JAFP-17-0063, Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)

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Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
ML17180A951
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/29/2017
From: Joseph Pacher
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
EA-13-109, JAFP-17-0063
Download: ML17180A951 (18)
v • d • e


Text

Exelon Generation Company, LLC James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-349-6024 Fax 315-349-6480 Joseph E. Pacher Site Vice President - JAF JAFP-17-0063 June 29, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Exelon - James A. FitzPatrick Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059

Reference:

1. NRC Order, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, EA-13-109, dated June 6, 2013
2. NRC Interim Staff Guidance, Compliance with Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, Revision 0, JLD-ISG-2013-02, dated November 2013
3. NRC Interim Staff Guidance, Compliance with Phase 2 of Order EA 109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions, Revision 0, JLD-ISG-2015-01, dated April 2015
4. NEI document, Industry Guidance for Compliance with NRC Order EA-13-109: BWR Mark I & II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, Revision 1, NEI 13-02, dated April 2015
5. ENOI letter, James A. FitzPatrick Overall Integrated Plan In Response To June 6, 2013 Commission Order Modifying License With Regard To Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), JAFP-14-0075, dated June 30, 2014
6. ENOI letter, James A. FitzPatrick Phase 2 Overall Integrated Plan In Response To June 6, 2013 Commission Order Modifying License With Regard To Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), JAFP 0149, dated December 29, 2015

JAFP-17-0063 Page 2 of 2

Dear Sir or Madam :

On June 6, 2013, the Nuclear Regulatory Commission ("NRC" or "Commission") issued Order EA-13-109 to James A. FitzPatrick Nuclear Power Plant (JAF) [Reference 1]. EA-13-109 directs JAF to install a reliable hardened venting capability in accordance with the requirements detailed in the Order, including:

A Phase 1 Overall Integrated Plan pursuant to Section IV, Condition D.1. Reference 2 endorses industry guidance document NEI 13-02, Revision 0 with clarifications and exceptions identified in Reference 2. Reference 5 provided the JAF's Phase 1 Overall Integrated Plan.

A Phase 2 Overall Integrated Plan pursuant to Section IV, Condition D.2. Reference 3 endorses industry guidance document NEI 13-02, Revision 1 [Reference 4]. Reference 6 provided the JAF's Phase 2 Overall Integrated Plan.

Submission of a status report at six-month intervals following submittal of the Overall Integrated Plan phase 1 [Reference 5] pursuant to Section IV, Condition D.3. NEI 13-02

[Reference 4] provides direction regarding the content of the status reports.

The purpose of this letter is to provide the sixth six-month status report, which delineates progress made in implementing the requirements of EA-13-109. Attachment 1 provides an update to milestone status, including any changes to the compliance method, schedule, or possible need for relief and the basis. The status update for responses to Phase 1 and 2 Interim Staff Evaluation Open Items as part of Attachment 1 is provided in Attachments 2 and 3.

This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact Mr. William C. Drews, Regulatory Assurance Manager, at 315-349-6562.

I declare under penalty of perjury that the foregoing is true and correct; executed on June 29, 2017.

oseph E. Pacher Site Vice President JEP/WCD/mh : James A. FitzPatrick (JAF) Nuclear Power Plant's Sixth Six Month Status Report for the Implementation of Order EA-13-109, "Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" 2: Response to Phase 1 Interim Staff Evaluation Open Items 3: Response to Phase 2 Interim Staff Evaluation Open Items cc: Director, Office of Nuclear Reactor NRC Project Manager Regulation NYSPSC NRC Regional Administrator NYSE RDA NRC Resident Inspector

JAFP-17-0063 Attachment 1 James A. FitzPatrick (JAF) Nuclear Power Plants Sixth Six Month Status Report for the Implementation of Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (4 Pages)

JAFP-17-0063 Attachment 1 James A. FitzPatrick (JAF) Nuclear Power Plants Sixth Six Month Status Report for the Implementation of Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions 1 Introduction JAF developed a Phase 1 Overall Integrated Plan (Reference 2) and a Phase 2 Overall Integrated Plan (Reference 3), documenting the installation of a Hardened Containment Vent System (HCVS) that provides a reliable hardened venting capability in response to NRC Order Number EA-13-109 (Reference 1). This attachment provides an update of milestone accomplishments since submittal of the Phase 1 Overall Integrated Plan, Phase 2 Overall Integrated Plan, and the subsequent Six Month Status Reports, including any changes to the compliance method, schedule, or need for relief / relaxation and the basis, if any.

2 Milestone Accomplishments The following milestone(s) have been completed since the development of the Phase 1 Overall Integrated Plan (Reference 2) and Phase 2 Overall Integrated Plan (Reference 3), and are current as of June 1, 2017. (See Section 3)

Submitted Sixth 6 Month Status Report by letter JAFP-17-0063.

While not listed as a specific milestone, the required HCVS offline (outage) installation activities were completed in February 2017.

3 Milestone Schedule Status The following provides an update to Part 5 of the Phase 1 Overall Integrated Plan (Reference 2) and Part 5 of the Phase 2 Overall Integrated Plan (Reference 3). It provides the status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.

JAF - Phase 1 and Phase 2 Specific Milestone Schedule Target Milestone Completion Activity Status Comments Date Phase 1 Hold preliminary / conceptual design Jan 2014 Complete meeting Submit Overall Integrated Implementation Jun 2014 Complete Plan Submit 6 Month Status Report Dec 2014 Complete Submit 6 Month Status Report Jun 2015 Complete Design Engineering On-site/Complete Dec 2015 Complete Submit 6 Month Status Report Dec 2015 Complete Submit 6 Month Status Report Jun 2016 Complete Submit 6 Month Status Report Dec 2016 Complete Complete with Submit 6 Month Status Report Jun 2017 this submittal Page 1 of 4

JAFP-17-0063 Attachment 1 James A. FitzPatrick (JAF) Nuclear Power Plants Sixth Six Month Status Report for the Implementation of Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Target Milestone Completion Activity Status Comments Date Submit 6 Month Status Report Dec 2017 Not Started Operations Procedure Changes April 2018 Not Started Developed Site Specific Maintenance Procedure April 2018 Not Started Developed HCVS Installation Complete May 2018 Started Procedure Changes Active Jun 2018 Not Started Walk Through Demonstration/Functional Jun 2018 Not Started Test Training Complete Jun 2018 Not Started HCVS Phase 1 Compliance Jun 2018 Not Started Submit Completion Report Nov 2018* Not Started Phase 2 Hold preliminary/conceptual design Oct 2015 Complete meeting Submit Overall Integrated Implementation Dec 2015 Complete Plan Submit 6 Month Status Report Jun 2016 Complete Submit 6 Month Status Report Dec 2016 Complete Complete with Submit 6 Month Status Report Jun 2017 this submittal Design Engineering On-site/Complete Oct 2017* Started Submit 6 Month Status Report Dec 2017 Not Started Operations Procedure Changes Jun 2018 Not Started Developed Site Specific Maintenance Procedure Jun 2018 Not Started Developed Training Complete Jun 2018 Not Started Submit 6 Month Status Report Jun 2018 Not Started Implementation Outage Sep 2018 Not Started Walk Through Demonstration/Functional Sep 2018 Not Started Test Procedure Changes Active Sep 2018 Not Started Submit Completion Report Nov 2018 Not Started

  • Date changed for this six month update Page 2 of 4

JAFP-17-0063 Attachment 1 James A. FitzPatrick (JAF) Nuclear Power Plants Sixth Six Month Status Report for the Implementation of Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions 4 Changes to Compliance Method The JAF design changes to the HCVS will continue to meet the requirements of Order EA-13-109 (Reference 1). There is a clarification to the information presented in the JAF HCVS OIPs based on the final detailed design. The following clarification is described based on the applicable Order section items as well as the applicable sections in the Overall Integrated Plan.

Phase 1 Phase 1 Overall Integrated Plan (Reference 2): Part 2 [BDBEE Venting, Greater than 24 Hour Coping Detail; HCVS Support Equipment Functions, BDBEE Venting, Severe Accident Venting]; Order EA-13-109 (Reference 1) Item 1.2.4, 1.2.8, 1.29 The HCVS battery charger will be normally powered from a 120V AC Non-safety related lighting panel via standard receptacle in lieu of a 600V AC power source and transformer repowered by a FLEX DG (as stated in the OIP). The battery charger will be repowered within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> via extension cords from the FLEX DG. This compliance method meets NEI 13-02.

Phase 2 There is no change to the compliance method that meets NEI 13-02 (Reference 4).

5 Need for Relief / Relaxation and Basis for the Relief / Relaxation On January 9, 2017, James A. FitzPatrick received approval for an extension until June 30, 2018 to comply with requirements for implementation of Phase 1 (wetwell) vent at JAF (Reference 9). JAF expects to comply with the Phase 2 order implementation date and no relief/relaxation for Phase 2 is required at this time.

6 Open Items from Overall Integrated Plan and Interim Staff Evaluation The following tables provide a summary of the open items documented in the Phase 1 and Phase 2 Overall Integrated Plan and the status of each item.

Overall Integrated Plan Phase 1 & 2 Status Open Items Phase 1 None Phase 2 Complete hydraulic analysis of diesel fire pump for Started SAWA / SAWM flowrates Identify and evaluate severe accident conditions for Started Phase 2 manual actions.

The FLEX Engineering Change (EC 52736) has not Complete; been completed; therefore, any reference to this Approved information is considered unverified. December 2016 Page 3 of 4

JAFP-17-0063 Attachment 1 James A. FitzPatrick (JAF) Nuclear Power Plants Sixth Six Month Status Report for the Implementation of Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Open items from the Phase 1 Interim Staff Evaluation (Reference 7) are provided in Attachment 2 to this letter. Open items from the Phase 2 Interim Staff Evaluation (Reference 8) are provided in Attachment 3 to this letter.

7 Interim Staff Evaluation Impacts There are no potential impacts to the Phase 1 or 2 Interim Staff Evaluation (Reference 7 and 8) identified at this time.

8 References The following references support the updates to the Phase 1 & 2 Overall Integrated Plan described in this attachment.

1. NRC Order Number EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions dated June 6, 2013 (ML13143A321).
2. Letter JAFP-14-0075, James A. FitzPatrick Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated June 30, 2014 (ML14181B117).
3. Letter JAFP-15-0149, James A. FitzPatrick Phase 2 Overall Integrated Plan In Response To June 6, 2013 Commission Order Modifying License With Regard To Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated December 29, 2015 (ML15365A593).
4. NEI 13-02, Industry Guidance for Compliance with Order EA-13-109: BWR Mark I & II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, Revision 1, dated April 2015 (ML15113B318).
5. NRC Interim Staff Guidance, JLD-ISG-2013-02, Compliance with Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, Revision 0, dated November 2013 (ML13304B836).
6. NRC Interim Staff Guidance, JLD-ISG-2015-01, Compliance with Phase 2 of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions, Revision 0, dated April 2015 (ML15104A118)
7. James A. FitzPatrick Nuclear Power Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 1 of Order EA-13-109 (Severe Accident Capable Hardened Vents), dated February 12, 2015, (ML15007A090).
8. James A. FitzPatrick Nuclear Power Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents), dated December 16, 2016, (ML16343B030).
9. NRC letter, James A. FitzPatrick Nuclear Power Plant - Relaxation of the Schedule Requirements for Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operations Under Severe Accident Conditions (CAC No. MF4464), dated January 9, 2017, (ML16336A754).

Page 4 of 4

JAFP-17-0063 Attachment 2 Response to Phase 1 Interim Staff Evaluation Open Items (5 Pages)

JAFP-17-0063 Attachment 2 Response to Phase 1 Interim Staff Evaluation Open Items Item Phase 1 Interim Staff Evaluation Open Status

  1. Items Make available for NRC staff audit analyses COMPLETE demonstrating that HCVS has the capacity to James A. FitzPatrick Nuclear Power Plant (JAF) is capable of (a) venting the vent the steam/energy equivalent of one (1) equivalent of (1) percent of licensed/rated thermal power and (b) the Torus is percent of licensed/rated thermal power capable of absorbing the decay heat for the first three hours to maintain the (unless a lower value is justified), and that the integrity of primary containment.

suppression pool and the HCVS together are ISE-1 able to absorb and reject decay heat, such Auditable analyses to justify the capability of the Torus, as described in this action, that following a reactor shutdown from full have been issued as calculation JAF-CALC-14-00015 (part of the approved design power containment pressure is restored and change package EC 52721) and calculation JAF-CALC-15-00026 (part of the then maintained below the primary approved design change package EC 58158). For additional discussion, see EC containment design pressure and the primary 52721 Topic Notes Section 3.1.7 entitled Hydraulic Requirements.

containment pressure limit.

COMPLETE The Hardened Containment Venting System (HCVS) piping from the Torus to the discharge above the Reactor Building (RB) Roof is designed to be seismically rugged as supported by calculations JAF-CALC-14-00017, JAF-CALC-15-00008, Make available for NRC staff audit the seismic JAF-CALC-15-00033, and JAF-CALC-14-00016 (part of the approved design ISE-2 and tornado missile final design criteria for the change package EC 52721).

HCVS stack.

Protection from tornado missiles is acceptable in accordance with evaluations based on the HCVS-WP-04 guidance. See EC 52721 Topic Notes Section 3.1.3 entitled Structural Requirements. Specifically, see the associated subsection entitled Tornado Missiles.

Page 1 of 5

JAFP-17-0063 Attachment 2 Response to Phase 1 Interim Staff Evaluation Open Items Item Phase 1 Interim Staff Evaluation Open Status

  1. Items COMPLETE The HCVS Battery System will support a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation. Refer to EC 52721 Topic Notes, Section 3.1.4 entitled "Electrical Requirements."

Make available for NRC staff audit the final Specifically, refer to the subsections entitled "Battery Selection and Sizing," "Battery sizing evaluation for HCVS batteries/battery ISE-3 Charger Selection and Sizing," and the associated Engineering Change (EC) charger including incorporation into FLEX DG attachment, P2e Sequence No. 6.003.

loading calculation.

The HCVS battery load has been incorporated into the FLEX Disel Generator (DG) via approved EC 52736 (FLEX Strategy) and associated calculation JAF-CALC 00031.

COMPLETE The HCVS pneumatic system design sizing will be capable of 12 cycles in the first Make available for NRC staff audit 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The sizing of the nitrogen motive force and purge systems is provided in documentation of the HCVS nitrogen calculations JAF-CALC-15-00013 and JAF-CALC-15-00038, respectively (part of ISE-4 pneumatic system design including sizing and the approved design change package EC 52721). For additional discussion, see location. EC 52721 Topic Notes Section 3.1.6.3 entitled Cross Flow & Hydrogen Detonation. Specifically, see the associated subsection entitled HCVS Pipeline Protection.

COMPLETE The JAF strategy for preventing hydrogen detonation and deflagration beyond the Provide a description of the final design of the final isolation point (valve) is a nitrogen purge system. Concurrent with closing the ISE-5 HCVS to address hydrogen detonation and isolation valve, the purge system will be initiated to purge the vented fluid from the deflagration. HCVS pipeline. For additional discussion, see EC 52721 Topic Notes Section 3.1.6.3 entitled Cross Flow & Hydrogen Detonation. Specifically, see the associated subsection entitled HCVS Pipeline Protection.

Page 2 of 5

JAFP-17-0063 Attachment 2 Response to Phase 1 Interim Staff Evaluation Open Items Item Phase 1 Interim Staff Evaluation Open Status

  1. Items COMPLETE At JAF, the interfaces between the RB and the HCVS pipeline are limited to Provide a description of the strategies for normally closed, small bore drain and instrument valves minimizing the hydrogen hydrogen control that minimizes the potential gas migration and ingress into the Reactor Building. In addition, migration to the ISE-6 Standby Gas Treatment System is minimized through the use of existing Class VI for hydrogen gas migration and ingress into the reactor building or other buildings. Motor Operator Valves (MOV) that will be leak tested in accordance with NEI 13-02.

For additional discussion, see EC 52721 Topic Notes Section 3.1.6.3 entitled Cross Flow & Hydrogen Detonation. Specifically, see the associated subsection entitled Interconnecting Systems.

STARTED The required instrumentation and controls (existing and new) are identified as part Make available for NRC staff audit of the JAF Overall Integrated Plan (OIP), Part 2. The qualification of the equipment descriptions of all instrumentation and controls ISE-7 has been described within the approved design change package EC 52721; (existing and planned) necessary to implement however, additional documentation must be supplied by vendors before this item is this order including qualification methods.

completed.

Upon completion, the evaluations will be posted to ePortal.

STARTED Make available for NRC staff audit The qualification of the equipment has been described within the approved design ISE-8 documentation of a seismic qualification change package EC 52721; however, additional documentation must be supplied evaluation of HCVS components. by vendors before this item is completed.

Upon completion, the evaluations will be posted to ePortal.

Page 3 of 5

JAFP-17-0063 Attachment 2 Response to Phase 1 Interim Staff Evaluation Open Items Item Phase 1 Interim Staff Evaluation Open Status

  1. Items Make available for NRC staff audit the STARTED descriptions of local conditions (temperature, The approved design change package EC 52721 describes the conditions and radiation and humidity) anticipated during capability of the equipment to function within the stated conditions. The qualification ELAP and severe accident for the components of the equipment has been described within the approved design change package (valves, instrumentation, sensors, transmitters, ISE-9 EC 52721; however, additional documentation must be supplied by vendors before indicators, electronics, control devices, etc.)

this item is completed.

required for HCVS venting including confirmation that the components are capable Upon completion, the evaluations will be posted to ePortal.

of performing their functions during ELAP and severe accident conditions.

COMPLETE Make available for NRC staff audit At JAF, the existing Primary Containment Isolation Valves (PCIV) (27AOV-117 and documentation of an evaluation verifying the -118) that will be part of the EA-13-109 HCVS flow path are currently a part of the existing containment isolation valves, relied Generic Letter (GL) 89-16 containment hardened pipe flow path. Calculation ISE-10 upon for the HCVS, will open under the 14620.9011-US(N)-004 "Suppression Chamber (20") & Drywell (24") Vent & Purge maximum expected differential pressure Butterfly Valves based on RELAP 5/MOD2 56 psig and 62 psig Results" concludes during BDBEE and severe accident wetwell the valves can be opened against the maximum expected differential pressure ventinq. during an Order EA-13-109 event, the primary containment pressure limit of 62 psig.

Make available for NRC staff audit COMPLETE documentation that demonstrates adequate JAF utilizes the site Ultra-High Frequency (UHF) security radio system (Ref. EC communication between the remote HCVS 53903) to communicate between the Main Control Room (MCR) and the operator at ISE-11 operation locations and HCVS decision the HCVS control location. This communication method is the same as accepted in makers during ELAP and severe accident Order EA-12-049. These items will be powered and remained powered using the conditions. same methods as evaluated under EA-12-049 for the period of sustained operation.

Page 4 of 5

JAFP-17-0063 Attachment 2 Response to Phase 1 Interim Staff Evaluation Open Items Item Phase 1 Interim Staff Evaluation Open Status

  1. Items COMPLETE Make available for NRC staff audit an The approved design change package EC 52721, along with supporting evaluation of temperature and radiological calculations, has identified the anticipated conditions during Extended Loss of AC ISE-12 conditions to ensure that operating personnel Power (ELAP) and a Severe Accident and confirm the capability for operating can safely access and operate controls and personnel to safely access and operate controls and support equipment. For support equipment. additional discussion, see EC 52721 Topic Notes Section 3.1.11.3 entitled HCVS Manual Actions.

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JAFP-17-0063 Attachment 3 Response to Phase 2 Interim Staff Evaluation Open Items (4 Pages)

JAFP-17-0063 Attachment 3 Response to Phase 2 Interim Staff Evaluation Open Items Item Phase 2 Interim Staff Evaluation Status

  1. Open Items STARTED Temperature and Humidity The location of Severe Accident Water Addition (SAWA) equipment and controls including ingress and egress paths that are the same or similar as FLEX will be bounded by the FLEX evaluations for temperature and humidity.

Licensee to evaluate the SAWA equipment and controls, as well as Ingress and Egress the ingress and egress paths for ISE- For locations inside the Reactor Building between 1 and 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> when SAWA is being the expected severe accident 1 deployed, JAF has performed a preliminary quantitative evaluation of expected dose rates conditions (temperature, humidity, per HCVS-FAQ-12 and found the dose rates at deployment locations including radiation) for the sustained ingress/egress paths are acceptable.

operating period.

For locations outside the Reactor Building between 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 7 days when SAWA is being utilized, JAF has performed a preliminary quantitative evaluation of expected dose rates per HCVS-WP-02 and found the dose rates at deployment locations including ingress/egress paths are acceptable.

Upon completion, the evaluations will be posted to ePortal.

Page 1 of 4

JAFP-17-0063 Attachment 3 Response to Phase 2 Interim Staff Evaluation Open Items Item Phase 2 Interim Staff Evaluation Status

  1. Open Items STARTED Equipment and Controls Plant instrumentation for SAWA that is qualified to Regulatory Guide (RG) 1.97 or equivalent is considered qualified for the sustained operating period without further evaluation. The following plant instruments are qualified to RG 1.97:

Drywell Pressure: 27PI-115A1, 2 Drywell Pressure: 27PI-115B1, 2 Torus Water Level: 23LI-202A, B Licensee to demonstrate how Passive components that do not need to change state after initially establishing SAWA flow instrumentation and equipment do not require evaluations.

being used for SAWA and The following additional equipment performing an active SAWA/Sever Accident Water ISE- supporting equipment is capable Management (SAWM) function is considered for temperature and radiation effects:

2 to perform for the sustained operating period under the SAWA/SAWM flow instrument expected temperature and SAWA/SAWM pump (FLEX pump) radiological conditions. SAWA/SAWM generator (FLEX generator)

Active valves in SAWA flow path Temperature The location of SAWA equipment and controls that are the same or similar as FLEX will be bounded by the FLEX evaluations for temperature and humidity.

Radiation The in-progress Phase 2 detailed design will address equipment and controls inside and outside the Reactor Building between 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 7 days, when SAWA is being utilized.

Upon completion, the evaluations will be posted to ePortal.

Page 2 of 4

JAFP-17-0063 Attachment 3 Response to Phase 2 Interim Staff Evaluation Open Items Item Phase 2 Interim Staff Evaluation Status

  1. Open Items STARTED The wetwell vent has been designed and will be installed to meet NEI 13-02 Rev 1 guidance, which will ensure that it is adequately sized to prevent containment overpressure under severe accident conditions (Ref. JAF-CALC-14-00015).

The SAWM strategy will ensure that the wetwell vent remains functional for the period of sustained operation. JAF will follow the guidance (flow rate and timing) for SAWA/SAWM described in BWROG-TP-15-008 and BWROG-TP-15-011. These documents have been posted to the ePortal for NRC staff review.

The wetwell vent will be opened prior to exceeding the PCPL value of 62 PSIG. Therefore, Licensee to demonstrate that containment over pressurization is prevented without the need for a drywell vent.

containment failure as a result of ISE-overpressure can be prevented JAF is bounded by the reference plant analysis that shows the SAWM strategy is successful 3

without a drywell vent during in making it unlikely that a drywell vent is needed as demonstrated by the following table.

severe accident conditions.

Reference Plant James A. FitzPatrick Torus freeboard volume is 525,0002 Torus freeboard volume is preliminarily gallons determined to be 813,000 gallons SAWA flow is 500 GPM at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> SAWA flow is 361 GPM at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> followed followed by 100 GPM from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by 73 GPM from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> The above parameters for JAF compared to the reference plant that determine success of the SAWM strategy demonstrate that the reference plant values are bounding. Therefore, the SAWM strategy implemented at JAF makes it unlikely that a Drywell (DW) vent is needed to prevent containment overpressure related failure.

2 Peach Bottom available freeboard volume in gallons is estimated from nominal water level of 14.7 feet to 21 feet. 21 feet is the upper range of the wide range torus level instrument and the assumed loss of wetwell vent function. The Peach Bottom torus is 31 feet in diameter.

Page 3 of 4

JAFP-17-0063 Attachment 3 Response to Phase 2 Interim Staff Evaluation Open Items Item Phase 2 Interim Staff Evaluation Status

  1. Open Items COMPLETE Licensee to demonstrate that there is adequate communication JAF utilizes the site Ultra-High Frequency (UHF) security radio system (Ref. EC 53903) to between the primary HCVS communicate between the MCR and the operator at the SAWA/SAWM flow control location.

ISE- This communication method is the same as accepted in Order EA-12-049. These items will operating station and the operator 4

at the FLEX supply hose splitter be powered and remained powered using the same methods as evaluated under EA-12-049 valve during severe accident for the period of sustained operation.

conditions.

STARTED JAF will utilize a four inch size Seametrics AG2000 flowmeter. The flow meter will be deployed in the Diesel Fire Pump room which is part of the plant circulating water Screen House building which is located a substantial distance from the Hardened Containment Venting System (HCVS) vent line and is well shielded from the expected HCVS vent line dose.

For locations outside the Reactor Building between 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 7 days when SAWA is being utilized, JAF performed a qualitative evaluation of equipment and deployment locations and Licensee to demonstrate the confirmed they are protected by buildings with substantial shielding to minimize dose rates.

SAWA/SAWM flow The selected instrument is designed for the expected flow rate, temperature and pressure for ISE- SAWA over the period of sustained operation. The instrument qualification for pressure, instrumentation qualification for 5 temperature and flow provided in the table below is from the product technical data.

the expected environmental conditions. SAWA Flow Instrument Expected SAWA Parameter Range Qualification 12 - 1,000 GPM 73 - 361 GPM 10 - 130 °F Operating 40 - 119 °F

-40 to 158 °F Storage 0 - 150 PSI Working Pressure 0 - 143 PSIG Page 4 of 4

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