ML14323A680
| ML14323A680 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/24/2014 |
| From: | John Hughey Japan Lessons-Learned Division |
| To: | Rausch T Susquehanna |
| Hughey J, NRR/JLD, 415-3204 | |
| References | |
| EA-12-049, EA-12-051, TAC MF0888, TAC MF0889, TAC MF0890, TAC MF0891 | |
| Download: ML14323A680 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 24, 2014 Mr. Timothy S. Rausch Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2- PLAN FOR THE ONSITE AUDIT REGARDING IMPLEMENTATION OF MITIGATING STRATEGIES AND RELIABLE SPENT FUEL INSTRUMENTATION RELATED TO ORDERS EA-12-049 AND EA-12-051 (TAC NOS. MF0888, MF0889, MF0890 AND MF0891)
Dear Mr. Rausch:
On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events" and Order EA-12-051, "Order to Modify Licenses With Regard To Reliable Spent Fuel Pool Instrumentation," (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12054A736 and ML12054A679, respectively). The orders require holders of operating reactor licenses and construction permits issued under Title 10 of the Code of Federal Regulations Part 50 to submit for review, Overall Integrated Plans (OIPs) including descriptions of how compliance with the requirements of of each order will be achieved.
By letter dated February 28, 2013 (ADAMS Accession No. ML13060A357), PPL Susquehanna, LLC (PPL, the licensee) submitted its OIP for Susquehanna Steam Electric Station (SESS),
Units 1 and 2, in response to Order EA-12-049. By letters dated August 26, 2013, February 28, 2014 and August 27. 2014 (ADAMS Accession Nos. ML13240A214, ML14062A061 and ML14251A231, respectively), the licensee submitted its first three six-month updates to the OIP.
By letter dated August 28, 2013 (ADAMS Accession No. ML13234A503), the NRC not1fied all licensees and construction permit holders that the staff is conducting audits of their responses to Order EA-12-049 in accordance with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195). This audit process led to the issuance of the SESS interim staff evaluation (IS E) and audit report (ADAMS Accession No. ML13339A750) on January 24, 2014, and continues with in-office and onsite portions of this audit.
T. Rausch By letter dated February 28, 2013 (ADAMS Accession No. ML13064A276), the licensee submitted its OIP for SESS in response to Order EA-12-051. By letter dated June 17,2013 (ADAMS Accession No. ML13163A003), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated July 3, 2013, August 26, 2013, February 27, 2014 and August 27, 2014 (ADAMS Accession Nos. ML13186A052, ML13240A215, ML14059A079, and ML14239A527, respectively), the licensee submitted its RAI responses and first three six-month updates to the OIP. The NRC staff's review of these submittals led to the issuance of the SESS ISE and RAI dated November 6, 2013 (ADAMS Accession No. ML13295A606). By letter dated March 26, 2014 (ADAMS Accession No. ML14083A620), the NRC notified all licensees and construction permit holders that the staff is conducting in-office and onsite audits of their responses to Order EA-12-051 in accordance with NRC NRR Office Instruction LIC-111, as discussed above.
The ongoing audit process, to include the in-office and onsite portions, allows the staff to assess whether it has enough information to make a safety evaluation of the integrated plans. The audit allows the staff to review open and confirmatory items from the mitigation strategies ISE, RAI responses from the spent fuel pool instrumentation ISE, the licensee's integrated plans, and other audit questions. Additionally, the staff gains a better understanding of submitted information, identifies additional information necessary for the licensee to supplement its plan, and identifies any staff potential concerns. The audit's onsite portion will occur prior to declarations of compliance for the first unit at each site.
This document outlines the onsite audit process that occurs after ISE issuance as licensees provide new or updated information via periodic updates, update audit information on e-portals, provide preliminary Overall Program Documents/Final Integrated Plans, and continue in-office audit communications with staff while proceeding towards compliance with the orders.
The staff plans to conduct an onsite audit at SSES in accordance with the enclosed audit plan from December 8 - 11, 2014.
T. Rausch If you have any questions, please contact me at 301-415-3204 or by e-mail at John.Hughey@nrc.gov.
John D. Hughey, Project Manager Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos.: 50-387 and 50-388
Enclosure:
Audit plan cc w/encl: Distribution via Listserv
Audit Plan Susquehanna Electric Steam Station, Units 1 and 2 BACKGROUND AND AUDIT BASIS On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events" and Order EA-12-051, "Order to Modify Licenses With Regard To Reliable Spent Fuel Pool Instrumentation," (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12054A736 and ML12054A679, respectively). Order EA-12-049 directs licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool (SFP) cooling capabilities in the event of a beyond-design-basis external event (BDBEE). Order EA-12-051 requires, in part, that all operating reactor sites have a reliable means of remotely monitoring wide-range SFP levels to support effective prioritization of event mitigation and recovery actions in the event of a BDBEE. The orders require holders of operating reactor licenses and construction permits issued under Title 10 of the Code of Federal Regulations Part 50 to submit for review, Overall Integrated Plans (OIPs) including descriptions of how compliance with the requirements of Attachment 2 of each order will be achieved.
By letter dated February 28, 2013 (ADAMS Accession No. ML13060A357), PPL Susquehanna, LLC (PPL, the licensee) submitted its OIP for Susquehanna Steam Electric Station (SESS),
Units 1 and 2, in response to Order EA-12-049. By letters dated August 26, 2013, February 28, 2014 and August 27, 2014 (ADAMS Accession Nos. ML13240A214, ML14062A061 and ML14251A231, respectively), the licensee submitted its first three six-month updates to the OIP.
By letter dated August 28, 2013 (ADAMS Accession No. ML13234A503), the NRC notified all licensees and construction permit holders that the staff is conducting audits of their responses to Order EA-12-049 in accordance with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195). This audit process led to the issuance of the SESS interim staff evaluation (ISE) and audit report (ADAMS Accession No. ML13339A750) on January 24, 2014, and continues with in-office and onsite portions of this audit.
By letter dated February 28, 2013 (ADAMS Accession No. ML13064A276), the licensee submitted its OIP for SESS in response to Order EA-12-051. By letter dated June 17, 2013 (ADAMS Accession No. ML13163A003), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated July 3, 2013, August 26, 2013, February 27, 2014 and August 27, 2014 (ADAMS Accession Nos. ML13186A052, ML13240A215, ML14059A079, and ML14239A527, respectively), the licensee submitted its RAI responses and first three six-month updates to the OIP. The NRC staff's review of these submittals led to the issuance of the SESS ISE and RAI dated November 6, 2013 (ADAMS Accession No. ML13295A606). By letter dated March 26, 2014 (ADAMS Accession No. ML14083A620), the NRC notified all licensees and construction permit holders that the staff is conducting in-office and onsite audits of their responses to Order EA-12-051 in accordance with NRC NRR Office Instruction LIC-111, as discussed above.
Enclosure
The ongoing audit process, to include the in-office and onsite portions, allows the staff to assess whether it has enough information to make a safety evaluation of the integrated plans. The audit allows the staff to review open and confirmatory items from the mitigation strategies ISE, RAI responses from the spent fuel pool instrumentation (SFPI) ISE, the licensee's integrated plans, and other audit questions. Additionally, the staff gains a better understanding of submitted information, identifies additional information necessary for the licensee to supplement its plan, and identifies any staff potential concerns. The audit's onsite portion will occur prior to declarations of compliance for the first unit at each site.
This document outlines the onsite audit process that occurs after ISE issuance as licensees provide new or updated information via periodic updates, update audit information on e-portals, provide preliminary Overall Program Documents (OPDs)/Finallntegrated Plans (FIPs), and continue in-office audit communications with staff while proceeding towards compliance with the orders.
Following the licensee's declarations of order compliance, the NRC staff will evaluate the OIPs as supplemented, the resulting site-specific OPDs/FIPs, and, as appropriate, other licensee submittals based on the requirements in the orders. For Order EA-12-049, the staff will make a safety determination regarding order compliance using the Nuclear Energy Institute (NEI) guidance document NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" issued in August 2012 (ADAMS Accession No. ML12242A378), as endorsed by NRC Japan Lessons-Learned Directorate (JLD) interim staff guidance (ISG) JLD-ISG-2012-01 "Compliance with Order EA-12-049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events"' (ADAMS Accession No. ML12229A174) as providing one acceptable means of meeting the order requirements. For Order EA-12-051, the staff will make a safety determination regarding order compliance using the NEI guidance document NEI 12-02, "Industry Guidance for Compliance with NRC Order EA-12-051, 'To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation"' (ADAMS Accession No. ML12240A307), as endorsed, with exceptions and clarifications, by NRC ISG JLD-ISG-2012-03 "Compliance with Order EA-12-051, 'Reliable Spent Fuel Pool Instrumentation"' (ADAMS Accession No. ML12221A339) as providing one acceptable means of meeting the order requirements. Should the licensee propose an alternative strategy or other method deviating from the guidance, additional staff review will be required to evaluate if the alternative strategy complies with the applicable order.
AUDIT SCOPE As discussed, onsite audits will be performed per NRR Office Instruction LIC-111, "Regulatory Audits," to support the development of safety evaluations. Site-specific OIPs and OPDs/FIPs rely on equipment and procedures that apply to all units at a site, therefore, audits will be planned to support the first unit at each site." Onsite audits for subsequent units at a site will be on an as-needed basis.
The purpose of the audits is to obtain and review information responsive to the SSES OIPs, as supplemented, open and confirmatory items from the mitigation strategies ISE, RAI responses from the SFPI ISE, and to observe and gain a better understanding of the basis for the site's overall programs to ensure the licensee is on the correct path for compliance with the Mitigation Strategies and SFPI orders. These may include, but are not limited to:
- Onsite review and discussion for the basis and approach for detailed analysis and calculations (Orders EA-12-049, EA-12-051);
- Walk-throughs of strategies and laydown of equipment to assess feasibility, timing, and effectiveness of a given mitigating strategy or integration of several strategies (Order EA-12-049);
- Storage, protection, access, and deployment feasibility and practicality for onsite portable equipment (Order EA-12-049);
- Evaluation of staging, access, and deployment of offsite resources to include equipment provided by the Strategic Alliance for FLEX Emergency Response from the National SAFER Response Centers (NSRCs) (Order EA-12-049); and
- Review dimensions and sizing of the SFP area, placement of the SFP level instrumentation, and applicable mounting methods and design criteria (Order EA 051 ).
NRC AUDIT TEAM Title Team Member Team Lead I Project Manar~er John Hughey Technical Support Matthew McConnell Technical Support Stephen Wyman Technical Support Michael Levine Technical Support Reed Anzalone Technical Support Due Nguyen Technical Support Bruce Heida NRC AUDIT TEAM- SUPPLEMENTAL MEMBERS Title Team Member Resident Ins ector Travis Daun LOGISTICS The audit will be conducted onsite at SSES on December 8 - 11, 2014. Entrance and exit briefings will be held with the licensee at the beginning and end of the audit, respectively, as well as daily briefings of team activities. Additional details will be addressed over the phone. A more detailed schedule is provided below.
A private conference room is requested for NRC audit team use with access to audit documentation upon arrival and as needed.
DELIVERABLES An audit report/summary will be issued to the licensee within 90 days from the end of the audit.
INFORMATION NEEDS
- Materials/documentation provided in responses to open or confirmatory items and RAis in the ISEs;
operator training plans, Strategic Alliance for FLEX Emergency Response (SAFER)
Response Plan for SSES; and
- Materials/documentation for staff audit questions and/or licensee OIP identified open items as listed in the Part 2 table below To provide supplemental input to the ongoing audit of documents submitted to the NRC and made available viae-portal, the onsite audit will have three components: 1) a review of the overall mitigating strategies for the site, including, if needed, walk-throughs of strategies and equipment laydown of select portions; 2) a review of material relating to open or confirmatory items and RAis from the ISEs, staff audit questions, and licensee open items; and 3) additional specific issues requested by NRC technical reviewers related to preparation of a safety evaluation. Each part is described in more detail below:
Part 1 - Overall Mitigating Strategies and Program Review:
During the onsite audit, please be prepared to conduct a tabletop discussion of the site's integrated mitigating strategies and SFPI compliance program. This discussion should address the individual components of the plans, as well as the integrated implementation of the strategies including a timeline. The licensee team presenting this should include necessary representatives from site management, engineering, training, and operations that were responsible for program development, and will be responsible for training and execution.
Following the tabletop discussion please be prepared to conduct walk-throughs of procedures and demonstrations of equipment as deemed necessary by NRC audit team members. Include representatives from engineering and operations that will be responsible for training and execution. At this time we expect, at a minimum, to walk-through the items below. Based on the tabletop presentations and audit activities, this list may change.
WALK-THROUGH LIST:
- 1. Walk-through a sample of strategies that will be delineated by specific NRC technical staff audit team members
- 2. Walk-through of portable (FLEX) diesel generator (DG) procedures, to include power supply pathways, areas where manual actions are required, and electrical isolation
- 3. Walk-through of building access procedures, to include any unique access control devices
- 4. Strategy walk-through of transfer routes from staging and storage areas to deployment locations for both onsite and offsite equipment
- 5. Strategy walk-through for core cooling and reactor coolant system (RCS) inventory, to include portable pumping equipment, flow paths, and water storage locations and the related reactor systems analysis and calculations
- 6. Walk-through of communications enhancements
- 7. Walk-through of SFP area, SFPI locations, and related equipment mounting areas Part 2- Specific Technical Review Items:
During the visit, audit items will be addressed from the licensee's ISEs open items, confirmatory items, and SFPI RAis; audit question list; licensee OIP, as supplemented, open items; and draft safety evaluation additional questions. Please provide documents or demonstrations as needed to respond to each item.
Part 3- Specific Topics for Discussion:
- 1. Draft of SSES OPD/FI P
- 2. Training
- 3. Portable (FLEX) equipment maintenance and testing
Proposed Schedule Onsite Day 1, Monday, December 8, 2014 0800 Check in at site; Badging; Dosimetry 1000 Entrance meeting 1015 Licensee presentation of strategies 1200 Lunch 1300 Licensee presentation of strategies (continued) 1430 NRC Audit Team Activities:
- Technical area break-out discussions between NRC and licensee staff in the areas of reactor systems, electrical, balance-of-plant/structures, SFPI, and others
- Review documents relating to open or confirmatory items, RAis, codes, analyses, etc.
- NRC Mitigating Strategies/SFPI walk-throughs with licensee 1630 Team lead daily debrief/next day planning with licensee Onsite Day 2, Tuesday, December 9, 2014 0800 Continue NRC Audit Team Activities 1200 Lunch 1300 Continue NRC Audit Team Activities 1630 Team lead daily debrief/next day planning with licensee Onsite Day 3, Wednesday, December 10, 2014 0800 Continue NRC Audit Team Activities 1200 Lunch 1300 Continue NRC Audit Team Activities 1630 Team lead daily debrief/next day planning with licensee
Onsite Day 4, Thursday, December 11, 2014 0800 Continue NRC Audit Team Activities 1200 Lunch 1300 NRC Audit Team meeting 1430 NRC/Licensee pre-exit meeting 1700 NRC/Licensee exit meeting 1730 Audit closeout/departure
T. Rausch If you have any questions, please contact me at 301-415-3204 or by e-mail at John.Hughey@nrc.gov.
Sincerely, IRA/
John D. Hughey, Project Manager Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos.: 50-387 and 50-388
Enclosure:
Audit plan cc w/encl: Distribution via Listserv DISTRIBUTION:
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