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| {{Adams | | {{Adams |
| | number = ML15204A829 | | | number = ML16005A548 |
| | issue date = 07/23/2015 | | | issue date = 01/05/2016 |
| | title = IR 05000440/2015008, 09/21/15, Perry Nuclear Power Plant - Notification of NRC Triennial Fire Protection Baseline | | | title = Inspection Report 05000440/2015008; 09/22/2015 - 10/23/2015; Perry Nuclear Power Plant; Routine Triennial Fire Protection Baseline Inspection (Dxs) |
| | author name = Daley R | | | author name = Daley R |
| | author affiliation = NRC/RGN-III/DRS/EB3 | | | author affiliation = NRC/RGN-III/DRS/EB3 |
| | addressee name = Harkness E | | | addressee name = Hamilton D |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000440 | | | docket = 05000440 |
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| | contact person = | | | contact person = |
| | document report number = IR 2015008 | | | document report number = IR 2015008 |
| | document type = Inspection Plan, Letter | | | document type = Inspection Report, Letter |
| | page count = 11 | | | page count = 31 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES uly 23, 2015 | | {{#Wiki_filter:UNITED STATES ary 5, 2016 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PERRY NUCLEAR POWER PLANT - NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION 05000440/2015008 | | PERRY NUCLEAR POWER PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000440/2015008 |
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| ==Dear Mr. Harkness:== | | ==Dear Mr. Hamilton:== |
| On September 21, 2015, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial fire protection baseline inspection at your Perry Nuclear Power Plant. This inspection will be performed in accordance with Inspection Procedure (IP) 71111.05T, the NRCs baseline fire protection inspection procedure. | | On October 23, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a triennial fire protection inspection at your Perry Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on December 29, 2015, with Mr. N. Conicella, and other members of your staff. |
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| Changes were made to the IP 71111.05T, which now requires the fire protection inspection to review your actions to mitigate postulated events that could potentially cause loss of large areas of power reactor facilities due to explosions or fires. This requirement was implemented by the issuance of the Interim Compensatory Measures Order EA-02-026, Section B.5.b and the subsequent requirements of 10 CFR 50.54(hh)(2), which are collectively referred to as B.5.b requirements. During this inspection, the B.5.b requirements review will be performed during the first onsite week of the inspection starting on September 23, 2015.
| | The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. |
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| The schedule for the onsite inspection activity is as follows: | | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
| Information Gathering Visit: September 21 - 23, 2015; B.5.b Requirements: September 23 - 25, 2015; and Fire Protection Inspection: October 5 - 9 and October 19 - 23, 2015.
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| The purpose of the information gathering visit is: (1) to obtain information and documentation needed to support the inspection; (2) to become familiar with the Perry Nuclear Power Plant fire protection programs, fire protection features, post-fire safe shutdown capabilities, and plant layout; and (3) to arrange administrative details, such as office space, availability of knowledgeable office personnel and to ensure unescorted site access privileges. Experience has shown that the baseline fire protection inspections are extremely resource intensive both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both organizations, we have enclosed a request for documents needed for the inspection. These documents have been divided into four groups. The first group lists information necessary to aid the inspection team in choosing specific focus areas for the inspection. It is requested that this information be provided to the lead inspector via mail or electronically no later than September 11, 2015.
| | NRC inspectors documented four findings of very low safety significance (Green) in this report. |
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| The second group also lists information and areas for discussion necessary to aid the inspection team in choosing specific fire protection focus areas for the inspection and to ensure that the inspection team is adequately prepared for the inspection. It is requested this information be available during the information gathering visit (September 21, 2015). The third group of requested documents consists of those items that the team will review, or need access to, during the inspection. Please have this information available by the first day of the second onsite inspection week (October 5, 2015). The fourth group lists the information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up-to-date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
| | These findings were determined to involve violations of NRC requirements. However, because of their very low safety significance, and because the issues were entered into your Corrective Action Program, the NRC is treating the issues as Non-Cited Violations (NCVs) in accordance with Section 2.3.2 of the NRC Enforcement Policy. |
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| The lead inspector for this inspection is Mr. Dariusz Szwarc. We understand that our regulatory contact for this inspection is Mr. David Lockwood of your organization. If there are any questions about the inspection or the material requested, please contact the lead inspector at (630) 829-9803 or via e-mail at dariusz.szwarc@nrc.gov.
| | If you contest the subject or severity of the NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, Region III; the Director, Office of Enforcement, U.S. |
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| This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
| | Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Perry Nuclear Power Plant. |
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| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) | | In addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region III, and the NRC Resident Inspector at the Perry Nuclear Power Plant. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) |
| component of the NRC's Agencywide Documents Access and Management System (ADAMS). | | component of the NRC's Agencywide Documents Access and Management System (ADAMS). |
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| Sincerely, | | Sincerely, |
| /RA George Hausman Acting for/ | | /RA/ |
| Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-440 License No. NPF-58 Enclosure: Fire Protection Inspection Document Request cc w/encl: Distribution via LISTSERV | | Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-440 License Nos. NPF-58 |
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| NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION Inspection Report: 05000440/2015008 Onsite Inspection Dates: September 21 - 23, 2015 (Information Gathering Visit)
| | ===Enclosure:=== |
| September 23 - 25, 2015 (B.5.b Requirements)
| | Inspection Report 05000440/2015008 w/Attachment: Supplemental Information |
| October 5 - 9, 2015 (Fire Protection Inspection)
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| October 19 - 23, 2015 (Fire Protection Inspection)
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| Inspection Procedures: IP71111.05T, Fire Protection (Triennial)
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| IP71152, "Identification and Resolution of Problems" Inspectors: Dariusz Szwarc Alan Dahbur Senior Reactor Inspector (Lead) Senior Reactor Inspector (630) 829-9803 (630) 829-9810 dariusz.szwarc@nrc.gov alan.dahbur@nrc.gov George Hausman Robert Winter Senior Reactor Inspector Reactor Inspector (630) 829-9743 (630) 829-9758 george.hausman@nrc.gov robert.winter@nrc.gov I. Information Requested Prior To the Information Gathering Visit The following information is requested by September 11, 2015. If you have any questions regarding this request, please call the lead inspector as soon as possible. All information should be sent to Mr. Dariusz Szwarc (e-mail address dariusz.szwarc@nrc.gov). Electronic media is preferred. The preferred file format is a searchable pdf file on a compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of use, if possible.
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| Please provide four copies of each CD submitted (one for each inspector).
| | REGION III== |
| | Docket No: 50-440 License No: NPF-58 Report No: 05000440/2015008 Licensee: FirstEnergy Nuclear Operating Company Facility: Perry Nuclear Power Plant Location: North Perry, Ohio Dates: September 22 through October 23, 2015 Inspectors: A. Dahbur, Senior Reactor Inspector G. Hausman, Senior Reactor Inspector D. Szwarc, Senior Reactor Inspector, Lead R. Winter, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure |
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| 1. The most risk significant fire areas as determined by probabilistic risk analyses, if available. Otherwise, the reactor plant's Individual Plant Examination for External Events (IPEEE) for fire and results of any post-IPEEE reviews for fire.
| | Table of Contents Table of Contents..................................................................................................................... 2 |
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| 2. A copy of the current version of the fire protection program (FPP), fire hazards analysis (FHA), safe shutdown analysis (SSA), updated safety analysis report (USAR),
| | =SUMMARY= |
| technical specifications, license (including the fire protection license condition), and technical requirements manual (TRM) or equivalent for fire protection structures, systems, and components.
| | ................................................................................................................................ 2 |
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| 3. A list of fire areas requiring alternative shutdown capability, (i.e., those areas for which 10 CFR Part 50, Appendix R, Section III G requirements are satisfied under Section III.G.3), or where both safe shutdown trains can be affected.
| | =REPORT DETAILS= |
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| Enclosure
| | ==REACTOR SAFETY== |
| | ......................................................................................... 4 |
| | {{a|1R05}} |
| | ==1R05 Fire Protection== |
| | {{IP sample|IP=IP 71111.05T}} |
| | ....................................................................... 4 |
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| NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION 4. Plant operating procedures which would be used and describe shutdown for a postulated fire (for both areas requiring alternative shutdown and areas which do not require alternative shutdown). Only those procedures with actions specific to shutdown in the event of a fire need be included. In addition, please include those procedures which operators would use for initial response to a fire, such as annunciator or alarm response procedures, the procedure used for activating the fire brigade, and the procedure which directs operators to the applicable safe shutdown procedure.
| | ===.1 Protection of Safe Shutdown Capabilities ......................................................... 5=== |
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| 5. Analysis performed in support of plant evaluation regarding multiple spurious operation (MSO), which includes the following:
| | ===.2 Passive Fire Protection .................................................................................... 8=== |
| a. List of identified multiple spurious fire-induced circuit failure configurations; b. List of the generic and plant specific MSOs; c. Results of expert panel process and associated review/evaluation of the generic and plant-specific MSOs and existing safe shutdown analysis; and d. Evaluations and corrective actions taken for resolution of MSO issues.
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| II. Information Requested During the Information Gathering Visit (SEPTEMBER 21, 2015)
| | ===.3 Active Fire Protection ......................................................................................11=== |
| The following information is requested to be provided to the inspection team during the onsite information gathering visit. Except for Item 8, it is requested that the following information be provided on four sets of CDs (searchable, if possible) with the B.5.b Mitigating Strategies information (Items 8.a through 8.h) provided on one separate CD.
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| In addition, one set of hard copy drawings are requested for Items 4.a. through 4.d.
| | ===.4 Protection from Damage from Fire Suppression Activities ...............................11=== |
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| 1. One set of hard-copy documents for facility layout drawings which identify plant fire area delineation; areas protected by automatic fire suppression and detection; and locations of fire protection equipment.
| | ===.5 Alternative Shutdown Capability ......................................................................11=== |
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| 2. Licensing Information:
| | ===.6 Circuit Analyses ..............................................................................................12=== |
| a. All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)
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| applicable to fire protection (specifically including those SERs referenced by the plant fire protection license condition) and all licensing correspondence referenced by the SERs; b. All licensing correspondence associated with the comparison to Standard Review Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes; c. Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and associated licensing correspondence;
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| NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION d. For pre-1979 plants, all licensing correspondence associated with those sections of 10 CFR Part 50, Appendix R, that are not applicable to the plant under 10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated with those fire protection features proposed or implemented by the licensee that have been accepted by the NRC staff as satisfying the provisions of Appendix A to Branch Technical Position (BTP) APCSB 9.5-1 reflected in the NRC fire protection SERs issued before February 19, 1981, (10 CFR 50.48(b)(1)(i)); or those fire protection features, which were accepted by the NRC staff in comprehensive fire protection SERs issued before Appendix A to BTP APCSB 9.5-1 was published in August 1976 (10 CFR 50.48(b)(1)(ii)); and e. The final safety analysis report (FSAR) sections applicable to fire protection, FHA, and SSA in effect at the time of original licensing.
| | ===.7 Communications .............................................................................................15=== |
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| 3. Fire Protection Program:
| | ===.8 Emergency Lighting ........................................................................................15=== |
| a. A listing of changes made to the FPP since the last triennial fire protection inspection; b. For pre-1979 plants, a listing of the protection methodologies identified under 10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for selected fire zones/areas (to be determined during information gathering visit).
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| That is, please specify whether 3-hour rated fire barriers; (Section III.G.2.a), 20 foot separation along with detection and suppression; (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression; (Section III.G.2.c), or alternative shutdown capability; (Section III.G.3) is used as a strategy for each selected fire zone/area; c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe-shutdown evaluations);
| | ===.9 Cold Shutdown Repairs...................................................................................15=== |
| d. A list of applicable codes and standards related to the design of plant fire protection features. The list should include National Fire Protection Association (NFPA) code versions committed to (i.e., the NFPA Codes of Record); and e. List of plant deviations from code commitments and associated evaluations.
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| 4. Facility Information:
| | ===.10 Compensatory Measures ................................................................................16=== |
| a. Piping and instrumentation (flow) diagrams showing the components used to achieve and maintain hot standby and cold shutdown for fires outside the control room, those components used for those areas requiring alternative shutdown capability, and systems relied upon for B.5.b mitigation strategies. These can be of the type that are used for training;
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| NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION b. One-line schematic drawings of the electrical distribution system for 4160 Volts alternating current (Vac) down to 480Vac; c. One-line schematic drawings of the electrical distribution system for 250 Volts direct current (Vdc) and 125Vdc systems as applicable; d. Logic diagrams showing the components used to achieve and maintain hot standby and cold shutdown; and e. Safe shutdown cable routing database (requested electronically, such as on compact disc, if available).
| | ===.11 Review and Documentation of Fire Protection Program Changes ...................18=== |
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| 5. Operations Response for Fire Protection:
| | ===.12 Control of Transient Combustibles and Ignition Sources .................................18=== |
| a. Pre-fire plans for selected fire zones/areas (to be determined during information gathering visit);
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| b. Plant operating procedures which specify the initial operations response to a fire alarm or annunciator; and c. Procedure for calling out the fire brigade and requesting off-site assistance.
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| 6. Corrective Actions:
| | ===.13 B.5.b Inspection Activities=== |
| a. Listing of open and closed fire protection condition reports (i.e., problem identification forms and their resolution reports) since the date of the last triennial fire protection inspection; and b. List of current fire impairments, including duration.
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| 7. General Information:
| | ==OTHER ACTIVITIES== |
| a. A listing of abbreviations and/or designators for plant systems; b. Organization charts of site personnel down to the level of fire protection staff personnel; and c. A phone list for onsite licensee personnel. | | .......................................................................................19 |
| | {{a|4OA2}} |
| | ==4OA2 Identification and Resolution of Problems== |
| | {{IP sample|IP=IP 71152}} |
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| 8. B.5.b Mitigating Strategies:
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| a. A list of all modifications to regulatory commitments made to meet the requirements of Section B.5.b of the ICM Order, EA-02-026, dated February 25, 2002, the subsequently imposed license conditions, and 10 CFR 50.54(hh)(2);
| | ==4OA6 Management Meetings .............................................................................20== |
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| NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION b. Copies of procedures/guidelines that were revised or generated to implement the mitigation strategies. These could be extensive damage mitigation guidelines (EDMGs), severe accident management guidelines (SAMGs), emergency operating procedures (EOPs), abnormal operating procedures (AOPs), etc.;
| | ===.1 Exit Meeting Summary ....................................................................................20=== |
| c. A matrix that shows the correlation between the mitigation strategies identified in Nuclear Energy Institute 06-12 and the site-specific procedures or guidelines that are used to implement each strategy; d. A listing of engineering evaluations/calculations that were used to verify engineering bases for the mitigation strategies; e. Copies of procedures used to inventory equipment (hoses, fittings, pumps, etc.)
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| required to be used to implement the mitigation strategies; f. A list of B.5.b mitigating strategies, if any, which have implementing details that differ from that documented in the submittals and the safety evaluation report; g. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments)
| | ===.2 Interim Exit Meetings .......................................................................................20=== |
| required to implement any mitigating strategies; and h. A list of changes made to B.5.b mitigating strategies and associated procedures since the previous NRC inspection of B.5.b mitigating strategies (March 13, 2012).
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| 9. Onsite Discussions:
| | =SUPPLEMENTAL INFORMATION= |
| In addition, during the information gathering visit, it is requested that licensee staff be available for the following:
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| a. Informal discussion on plant procedures operators would use in the event of fire or explosion (including B.5.b mitigation strategies) and under what conditions would the plant be shutdown using alternative shutdown methodology; b. Informal discussion on the plants safe shutdown cable routing database and the plant-wide cable routing database, as applicable; c. A tour of alternative shutdown and risk significant fire areas; and d. A discussion of scheduling of fire drills which may occur during the inspection so that the inspectors may be able to observe a fire drill, if possible.
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| NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION III. Information Requested to be Available on First Day of the Second ONSITE Inspection Week (OCTOBER 5, 2015)
| | ==KEY POINTS OF CONTACT== |
| The following information is requested to be provided on the first day of inspection. It is requested that this information be provided on four sets of CDs (searchable, if possible).
| | .................................................................................................. 1 |
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| 1. Program Procedures:
| | ==LIST OF ITEMS== |
| a. Procedures for:
| | OPENED, CLOSED AND DISCUSSED........................................................ 1 |
| i. Administrative controls (such as allowed out of service times and compensatory measures) for fire protection systems and components; ii. Control of transient combustibles; and iii. Control of hot work.
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| b. List of maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, pumps, and suppression systems; and c. List of maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.
| | ==LIST OF DOCUMENTS REVIEWED== |
| | | ...................................................................................... 2 |
| 2. Design and Equipment Information:
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| a. Coordination calculations and/or justifications that verify fuse/breaker coordination for selected fire zones/areas (to be determined during information gathering visit) that are fed off of the same electrical buses as components in the protected safe shutdown train; b. Copies of significant fire protection and post-fire safe shutdown related design change package descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter (GL) 86-10 (or adverse to safe shutdown)
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| evaluations; c. Gaseous suppression system pre-operational testing, if applicable, for selected fire zones/areas (to be determined during information gathering visit);
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| d. Hydraulic calculations and supporting test data which demonstrate operability for water suppression systems, if applicable, for selected fire zones/areas (to be determined during information gathering visit);
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| e. Alternating current (ac) coordination calculations for 4160Vac down to 480Vac electrical systems; and f. List of all fire protection or Appendix R calculations.
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| NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REQUEST FOR INFORMATION 3. Assessment and Corrective Actions:
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| The three most recent fire protection Quality Assurance (QA) audits and/or fire protection self-assessments.
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| 4. Any updates to information previously provided.
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| IV. Information Requested to Be Provided Throughout the Inspection 1. Copies of any corrective action documents generated as a result of the inspection teams questions or queries during this inspection.
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| 2. Copies of the list of questions submitted by the inspection team members and the status/resolution of the information requested (provided daily during the inspection to each inspection team member).
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| If you have questions regarding the information requested, please contact the lead inspector.
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Category:Inspection Report
MONTHYEARIR 05000440/20240022024-08-0808 August 2024 Integrated Inspection Report 05000440/2024002 IR 05000440/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000440/2024401 IR 05000440/20240112024-06-17017 June 2024 Fire Protection Team Inspection Report 05000440/2024011 IR 05000440/20240012024-04-24024 April 2024 Integrated Inspection Report 05000440/2024001 IR 05000440/20230062024-02-28028 February 2024 Annual Assessment Letter for Perry Nuclear Power Plant, Unit 1 (Report 05000440/2023006) IR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 IR 05000440/20234012023-08-28028 August 2023 Public - Perry Nuclear Power Plant Security Baseline Inspection Report 05000440/2023401 IR 05000440/20230052023-08-24024 August 2023 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2023005) IR 05000440/20230022023-08-0202 August 2023 Integrated Inspection Report 05000440/2023002 IR 05000440/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection Report 05000440/2023010 IR 05000440/20230012023-05-0404 May 2023 Integrated Inspection Report (05000440/2023001) IR 05000440/20220062023-03-0101 March 2023 Annual Assessment Letter for Perry Nuclear Power Plant, Unit 1 (Report 05000440/2022006) IR 05000440/20224062023-02-13013 February 2023 Material Control and Accounting Program Inspection Report 05000440/2022406 IR 05000440/20220042023-02-10010 February 2023 Integrated Inspection Report 05000440/2022004; and 07200069/2022001 and Exercise of Enforcement Discretion IR 05000440/20223012023-01-24024 January 2023 05000440/2022301 IR 05000440/20224052022-12-20020 December 2022 Security Baseline Inspection Report 05000440/2022405 (Cover Letter Only) IR 05000440/20220032022-11-0808 November 2022 Integrated Inspection Report 05000440/2022003 IR 05000440/20225012022-10-17017 October 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000440/2022501 IR 05000440/20220102022-09-29029 September 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000440/2022010 IR 05000440/20220052022-08-26026 August 2022 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2022005) IR 05000440/20220022022-08-0808 August 2022 Integrated Inspection Report 05000440/2022002 IR 05000440/20224202022-08-0404 August 2022 Security Baseline Inspection Report 05000440/2022420 - Cover Letter IR 05000440/20224022022-07-21021 July 2022 Security Baseline Inspection Report 05000440/2022402 IR 05000440/20224042022-06-0909 June 2022 Security Baseline Inspection Report 05000440/2022404 IR 05000440/20220012022-05-12012 May 2022 Integrated Inspection Report 05000440/2022001 IR 05000440/20210062022-03-0202 March 2022 Annual Assessment Letter for Perry Nuclear Power Plant, Unit 1 (Report 05000440/2021006) IR 05000440/20224012022-02-17017 February 2022 Security Baseline Inspection Report 05000440/2022401 IR 05000440/20210042022-02-11011 February 2022 Integrated Inspection Report 05000440/2021004 IR 05000440/20224032022-02-0909 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000440/2022403 IR 05000440/20210132022-01-10010 January 2022 Biennial Problem Identification and Resolution Inspection Report 05000440/2021013 IR 05000440/20210102021-12-0101 December 2021 Triennial Fire Protection Inspection Report 05000440/2021010 IR 05000440/20210032021-11-12012 November 2021 Integrated Inspection Report 05000440/2021003 IR 05000440/20214022021-10-27027 October 2021 Security Baseline Inspection Report 05000440/2021402 IR 05000440/20210122021-09-30030 September 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000440/2021012 IR 05000440/20210052021-09-0101 September 2021 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2021005) IR 05000440/20210022021-08-12012 August 2021 Integrated Inspection Report 05000440/2021002 IR 05000440/20210012021-06-10010 June 2021 NRC Inspection of Temporary Instruction 2515/194, Inspection of the Licensee'S Implementation of Industry Initiative Associated with the OPC Design Vulnerabilities in Electric Power Systems (NRC Bulletin 2012-01)-Inspection Report 0 ML21132A0952021-05-12012 May 2021 Integrated Inspection Report 05000440/2021001 IR 05000440/20213012021-04-0808 April 2021 NRC Initial License Examination Report 05000440/2021301 IR 05000440/20200062021-03-0404 March 2021 Annual Assessment Letter Perry Nuclear Power Plant (Report 05000440/2020006) IR 05000440/20200042021-02-12012 February 2021 Integrated Inspection Report 05000440/2020004 IR 05000440/20200102020-12-0303 December 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000440/2020010 IR 05000440/20204032020-12-0101 December 2020 Security Baseline Inspection Report 05000440/2020403 IR 05000440/20200032020-11-12012 November 2020 Integrated Inspection Report 05000440/2020003 and 07200069/2020001 IR 05000440/20205012020-10-16016 October 2020 Emergency Preparedness Biennial Exercise Inspection Report 05000440/2020501 IR 05000440/20204022020-09-23023 September 2020 Security Baseline Inspection Report 05000440/2020402 2024-08-08
[Table view] Category:Letter
MONTHYEARIR 05000440/20240022024-08-0808 August 2024 Integrated Inspection Report 05000440/2024002 L-24-178, License Renewal Application Revision O - Supplement 42024-08-0808 August 2024 License Renewal Application Revision O - Supplement 4 L-24-189, License Renewal Application for Revision O - Supplement 12024-08-0707 August 2024 License Renewal Application for Revision O - Supplement 1 L-24-171, Spent Fuel Storage Cask Registration2024-07-30030 July 2024 Spent Fuel Storage Cask Registration ML24150A2022024-07-25025 July 2024 Letter to Rod L. Penfield-Perry Nuclear Power Plant Unit 1-License Renewal Scoping Summary Rpt L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 IR 05000440/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000440/2024401 L-24-036, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-27027 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-24-020, License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 22024-06-27027 June 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 2 IR 05000440/20240112024-06-17017 June 2024 Fire Protection Team Inspection Report 05000440/2024011 ML24157A3782024-06-0606 June 2024 – Revised Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 ML24141A1632024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-116, Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification2024-05-16016 May 2024 Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification L-24-085, Nudear Power Plant, Submittal of Emergency Plan, Revision 622024-05-0606 May 2024 Nudear Power Plant, Submittal of Emergency Plan, Revision 62 L-24-103, Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams2024-05-0202 May 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams ML24117A1222024-04-26026 April 2024 Confirmation of Initial License Examination IR 05000440/20240012024-04-24024 April 2024 Integrated Inspection Report 05000440/2024001 L-24-097, Submittal of 2023 Annual Radiological Effluent Release Report2024-04-22022 April 2024 Submittal of 2023 Annual Radiological Effluent Release Report L-24-096, Submittal of Annual Radiological Environmental Operating Report2024-04-22022 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24095A3282024-04-19019 April 2024 License Renewal Revised Schedule Letter L-24-066, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency2024-04-15015 April 2024 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency L-24-083, Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification2024-04-15015 April 2024 Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification ML24088A1922024-03-28028 March 2024 Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 L-24-057, Submittal of the Decommissioning Funding Status Report2024-03-28028 March 2024 Submittal of the Decommissioning Funding Status Report L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-076, Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-22022 March 2024 Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24064A2212024-03-14014 March 2024 Letter to Rod L. Penfield-Perry Nuclear Power Plant Unit 1 - Summary of the Jan-Feb 2024 Environmental Audit Related to the Review of the License Renewal Application Environmental Report ML24059A3922024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0080 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000440/20230062024-02-28028 February 2024 Annual Assessment Letter for Perry Nuclear Power Plant, Unit 1 (Report 05000440/2023006) L-24-053, Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-02-27027 February 2024 Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 ML24003A8032024-01-0303 January 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML23321A0472023-12-20020 December 2023 Letter to Rod L. Penfield - Perry Nuclear Power Plant, Unit 1 - License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 ML23292A2482023-10-19019 October 2023 Fws to NRC, Federal Agency Coordination Under ESA Section 7 for Perry Nuclear Plant, Unit 1, License Renewal, and Concurrence with Not Likely to Adversely Affect Determination for Northern Long-eared Bat ML23292A2472023-10-19019 October 2023 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 ML23249A1032023-10-0303 October 2023 Letter to Rod L. Penfield, Site Vice President-Perry Nuclear Power Plant, Unit 1-Notice of Intent to Conduct Scoping Process and Prepare an Environmental Impact Statement 2024-08-08
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Inspection Report - Perry - 2015008 |
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UNITED STATES ary 5, 2016
SUBJECT:
PERRY NUCLEAR POWER PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000440/2015008
Dear Mr. Hamilton:
On October 23, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a triennial fire protection inspection at your Perry Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on December 29, 2015, with Mr. N. Conicella, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
NRC inspectors documented four findings of very low safety significance (Green) in this report.
These findings were determined to involve violations of NRC requirements. However, because of their very low safety significance, and because the issues were entered into your Corrective Action Program, the NRC is treating the issues as Non-Cited Violations (NCVs) in accordance with Section 2.3.2 of the NRC Enforcement Policy.
If you contest the subject or severity of the NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, Region III; the Director, Office of Enforcement, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Perry Nuclear Power Plant.
In addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region III, and the NRC Resident Inspector at the Perry Nuclear Power Plant. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents 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).
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-440 License Nos. NPF-58
Enclosure:
Inspection Report 05000440/2015008 w/Attachment: Supplemental Information
REGION III==
Docket No: 50-440 License No: NPF-58 Report No: 05000440/2015008 Licensee: FirstEnergy Nuclear Operating Company Facility: Perry Nuclear Power Plant Location: North Perry, Ohio Dates: September 22 through October 23, 2015 Inspectors: A. Dahbur, Senior Reactor Inspector G. Hausman, Senior Reactor Inspector D. Szwarc, Senior Reactor Inspector, Lead R. Winter, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
Table of Contents Table of Contents..................................................................................................................... 2
SUMMARY
................................................................................................................................ 2
REPORT DETAILS
REACTOR SAFETY
......................................................................................... 4
1R05 Fire Protection
Main article: IP 71111.05T
....................................................................... 4
.1 Protection of Safe Shutdown Capabilities ......................................................... 5
.2 Passive Fire Protection .................................................................................... 8
.3 Active Fire Protection ......................................................................................11
.4 Protection from Damage from Fire Suppression Activities ...............................11
.5 Alternative Shutdown Capability ......................................................................11
.6 Circuit Analyses ..............................................................................................12
.7 Communications .............................................................................................15
.8 Emergency Lighting ........................................................................................15
.9 Cold Shutdown Repairs...................................................................................15
.10 Compensatory Measures ................................................................................16
.11 Review and Documentation of Fire Protection Program Changes ...................18
.12 Control of Transient Combustibles and Ignition Sources .................................18
.13 B.5.b Inspection Activities
OTHER ACTIVITIES
.......................................................................................19
4OA2 Identification and Resolution of Problems
...................................19
4OA6 Management Meetings .............................................................................20
.1 Exit Meeting Summary ....................................................................................20
.2 Interim Exit Meetings .......................................................................................20
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
.................................................................................................. 1
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED........................................................ 1
LIST OF DOCUMENTS REVIEWED
...................................................................................... 2