correspondence of the final significance for this finding, as well as any changes to our performance assessment and associated inspection plan. At the beginning of this assessment cycle, Wolf Creek Generating Station was in the Degraded Cornerstone Column because there was one Yellow finding and one White performance indicator in the Mitigating Systems Cornerstone. The Yellow finding involved your staff's failure to provide adequate oversight of contractors while they performed work that could affect safety- related equipment in April 2011. The performance indicator for Mitigating Systems Performance Index - Emergency AC System (MSPI - EAC) had been reported as White since the first quarter of 2012. On June 7, 2013, the NRC completed a supplemental inspection pursuant to Inspection Procedure 95002, "Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area," at Wolf Creek Generating Station. This A.Heflin - 2 - inspection was performed to assess your staff's evaluation of the root causes, contributing causes, and corrective actions associated with the Yellow finding, and included an assessment of actions to address four open substantive cross-cutting issues. The team also performed a limited scope independent safety culture assessment follow-up in accordance with Inspection Procedure 40100, "Independent Safety Culture Assessment Follow-up." The inspectors determined that your staff performed a comprehensive evaluation to identify appropriate causes for the Yellow finding, and corrective actions were appropriate to address those causes. Based on the results of this inspection, the Yellow finding was closed in NRC Inspection Report 05000482/2013010 (ML13203A329). On April 29, 2013, the NRC completed the supplemental inspection to review the action taken to address the White MSPI - EAC, pursuant to Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." As documented in NRC Inspection Report 05000482/2013009 (ML13126A197), this inspection was performed to assess your staff's evaluation of the root causes, contributing causes, and corrective actions associated with the White PI. The PI data reported for Wolf Creek Generating Station for the second quarter of 2013 indicated that MSPI - EAC had returned to Green. Therefore, since four quarters had passed since the White PI was identified; the NRC had concluded based on the 95001 supplemental inspection results, that you had adequately evaluated and addressed the performance issues; and given that the PI had returned to Green as of June 30, 2013, Wolf Creek Generating Station was returned to the Licensee Response column as of July 1, 2013. The NRC also issued a Chilling Effect Letter (CEL) (ADAMS ML13233A208) to Wolf Creek Nuclear Operating Corporation on August 19, 2013. The CEL was issued because the Occupational Safety and Health Administration (OSHA) had issued a finding of discrimination for raising safety concerns against a former employee of an engineering contractor employed by Wolf Creek Nuclear Operating Corporation, and due to the NRC identifying that a chilled work environment existed within your facility's Quality Assurance Group. Issuance of a CEL meets the NRC criteria in Inspection Manual Chapter (IMC) 0305, "Operating Reactor Assessment Program," for the identification of a cross-cutting theme in the area of safety conscious work environment (SCWE). However, the NRC has assessed your 30-day and 6-month responses to the CEL, and conducted a public meeting in the Region IV office on January 22, 2014, to discuss the actions that you are taking to address the working environment at your facility. The NRC has decided not to open a substantive cross-cutting issue in the area of SCWE at this time because the NRC staff does not have a concern with your actions. This theme will continue to be reviewed during the next two performance assessments as we continue to monitor your staff's actions to ensure Wolf Creek Generating Station is a workplace that fosters an environment where employees feel free, and are encouraged, to raise safety concerns. 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 scheduled to be conducted during the last nine months are tentative and may be revised based on the results of the mid-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact your staff 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.
| | This errata corrects errors that were in the original report. Please replace the first three pages of the letter dated March 4, 2014, with the enclosed pages. The purpose of the change is to correct the inadvertent omission of the discussion of the cross-cutting aspect theme in the human performance area of resources. |
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| A.Heflin - 3 - 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 aid the NRC staff in development of an ultimate Safety Evaluation for the site. The NRC staff will be working with your staff to establish a date for the onsite component audit. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised effective January 1, 2014. New cross-cutting aspects will be coded in accordance with the latest revision to NRC Inspection Manual Chapter (IMC) 0310, "Aspects within Cross-Cutting Areas", dated December 19, 2013. Cross-cutting aspects identified in the last six months of 2013 using the previous terminology will be converted to the revised language in accordance with the cross-reference in IMC 0310. The revised cross- cutting aspects will be evaluated for cross-cutting themes and potential substantive cross- cutting issues in accordance with IMC 0305 starting with the calendar year 2014 mid-cycle assessment. In accordance with 10 CFR 2.390 of the NRC's 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 (PARS) component of NRC's 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). Please contact Neil O'Keefe at 817-200-1141 with any questions you or your staff may have regarding this letter.
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/readingrm/adams.html. To the extent possible, your response should not include any personal privacy or proprietary, information so that it can be made available to the Public without redaction. |
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| Sincerely,/RA/ Marc L. Dapas, Regional Administrator Docket No. 50-482 License No. NPF-42 | | Sincerely,/RA/ Anton Vegel for Marc L. Dapas Regional Administrator Docket No. 50-482 License No. NPF-42 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Plan A.Heflin - 4 - | | Replacement pages for Inspection Report 05000482/2013001 |
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| R:\_REACTORS\EOC 2013\WC2013 EOC LTR NFO 140304.docx ML14063A628 ADAMS: No Yes SUNSI Review Complete Reviewer Initials: NFO Publicly Available Non-Sensitive Non-publicly Available Sensitive DRP B/BC DRS/DIR DRP/DIR RA NO'Keefe JClark KKennedy MDapas /RA/ /RA/ /RA/ /RA/ 02/26/2014 02/28/2014 02/28/2014 03/03/2014 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax WolfCreek Inspection I Activity Plan 03/01/2014 - 06/30/2015 Page 1 of 2 02/27/2014 Report22 13:10:28 This report shows only on-site and announced inspection procedures. Enclosure RS 12 PI - RADIATION SAFETY Title 2 03/17/2014 03/21/2014 03/17/2014 03/21/2014 IP 71124.01 IP 71124.02 RadiologicalHazard Assessment and Exposure Controls Occupational ALARA Planning and Controls 03/17/2014 03/21/2014 03/17/2014 03/21/2014 IP 71151-0R01 Occupational Exposure Control Effectiveness IP 71151-PR01 RETS/ODCM Radiological Effluent TSB 52B - BIENNIAL PI&R 4 05/19/2014 05/23/2014 IP 71152B Problem Identification and Resolution 06/02/2014 06/06/2014 IP 711528 Problem Identification and Resolution RS 5678 - RADIATION SAFETY- TEAM 4 06/02/2014 06/06/2014 06/02/2014 06/06/2014 06/02/2014 06/06/2014 06/02/2014 06/06/2014 IP '11124.05 IP 71124.06 IP 71124.0'1 IP 71124.08 INSP Radiation Monitoring Instrumentation Radioactive Gaseous and Liquid Effluent Treatment Radiological Environmental Monitoring Program Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation - BIENNIAL REQUAL INSPECTION 3 08/25/2014 08/29/2014 10/20/2014 10/24/2014 11/03/2014 11/07/2014 IP 7111111B Licensed Operator Requalification Program EB2-05T - TRIENNIAL FIRE PROTECTION INSPECTION 4 IP 7111105T Fire Protection [Triennial] IP 7111105T Fire Protection [Triennial] EP-1 - EP PERFORMANCE INDICATORS 11/17/2014 11/1712014 11/17/2014 11/21/2014 11/21/2014 11/21/2014 IP 71151-EP01 IP 71151-EP02 IP 71151-EP03 Drill/Exercise Performance ERO Drill Participation Alert & Notification System EP-2 - EP PROGRAM INSPECTION 11/17/2014 11/1712014 11/17/2014 11/17/2014 11121/2014 11/21/2014 11/2112014 11121/2014 IP 7111402 IP 7111403 IP 7111404 IP 7111405 71111.08 Alert and Notification System Testing Emergency Preparedness Organization Staffing and Augmentation System Emergency Action Level and Emergency Plan Changes Correction of Emergency Preparedness Weaknesses and Deficiencies - INSERVICE INSPECTION 02/23/2015 03/06/2015 IP 7111108P lnservice Inspection Activities - PWR RS 13 PI - RADIATION SAFETY 2 03/09/2015 03/13/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 03/09/2015 03/13/2015 IP '11124.03 In-Plant Airborne Radioactivity Control and Mitigation 03/09/2015 03/13/2015 IP '11151-0R01 Occupational Exposure Control Effectiveness rfhis report does not include INPO and OUTAGE adlvffles.
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| WolfCreek Inspection I Activity Plan 03/01/2014 - 06/30/2015 Page 2 of 2 02/27/2014 Report22 13:10:28 *This report shows only on-site and announced inspection procedures. Enclosure i Unit i Number Planned Dates Start End RS 13 PI -RADIATION SAFETY - --*L. Title No. of Staff on Site 2 03/09/2015 03/13/2015 IP 71151-PR01 RETS/ODCM Radiological Effluent EB1-17T - WC PERMANENT PLANT MODS & 50.59 06/15/2015 06/26/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
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| Ttiis report does not inClude INPO and OUTAGE activities.
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Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
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Text
March 13, 2014
Mr. Adam C. Heflin, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT: ERRATA FOR WOLF CREEK GENERATING STATION ANNUAL ASSESSMENT LETTER FOR (REPORT 05000482/2013001)
Dear Mr. Heflin:
This errata corrects errors that were in the original report. Please replace the first three pages of the letter dated March 4, 2014, with the enclosed pages. The purpose of the change is to correct the inadvertent omission of the discussion of the cross-cutting aspect theme in the human performance area of resources.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/readingrm/adams.html. To the extent possible, your response should not include any personal privacy or proprietary, information so that it can be made available to the Public without redaction.
Sincerely,/RA/ Anton Vegel for Marc L. Dapas Regional Administrator Docket No. 50-482 License No. NPF-42
Enclosure:
Replacement pages for Inspection Report 05000482/2013001