ML19162A106
| ML19162A106 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/13/2019 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | Heflin A Wolf Creek |
| Singal B, NRR/DORL/LPL4-1 | |
| References | |
| EPID L-2019-LLA-0062 | |
| Download: ML19162A106 (6) | |
Text
Mr. Adam C. Heflin UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Jun e 13, 2019 President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION, UNIT 1-REGULATORY AUDIT PLAN IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.3.5, "LOSS OF POWER (LOP) DIESEL GENERATOR (DG) START INSTRUMENTATION" (EPID L-2019-LLA-0062)
Dear Mr. Heflin:
By letter dated March 18, 2019 (Agencywide Documents Access and Management System Accession No. ML19086A111 ), Wolf Creek Nuclear Operating Corporation submitted a license amendment request for Wolf Creek Generating Station, Unit 1, regarding revision to Technical Specification 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation."
Specifically, the license amendment request proposes to revise the degraded voltage and loss of voltage relays allowable values, nominal trip setpoints, and time delays specified in Surveillance Requirement 3.3.5.3.
The U.S. Nuclear Regulatory Commission staff has identified the need for a regulatory audit to examine the licensee's non-docketed information with the intent to gain understanding, to verify information, or to identify information that will require docketing to support the basis of the licensing or regulatory decision. The enclosure to this letter provides an audit plan in support of this audit.
If you have any questions, please contact me at 301-415-3016 or via e-mail at Balwant.Sinqal@nrc.gov.
Docket No. 50-482
Enclosure:
Regulatory Audit Plan cc: Listserv Sincerely,
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Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REGULATORY AUDIT PLAN TO SUPPORT REVIEW OF THE LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.3.5 "LOSS OF POWER (LOP) DIESEL GENERATOR (DG) START INSTRUMENTATION" WOLF CREEK GENERATING STATION, UNIT 1 DOCKET NO. 50-482
1.0 BACKGROUND
By letter dated March 18, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19086A111 ), Wolf Creek Nuclear Operating Corporation (the licensee) submitted a license amendment request (LAR) for Wolf Creek Generating Station, Unit 1, regarding revision to Technical Specification 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation." Specifically, the amendment proposes to revise the degraded voltage (DV) and loss of voltage (LOV) relays allowable values, nominal trip setpoints, and time delays specified in Surveillance Requirement (SR) 3.3.5.3.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined the need for a regulatory audit to be conducted in accordance with the Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195), for the NRC staff to examine the licensee's non-docketed information with the intent to gain understanding, to verify information, or to identify information that will require docketing to support the basis of the licensing or regulatory decision.
2.0 REGULATORY AUDIT BASIS The NRC staff will perform the audit to support its evaluation of whether the licensee's request meets the requirements of Title 10 of the Code of Federal Regulations, Section 50.90.
3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY The NRC staff will review the licensee's analyses/calculations related to DV and LOV relays nominal trip setpoints and allowable values, nominal trip setpoints, and time delays specified in SR 3.3,5.3 to determine if the licensee needs to submit any additional information contained in the analyses performed in support of the requested change to support or develop conclusions for the staff's safety evaluation.
4.0 INFORMATION NECESSARY FOR THE REGULATORY AUDIT The NRC staff requests the licensee to have the following information readily available and accessible for the staffs review via an internet-based portal:
Analysis/Calculation related to "Establish DV Relay Dropout Setting [Minimum Operating Voltage Limit]," as described in the LAR, Attac~ment I, Section 3.1.1.
Enclosure Analysis/Calculation related to "Confirm Adequacy of DV Relay Dropout Setting for Motor Starting," as described in LAR, Attachment I, Section.3.1.2.
Analysis/Calculation related to "Establish DV Relay Time Delay (with accident signal),"
as described in LAR, Attachment I, Section 3.1.3.
Analysis/Calculation related to "Confirm Reset of DV Relay with Minimum Required Grid Voltage," as described in LAR, Attachment I, Section 3.1.4.
Analysis/Calculation related to "Confirm LOV Relay Setpoint Prevents Motor Stalling," as described in LAR, Attachment I, Section 3.1.5.
Analysis/Calculation related to determine the setting of DV time delay relay with safety injection signal, as described in LAR, Attachment I, Section 3.3.
Based on the review of the documents provided, the NRC staff will determine whether it needs to request any additional documents to be made available on the portal, or additional information needs to be submitted on docket for the staff to complete the review of the requested change.
5.0 TEAM ASSIGNMENTS AND LOGISTICS The audit team will consist of the following NRR staff:
Mr. Vijay Goel, Electrical Engineering Operating Reactor Branch, NRR (Technical Team Lead)
Mr. Stephen Wyman, Electrical Engineering Operating Reactor Branch, NRR Mr. Balwant Singal, NRR (Project Manager)
If necessary, the NRC staff will conduct a teleconference with the licensee for the purposes of introducing the review team, discussing the scope of the audit, and describing the information to be made available on internet portal. The NRC staff will also confirm with the licensee if the information made available on the internet portal contains any sensitive or proprietary information.
The audit will occur intermittently via an internet-based portal at NRC Headquarters Office in Rockville, Maryland, from June 17, 2019, through July 12, 2019. The NRC staff requests the licensee to have the information discussed in Section 4.0 of this audit plan readily available and accessible for the staffs review via an internet-based portal by June 14, 2019. The NRC staff requests the licensee to have its staff available at a mutually agreeable day and time by telephone to answer the NRC staff questions during the audit related to information provided on the portal. The NRC staff will not conduct formal entrance or exit meetings; however, the NRC's project manager will inform the licensee via routine communications when the staff no longer needs access to the portal information. The NRC staff does not foresee-the need for an onsite visit or in-person discussions between the NRC and licensee staff to discuss information to be provided on the portal at this time. However, if the need for a such a meeting is identified in the future, the audit plan will be revised and the schedule for the audit will be adjusted accordingly.
J 6.0 DELIVERABLES After the audit, the NRC staff may develop a request for additional information, as needed. Any such request will be officially documented. The staff intends to issue an audit summary report by August 30, 2019.
ML19162A106 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NAME BSingal PBlechman DATE 06/11/19 06/11/19 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RPascarelli BSingal DATE 06/12/19 06/13/19