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| number = ML15301A093 | | number = ML15301A093 | ||
| issue date = 10/30/2015 | | issue date = 10/30/2015 | ||
| title = | | title = Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 | ||
| author name = Boska J | | author name = Boska J | ||
| author affiliation = NRC/NRR/JLD | | author affiliation = NRC/NRR/JLD | ||
| addressee name = | | addressee name = | ||
| Line 13: | Line 13: | ||
| document type = Audit Plan, Letter | | document type = Audit Plan, Letter | ||
| page count = 10 | | page count = 10 | ||
| project = TAC: | | project = TAC:MF0737, TAC:MF0744 | ||
| stage = Other | | stage = Other | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 30, 2015 Vice President, Operations Entergy Nuclear Operations, Inc. | ||
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 | |||
==SUBJECT:== | ==SUBJECT:== | ||
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 -PLAN FOR THE ONSITE Au°DIT REGARDING IMPLEMENTATION OF MITIGATING STRATEGIES AND RELIABLE SPENT FUEL POOL INSTRUMENTATION RELATED TO ORDERS EA-12-049 AND EA-12-051 (TAC NOS. MF0744 AND MF0737) | INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - PLAN FOR THE ONSITE Au°DIT REGARDING IMPLEMENTATION OF MITIGATING STRATEGIES AND RELIABLE SPENT FUEL POOL INSTRUMENTATION RELATED TO ORDERS EA-12-049 AND EA-12-051 (TAC NOS. MF0744 AND MF0737) | ||
==Dear Sir or Madam:== | ==Dear Sir or Madam:== | ||
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. | |||
ML13239A238, ML13247A031, ML14070A447, ML14251A226, ML15065A123, and | 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 1O 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. ML13079A348), Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted its OIP for Indian Point Nuclear Generating Unit Nos. 2 and 3 (Indian Point, IP2 and IP3) in response to Order EA-12-049. By letters dated August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos. ML13247A032, ML14070A365, ML14251A227, ML15069A028, and ML15246A119, respectively), Entergy submitted its first five 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 Indian Point interim staff evaluation (ISE) (ADAMS Accession No. ML13337A594) and continues with in-office and onsite portions of this audit. The NRC's onsite audit for IP3 was conducted the week of October 27, 2014, and the audit report was issued on December 9, 2014 (ADAMS Accession No. ML14335A642). | |||
By letter dated February 27, 2013 (ADAMS Accession No. ML13072A082), the licensee submitted its OIP for Indian Point in response to Order EA-12-051. By letter dated June 25, 2013 (ADAMS Accession No. ML13169A127), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated August 20, 2013, August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos. | |||
ML13239A238, ML13247A031, ML14070A447, ML14251A226, ML15065A123, and ML15251A235, respectively), the licensee submitted its RAI responses and first five six-month updates to the OIP. The NRC staff's review led to the issuance of the Indian Point ISE and RAI dated November 8, 2013 (ADAMS Accession No. ML13298A805). 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. | |||
This document outlines the on-site 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 IP2 in accordance with the enclosed audit plan from November 30-December 3, 2015. | |||
If you have any questions, please contact me at 301-415-2901 or by e-mail at John.Boska@nrc.gov. | |||
Sincerely, hn Beska, Senior Project Manager rders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No.: 50-24 7 | |||
==Enclosure:== | ==Enclosure:== | ||
Audit plan cc w/encl: Distribution via Listserv | |||
Audit plan cc w/encl: Distribution via Listserv | |||
Audit Plan Indian Point Nuclear Generating Unit No. 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 (1 O CFR) Part 50 to submit for review their 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. ML13079A348), Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted its OIP for Indian Point Nuclear Generating Unit Nos. 2 and 3 (Indian Point, IP2 and IP3) in response to Order EA-12-049. By letters dated August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos. ML13247A032, ML14070A365, ML14251A227, ML15069A028, and ML15246A119, respectively), Entergy submitted its first five 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). The purpose of the staff's audit is to determine the extent to which the licensees are proceeding on a path towards successful implementation of the actions needed to achieve full compliance with the order. This audit process led to the issuance of the Indian Point interim staff evaluation (ISE) | |||
(ADAMS Accession No. ML13337A594) and continues with in-office and onsite portions of this audit. The NRC's onsite audit for IP3 was conducted the week of October 27, 2014, and the audit report was issued on December 9, 2014 (ADAMS Accession No. ML14335A642). | |||
By letter dated February 27, 2013 (ADAMS Accession No. ML13072A082), the licensee submitted its OIP for Indian Point in response to Order EA-12-051. By letter dated June 25, 2013 (ADAMS Accession No. ML13169A127), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated August 20, 2013, August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos. | |||
ML13239A238, ML13247A031, ML14070A447, ML14251A226, ML15065A123, and ML15251A235 respectively), the licensee submitted its RAI responses and first five six-month updates to the OIP. The NRC staff's review led to the issuance of the Indian Point ISE and RAI dated November 8, 2013 (ADAMS Accession No. ML13298A805). By letter dated March 26, Enclosure | |||
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 (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. | |||
This document outlines the on-site 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)/Final Integrated 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 Project 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 usually 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." On-site audits for subsequent units at a site will be on an as-needed basis. Although an onsite audit was completed for IP3, the licensee was not prepared at that time to discuss the strategies for order compliance for IP2. Therefore, the NRC staff determined that an additional onsite audit for IP2 was necessary. | |||
The purpose of the audits is to obtain and review information responsive to the Indian Point 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: | The purpose of the audits is to obtain and review information responsive to the Indian Point 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); | * Onsite review and discussion for the basis and approach for detailed analysis and calculations (Orders EA-12-049, EA-12-051); | ||
| Line 34: | Line 58: | ||
* Storage, protection, access, and deployment feasibility and practicality for onsite portable equipment (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 National SAFER Response Center (NSRC) provided equipment (Order EA-12-049); and | * Evaluation of staging, access, and deployment of offsite resources to include National SAFER Response Center (NSRC) provided equipment (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 | * 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 Tearn Lead and Project Manaqer John Boska Technical Support Kerby Scales Technical Support On Yee Technical Support KhoiNguyen Technical Support Joshua Miller LOGISTICS The audit will be conducted onsite at Indian Point from November 30 to December 3, 2015. | |||
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 | INFORMATION NEEDS | ||
* Materials/documentation provided in responses to open or confirmatory items and RAls in the ISEs; | * Materials/documentation provided in responses to open or confirmatory items and RAls in the ISEs; | ||
* OPD/FIP (current version), operator procedures, FLEX Support Guidelines (FSGs), operator training plans, NSRC (SAFER) Indian Point Response Plan; and | * OPD/FIP (current version), operator procedures, FLEX Support Guidelines (FSGs), | ||
* Materials/documentation for staff audit questions and/or licensee OIP identified open items as listed in the Part 2 below To provide supplemental input to the ongoing audit of documents submitted to the NRC and made available via e-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 RAls 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. | operator training plans, NSRC (SAFER) Indian Point Response Plan; and | ||
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 8. Walk-through of the procedures for electrical load shed, with an operator who would perform this procedure during an event demonstrating the steps needed to perform the load shed. Part 2 -Specific Technical Review Items: During the visit, the following audit items will be addressed from the licensee's ISEs (open items (01), confirmatory items (Cl), and SFPI RAls); audit question list (AQ); licensee OIP, as supplemented, open items; and draft safety evaluation (SE) additional questions. Please provide documents or demonstrations as needed to respond to each item. Part 3 -Specific Topics for Discussion: 1. Draft of Indian Point OPD/FIP 2. Reactor systems analyses to include a discussion of applicability to WCAP-17601-P, boron mixing, WCAP-17792-P, and Nuclear Safety Advisory Letter (NSAL) 14-1 3. Training 4. Portable (FLEX) equipment maintenance and testing 5. NSRC (SAFER) Response Plan for Indian Point 6. The licensee's plan for coordination with New York State authorities for delivery of Phase 3 FLEX equipment. | * Materials/documentation for staff audit questions and/or licensee OIP identified open items as listed in the Part 2 below To provide supplemental input to the ongoing audit of documents submitted to the NRC and made available via e-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 RAls 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: | ||
Proposed Schedule Onsite Day 1, Monday, November 30, 2015 0800 NRC team arrives at site; Badging; Dosimetry, Technical discussions in Generation Support Building 1000 Entrance meeting 1030 Licensee presentation of strategies 1200 Lunch Onsite Day 2, Tuesday, December 1, 2015 0800 NRC Mitigating Strategies/SFPI walk-throughs with licensee 1200 Lunch 1300 NRC Audit Team Activities: | 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 | |||
: 8. Walk-through of the procedures for electrical load shed, with an operator who would perform this procedure during an event demonstrating the steps needed to perform the load shed. | |||
Part 2 - Specific Technical Review Items: | |||
During the visit, the following audit items will be addressed from the licensee's ISEs (open items (01), confirmatory items (Cl), and SFPI RAls); audit question list (AQ); licensee OIP, as supplemented, open items; and draft safety evaluation (SE) additional questions. Please provide documents or demonstrations as needed to respond to each item. | |||
Part 3 - Specific Topics for Discussion: | |||
: 1. Draft of Indian Point OPD/FIP | |||
: 2. Reactor systems analyses to include a discussion of applicability to WCAP-17601-P, boron mixing, WCAP-17792-P, and Nuclear Safety Advisory Letter (NSAL) 14-1 | |||
: 3. Training | |||
: 4. Portable (FLEX) equipment maintenance and testing | |||
: 5. NSRC (SAFER) Response Plan for Indian Point | |||
: 6. The licensee's plan for coordination with New York State authorities for delivery of Phase 3 FLEX equipment. | |||
Proposed Schedule Onsite Day 1, Monday, November 30, 2015 0800 NRC team arrives at site; Badging; Dosimetry, Technical discussions in Generation Support Building 1000 Entrance meeting 1030 Licensee presentation of strategies 1200 Lunch Onsite Day 2, Tuesday, December 1, 2015 0800 NRC Mitigating Strategies/SFPI walk-throughs with licensee 1200 Lunch 1300 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 | * 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, RAls, codes, analyses, etc. | * Review documents relating to open or confirmatory items, RAls, codes, analyses, etc. | ||
* Plant walkdowns 1600 NRC Audit Team meeting 1630 Team lead daily debrief/next day planning with licensee Onsite Day 3, Wednesday, December 2, 2015 0800 Continue NRC Audit Team Activities 0900 NRC Mitigating Strategies/SFPI walk-throughs with licensee: 1200 Lunch 1300 Continue NRC Audit Team Activities 1600 NRC Audit Team meeting 1630 Team lead daily debrief/next day planning with licensee Onsite Day 4, Thursday, December 3, 2015 0800 Continue NRC Audit Team Activities 1200 Lunch 1300 NRC Audit Team meeting 1400 NRG/Licensee pre-exit meeting 1500 NRG/Licensee exit meeting 1600 Audit closeout/departure | * Plant walkdowns 1600 NRC Audit Team meeting 1630 Team lead daily debrief/next day planning with licensee Onsite Day 3, Wednesday, December 2, 2015 0800 Continue NRC Audit Team Activities 0900 NRC Mitigating Strategies/SFPI walk-throughs with licensee: | ||
1200 Lunch 1300 Continue NRC Audit Team Activities 1600 NRC Audit Team meeting 1630 Team lead daily debrief/next day planning with licensee | |||
Onsite Day 4, Thursday, December 3, 2015 0800 Continue NRC Audit Team Activities 1200 Lunch 1300 NRC Audit Team meeting 1400 NRG/Licensee pre-exit meeting 1500 NRG/Licensee exit meeting 1600 Audit closeout/departure | |||
ML13298A805). 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. | |||
This document outlines the on-site 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 IP2 in accordance with the enclosed audit plan from November 30-December 3, 2015. | |||
If you have any questions, please contact me at 301-415-2901 or by e-mail at John.Boska@nrc.gov. | |||
Sincerely, IRA/ | |||
John Beska, Senior Project Manager Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No.: 50-247 | |||
==Enclosure:== | ==Enclosure:== | ||
Audit plan | |||
}} | Audit plan cc w/encl: Distribution via Listserv DISTRIBUTION: | ||
See next page ADAMS Accession No. ML15301A093 *via email OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NRR/JLD/JCBB/BC(A)* | |||
NAME JBoska SLent BTitus DATE 10/30/2015 10/29/2015 10/30/2015 OFFICE NRR/JLD/JERB/BC* NRR/JLD/JOMB/BC(A) NRR/JLD/JOMB/PM NAME SBailey MHalter PBamford for JBoska DATE 10/30/2015 10/30/2015 10/30/2015}} | |||
Latest revision as of 08:10, 5 February 2020
| ML15301A093 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/30/2015 |
| From: | Boska J Japan Lessons-Learned Division |
| To: | Entergy Nuclear Operations |
| Boska, John, NRR/JLD 415-2901 | |
| References | |
| EA-12-049, EA-12-051, TAC MF0737, TAC MF0744 | |
| Download: ML15301A093 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 30, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - PLAN FOR THE ONSITE Au°DIT REGARDING IMPLEMENTATION OF MITIGATING STRATEGIES AND RELIABLE SPENT FUEL POOL INSTRUMENTATION RELATED TO ORDERS EA-12-049 AND EA-12-051 (TAC NOS. MF0744 AND MF0737)
Dear Sir or Madam:
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 1O 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. ML13079A348), Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted its OIP for Indian Point Nuclear Generating Unit Nos. 2 and 3 (Indian Point, IP2 and IP3) in response to Order EA-12-049. By letters dated August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos. ML13247A032, ML14070A365, ML14251A227, ML15069A028, and ML15246A119, respectively), Entergy submitted its first five 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 Indian Point interim staff evaluation (ISE) (ADAMS Accession No. ML13337A594) and continues with in-office and onsite portions of this audit. The NRC's onsite audit for IP3 was conducted the week of October 27, 2014, and the audit report was issued on December 9, 2014 (ADAMS Accession No. ML14335A642).
By letter dated February 27, 2013 (ADAMS Accession No. ML13072A082), the licensee submitted its OIP for Indian Point in response to Order EA-12-051. By letter dated June 25, 2013 (ADAMS Accession No. ML13169A127), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated August 20, 2013, August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos.
ML13239A238, ML13247A031, ML14070A447, ML14251A226, ML15065A123, and ML15251A235, respectively), the licensee submitted its RAI responses and first five six-month updates to the OIP. The NRC staff's review led to the issuance of the Indian Point ISE and RAI dated November 8, 2013 (ADAMS Accession No. ML13298A805). 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.
This document outlines the on-site 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 IP2 in accordance with the enclosed audit plan from November 30-December 3, 2015.
If you have any questions, please contact me at 301-415-2901 or by e-mail at John.Boska@nrc.gov.
Sincerely, hn Beska, Senior Project Manager rders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No.: 50-24 7
Enclosure:
Audit plan cc w/encl: Distribution via Listserv
Audit Plan Indian Point Nuclear Generating Unit No. 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 (1 O CFR) Part 50 to submit for review their 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. ML13079A348), Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted its OIP for Indian Point Nuclear Generating Unit Nos. 2 and 3 (Indian Point, IP2 and IP3) in response to Order EA-12-049. By letters dated August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos. ML13247A032, ML14070A365, ML14251A227, ML15069A028, and ML15246A119, respectively), Entergy submitted its first five 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). The purpose of the staff's audit is to determine the extent to which the licensees are proceeding on a path towards successful implementation of the actions needed to achieve full compliance with the order. This audit process led to the issuance of the Indian Point interim staff evaluation (ISE)
(ADAMS Accession No. ML13337A594) and continues with in-office and onsite portions of this audit. The NRC's onsite audit for IP3 was conducted the week of October 27, 2014, and the audit report was issued on December 9, 2014 (ADAMS Accession No. ML14335A642).
By letter dated February 27, 2013 (ADAMS Accession No. ML13072A082), the licensee submitted its OIP for Indian Point in response to Order EA-12-051. By letter dated June 25, 2013 (ADAMS Accession No. ML13169A127), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated August 20, 2013, August 27, 2013, February 27, 2014, August 27, 2014, February 27, 2015, and August 28, 2015 (ADAMS Accession Nos.
ML13239A238, ML13247A031, ML14070A447, ML14251A226, ML15065A123, and ML15251A235 respectively), the licensee submitted its RAI responses and first five six-month updates to the OIP. The NRC staff's review led to the issuance of the Indian Point ISE and RAI dated November 8, 2013 (ADAMS Accession No. ML13298A805). By letter dated March 26, Enclosure
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 (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.
This document outlines the on-site 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)/Final Integrated 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 Project 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 usually 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." On-site audits for subsequent units at a site will be on an as-needed basis. Although an onsite audit was completed for IP3, the licensee was not prepared at that time to discuss the strategies for order compliance for IP2. Therefore, the NRC staff determined that an additional onsite audit for IP2 was necessary.
The purpose of the audits is to obtain and review information responsive to the Indian Point 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 National SAFER Response Center (NSRC) provided equipment (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 Tearn Lead and Project Manaqer John Boska Technical Support Kerby Scales Technical Support On Yee Technical Support KhoiNguyen Technical Support Joshua Miller LOGISTICS The audit will be conducted onsite at Indian Point from November 30 to December 3, 2015.
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 RAls in the ISEs;
operator training plans, NSRC (SAFER) Indian Point Response Plan; and
- Materials/documentation for staff audit questions and/or licensee OIP identified open items as listed in the Part 2 below To provide supplemental input to the ongoing audit of documents submitted to the NRC and made available via e-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 RAls 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
- 8. Walk-through of the procedures for electrical load shed, with an operator who would perform this procedure during an event demonstrating the steps needed to perform the load shed.
Part 2 - Specific Technical Review Items:
During the visit, the following audit items will be addressed from the licensee's ISEs (open items (01), confirmatory items (Cl), and SFPI RAls); audit question list (AQ); licensee OIP, as supplemented, open items; and draft safety evaluation (SE) additional questions. Please provide documents or demonstrations as needed to respond to each item.
Part 3 - Specific Topics for Discussion:
- 1. Draft of Indian Point OPD/FIP
- 2. Reactor systems analyses to include a discussion of applicability to WCAP-17601-P, boron mixing, WCAP-17792-P, and Nuclear Safety Advisory Letter (NSAL) 14-1
- 3. Training
- 4. Portable (FLEX) equipment maintenance and testing
- 6. The licensee's plan for coordination with New York State authorities for delivery of Phase 3 FLEX equipment.
Proposed Schedule Onsite Day 1, Monday, November 30, 2015 0800 NRC team arrives at site; Badging; Dosimetry, Technical discussions in Generation Support Building 1000 Entrance meeting 1030 Licensee presentation of strategies 1200 Lunch Onsite Day 2, Tuesday, December 1, 2015 0800 NRC Mitigating Strategies/SFPI walk-throughs with licensee 1200 Lunch 1300 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, RAls, codes, analyses, etc.
- Plant walkdowns 1600 NRC Audit Team meeting 1630 Team lead daily debrief/next day planning with licensee Onsite Day 3, Wednesday, December 2, 2015 0800 Continue NRC Audit Team Activities 0900 NRC Mitigating Strategies/SFPI walk-throughs with licensee:
1200 Lunch 1300 Continue NRC Audit Team Activities 1600 NRC Audit Team meeting 1630 Team lead daily debrief/next day planning with licensee
Onsite Day 4, Thursday, December 3, 2015 0800 Continue NRC Audit Team Activities 1200 Lunch 1300 NRC Audit Team meeting 1400 NRG/Licensee pre-exit meeting 1500 NRG/Licensee exit meeting 1600 Audit closeout/departure
ML13298A805). 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.
This document outlines the on-site 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 IP2 in accordance with the enclosed audit plan from November 30-December 3, 2015.
If you have any questions, please contact me at 301-415-2901 or by e-mail at John.Boska@nrc.gov.
Sincerely, IRA/
John Beska, Senior Project Manager Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No.: 50-247
Enclosure:
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See next page ADAMS Accession No. ML15301A093 *via email OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NRR/JLD/JCBB/BC(A)*
NAME JBoska SLent BTitus DATE 10/30/2015 10/29/2015 10/30/2015 OFFICE NRR/JLD/JERB/BC* NRR/JLD/JOMB/BC(A) NRR/JLD/JOMB/PM NAME SBailey MHalter PBamford for JBoska DATE 10/30/2015 10/30/2015 10/30/2015