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Category:Inspection Report
MONTHYEARIR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion IR 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 IR 05000528/20233012023-06-0505 June 2023 NRC Examination Report 05000528/2023301, 05000529/2023301 and 05000530/2023301 IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) IR 05000528/20220062023-03-0101 March 2023 Annual Assessment Letter for Palo Verde Nuclear Generating Station Units 1, 2 and 3 (Report 05000528/2022006, 05000529/2022006, and 05000530/2022006) IR 05000528/20234012023-02-27027 February 2023 NRC Security Inspection Report 05000528/2023401, 05000529/2023401, 05000530/2023401, and 07200044/2023401 (Full Report) IR 05000528/20220042023-01-30030 January 2023 Integrated Inspection Report 05000528/2022004 and 05000529/2022004 and 05000530/2022004 IR 05000528/20220102023-01-17017 January 2023 Design Basis Assurance Inspection (Teams) Inspection Report 05000528/2022010 and 05000529/2022010 and 05000530/2022010 IR 05000528/20220032022-10-24024 October 2022 Units, 1, 2 and 3 Integrated Inspection Report 05000528/2022003, 05000529/2022003, and 05000530/2022003 IR 05000528/20224032022-10-14014 October 2022 Security Baseline Inspection Report 05000528/2022403 and 05000529/2022403 and 05000530/2022403 ML22235A6662022-08-23023 August 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000528/2022010, 05000529/2022010, and 05000530/2022010) and Request for Information IR 05000528/20220052022-08-23023 August 2022 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2022005 and 05000529/2022005 and 05000530/2022005) IR 05000528/20224022022-08-0808 August 2022 Cover Letter Only - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 NRC Security Inspection Report 05000528 2022402, 05000529 2022402, 05000530 2022402, and 07200044 2022402 IR 05000520/20220022022-08-0505 August 2022 Integrated Inspection Report 05000528/2022002 and 05000529/2022002 and 05000520/2022002 IR 05000528/20223012022-06-21021 June 2022 NRC Examination Report 05000528/2022301, 05000529/2022301, and 05000530/2022301 IR 05000528/20220012022-05-0909 May 2022 Integrated Inspection Report 05000528/2022001, 05000529/2022001 and 05000530/2022001 ML22105A0512022-04-19019 April 2022 Review of the 2021 Steam Generator Tube Inspections During Refueling Outage 22 IR 05000528/20224202022-03-0808 March 2022 Security Baseline Inspection Report 05000528/2022420, 05000529/2022420 and 05000530/2022420, Cover Letter IR 05000528/20210062022-03-0202 March 2022 Annual Assessment Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021006, 05000529/2021006, and 05000530/2021006) IR 05000528/20210042022-02-0707 February 2022 Integrated Inspection Report 05000528/2021004, 05000529/2021004, and 05000530/2021004 IR 05000528/20210032021-11-12012 November 2021 Integrated Inspection Report 05000528/2021003, 05000529/2021003 and 05000530/2021003 IR 05000528/20210152021-10-27027 October 2021 Temporary Instruction 2515/194 Report 05000528/2021015 and 05000529/2021015 and 05000530/2021015 ML21273A3172021-10-0404 October 2021 Station. NON-SENSITIVE IR 05000528/20214042021-09-23023 September 2021 NRC Security Inspection Report 05000528/2021404, 05000529/2021404, 05000530/2021404 and 07200044/2021401 IR 05000528/20214012021-09-14014 September 2021 Security Baseline Inspection Report 05000528/2021401 and 05000529/2021401 and 05000530/2021401 IR 05000528/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021005, 05000529/2021005, and 05000530/2021005) IR 05000528/20210022021-08-0909 August 2021 Integrated Inspection Report 05000528/2021002, 05000529/2021002, and 05000530/2021002 and Exercise of Enforcement Discretion IR 07200044/20214012021-07-21021 July 2021 ISFSI, Information Request, Security Inspection Report 07200044/2021401 IR 05000528/20210142021-07-14014 July 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000528/2021014, 05000529/2021014 and 05000530/2021014 IR 05000528/20213012021-06-21021 June 2021 NRC Initial Examination Report 05000528/2021301, 05000529/2021301, and 05000530/2021301 IR 05000528/20214032021-05-28028 May 2021 Security Baseline Inspection Report 05000528/2021403; 05000529/2021403 and 05000530/2021403 (Public) 2024-08-08
[Table view] Category:Letter
MONTHYEARIR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) IR 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations ML24066A0472024-03-0606 March 2024 Response to Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown and TS IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) 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 ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program 2024-08-08
[Table view] |
Text
March 16, 2018
Mr. Robert Executive Vice President Nuclear/
Chief Nuclear Officer
Arizona Public Service Company P.O. Box 52034, MS 7602 Phoenix, AZ 85072-2034
SUBJECT: PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION REPORT (NRC INSPECTION REPORT 05000528/2018012; 05000529/2018012; 05000530/2018012)
Dear Mr. Bement:
On February 15, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 and discussed the results of this inspection with Ms. Maria Lacal, Senior Vice-President Regulatory and Oversight,
and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC team documented one finding of very low safety significance (Green) in this report. This finding did not involve a violation of NRC requirements.
If you disagree with the finding not associated with a regulatory requirement 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 U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC resident inspector at the Palo Verde Nuclear Generating Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."
Sincerely,/RA/
Gregory E. Werner, Chief Engineering Branch 2 Division of Reactor Safety
Docket Nos. 50-528; 50-529; 50-530 License Nos. NPF-41; NPF-51; NPF-74
Enclosure:
Inspection Report 05000528/2018012; 05000529/2018012; and 05000530/2018012 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report
Docket Numbers: 05000528, 05000529, 05000530
License Numbers: NPF-41, NPF-51, NPF-74
Report Numbers: 05000528/2018012, 05000529/2018012, 05000530/2018012
Enterprise Identifier: I-2017-012-0023
Licensee: Arizona Public Service Company
Facility: Palo Verde Nuclear Generating Station
Location: Tonopah, Arizona
Inspection Dates: January 29, 2018, to February 15, 2018
Inspectors: J. Mateychick, Senior Reactor Inspector (Team Lead)
B. Correll, Reactor Inspector N. Okonkwo, Reactor Inspector E. Uribe, Reactor Inspector
Approved By: G. Werner, Branch Chief Engineering Branch 2 Division of Reactor Safety 2 SUMMARY The U.S. Nuclear Regulatory Commission continued monitoring licensee's performance by conducting a Triennial Fire Protection Baseline Inspection at the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 in accordance with the Reactor Oversight Process.
The Reactor Oversight Process is the Nuclear Regulatory Commission's program for overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information. The Nuclear Regulatory Commission and self-revealed findings, violations, and additional items are summarized in the table below.
List of Findings and Violations Failure to provide adequate guidance to personnel to assure degraded or deficient emergency lighting required for post-fire safe shutdown was corrected in a timely manner.
Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems Green Finding FIN 05-000528/2018012-01;
05-000529/2018012-01; 05-000530/2018012
-01 Closed None 71111.05T-
Fire Protection (Triennial)
The inspectors identified a Green finding for failure to provide adequate guidance to assure degraded or deficient emergency lighting required for post-fire safe shutdown is corrected in a timely manner. Specifically, the licensee failed to specify that failed Appendix R emergency lighting observed during operator rounds must be promptly reported to ensure the 30-day repair requirement can be met.
3 INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures in effect at the beginning of the inspection unless otherwise noted. Currently approved inspection procedures with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html
. Samples were declared complete when the inspection procedure requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC)
2515, "Light-Water Reactor Inspection Program - Operations Phase." The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards."
REACTOR SAFETY 71111.05T - Fire Protection (Triennial)
The inspectors evaluated the design, operational status, and material condition of the licensee's fire protection program, including assumptions made in plant and area specific fire protection analyses, by verifying that the licensee's program includes:
(1) Adequate controls for combustibles and ignition sources inside the plant;
(2) Adequate fire detection and suppression capability;
(3) Passive fire protection features in good material condition;
(4) Adequate compensatory measures for out-of-service, degraded or inoperable fire protection equipment, systems, or features;
(5) Adequate protection to ensure the post-fire capability to safely shut down the plant, including implementation of NRC/industry fire
-induced circuit failure analysis guidance; (6) Feasible and reliable manual actions when appropriate to achieve safe shutdown; and
(7) Adequate review and documentation of fire protection program changes.
Fire Protection Risk-Significant Fire Area Inspection Activities (4 Samples)
The inspection team used the fire hazards analysis section of the Palo Verde Nuclear Generating Station Individual Plant Examination of External Events to select the following four risk-significant fire areas for review:
(1) Fire Area 1D, Fire Zone 7A, Channel A DC Equipment Room (2) Fire Area 1F, Fire Zone 5A, train A Engineered Safety Features Switchgear Room (3) Fire Area 15C, Fire Zone 42D, Auxiliary Building 100' Elevation West Corridors (4) Fire Area 15D, Fire Zone 42C, Auxiliary Building 100' Elevation East Corridors
4 The inspectors reviewed and evaluated the following fire protection inspection requirements:
(1) Fire brigade drill performance (2) Protection of safe shutdown capabilities (3) Passive fire protection (4) Active fire protection (5) Protection from damage from fire suppression activities (6) Alternative shutdown capability (7) Circuit analysis (8) Communications (9) Emergency lighting (10) Cold shutdown repairs (11) Compensatory measures a. Compensatory measures for degraded fire protection components b. Manual actions as compensatory measures for safe shutdown (12) Review and documentation of fire protection plan changes (13) Control of transient combustibles and ignition sources (14) Sample of fire protection corrective action documents
B.5.b Inspection Activities (2 Samples)
The inspectors evaluated feasibility of the B.5.b mitigating strategies by determining the following:
- Procedures are being maintained and adequate.
- Equipment is properly staged and is being maintained and tested.
- Station personnel are knowledgeable and can implement the procedures.
The inspectors reviewed the following two mitigating strategies contained in
Procedure 79IS-9ZZ05, "Palo Verde Nuclear Generating Station Severe Accident Management Guidelines," Revision 22:
- Appendix 16 - Containment Flooding 5 * Appendix 18 - Feed Steam Generators from Au xiliary Feedwater - Fire Protection Cross-Tie INSPECTION RESULTS Failure to provide adequate guidance to personnel to assure degraded or deficient emergency lighting required for post-fire safe shutdown was corrected in a timely manner.
Cornerstone Significance Cross-cutting Aspect Report Section Mitigating Systems Green Finding FIN 05000528/2018012-01; 05000529/2018012-01;
05000530/2018012
-01 Closed None 71111.05T-
Fire Protection (Triennial)
The inspectors identified a Green finding for failure to provide adequate guidance to assure degraded or deficient emergency lighting required for post-fire safe shutdown is corrected in a timely manner. Specifically, the licensee failed to specify that failed Appendix R emergency lighting observed during operator rounds must be promptly reported to ensure the 30-day repair requirement can be met.
Description: The licensee provides emergency lighting for access and egress paths, and to illuminate required safe shutdown components to safely shut down the reactor in case of fire requiring control room evacuation, in accordance with 10 CFR 50, Appendix R, Section III.J., Procedure 40DP-9ZZ16, "Administrative Controls for Appendix R Equipment," Revision 13, Steps 4.5.1 and 4.6.1, limit the out-of-service time for Appendix R equipment and require restoring the equipment to service within 30 days. The licensee provides guidance to operations department watch standers to check for deficient lighting throughout the plant. Procedure 40DP-9OP20, "Watch Standing Practices," Revision 48, Step 4.3.1.1 instructs watch standers to check for "adequate or sufficient lighting," among other items during routine tours of the plant.
On January 30, 2018, during the walkdown of the control room evacuation due to fire Procedure 40AO-9ZZ19, "Control Room Fire," Revision 35, the inspectors identified multiple examples of Appendix R emergency light fixtures that were not functional. The licensee confirmed no condition report had documented these deficient emergency lights at that time.
During operator rounds through the area, with offsite power available, the area had adequate and sufficient lighting from the normal AC lighting system. The guidance provided in Procedure 40DP-9OP20 was not adequate to instruct watch standers to identify when an Appendix R emergency light is not functional and to promptly identify the failure to ensure timely restoration of the light.
Corrective Actions: The licensee documented the emergency light deficiencies in the corrective action program to initiate repairs, and also issued an Operations Communication Newsflash titled, "Actions needed on Emergency (App R) Lighting," dated February 1, 2018. The Newsflash required all operations crews to review procedures for identifying emergency lighting deficiencies and to focus on the emergency light fixtures. The licensee has 30 days to repair and restore the emergency lights to operation. The licensee has a standing 6 compensatory measure for emergency lighting requiring operators to obtain flashlights from the emergency storage locker during a control room evacuation due to fire.
The licensee initiated a revision request to provide additional guidance in Procedure 40DP-9OP20, concerning the Appendix R emergency lighting.
Corrective Action Reference(s): 18-01512, 18-01683, 18-01685, 18-01702, 18-01737 Performance Assessment:
Performance Deficiency: The Licensee failed to provide adequate guidance to personnel to assure degraded or deficient emergency lighting required for post-fire safe shutdown was corrected in a timely manner. The licensee failed to specify in Procedure 40DP-0OP20,
"Watch Standing Practices," that degraded or deficient Appendix R emergency lighting was to be promptly identified to ensure restoration within the licensee's 30-day requirement.
Screening:
The inspectors determined the performance deficiency was more than minor because it adversely affected the Protection Against External Factors (Fire) attribute of the Mitigating Systems cornerstone to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, emergency lighting is required for access and egress, and to illuminate safe shutdown equipment needed to bring the reactor to safe shutdown following a fire.
Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter (IMC) 0609, Appendix F, "Fire Protection," dated September 20, 2013. The finding is associated with the Mitigating Systems cornerstone and screened to Green with Step 1.3.1 because the reactor is able to reach and maintain safe shutdown conditions because the operators are required to carry flashlights to accomplish the safe shutdown procedure.
Cross-cutting Aspect: No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Inspectors did not identify a violation of regulatory requirements associated with this finding.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On February 15, 2018, the inspector presented the triennial fire protection inspection results to Ms. M. Lacal, Senior Vice-President Regulatory and Oversight, and other members of the licensee staff.
DOCUMENTS REVIEWED The documents reviewed related to the finding are included in the inspection results section.
ML18078A876 SUNSI Review By: JMM Non-Sensitive Sensitive Publicly Available Non-Publicly Available Keyword: NRC-002 OFFICE RI:EB2 RI:EB2 RI:IPAT SRI:EB2 BC:DRS/EB2 BC:DRP/D BC:DRS/EB2 NAME BCorrell NOkonkwo EUribe JMateychick GWerner GMiller GWerner SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 2/28/18 03/05/18 03/05/18 03/05/18 03/13/2018 03/13/2018 03/16/2018