ML13289A248

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6.a.iii.l.a SQN Fukushima DG, Diesel Pumps/Tow Truck List, Docketed Letter
ML13289A248
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 10/28/2013
From: James Shea
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML13289A109 List: ... further results
References
EA-12-049
Download: ML13289A248 (6)
v • d • e


Text

L44 130228 002 Enclosure 1 Attachment 3 is to be withheld from public disclosure under 10 CFR 2.390. When separated from this submittal, this letter is decontrolled.

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 EA-12-049

  • February 28, 2013 10 CFR 2.202 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission
  • Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Tennessee Valley Authority (TV A) -Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses.

with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Sequoyah Nuclear Plant

References:

1. NRC Order Number EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12, 2012 (ML12054A735)
2. NRC Interim Staff Guidance 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," Revision 0, dated August 29, 2012 (ML12229A174)
3. NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide," Revision 0, dated August 2012 (ML12242A378)

4o:-better-frem-TVA-te-NRG, Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)," dated October 29, 2012 (ML12307A104)

Pnnted on recycled paper

*-**------

-*** ______ _. _____

U.S. Nuclear Regulatory Commission Page3 February 28, 2013 The information in the enclosure to this letter provides the SQN overall integrated plan for mitigation strategies using the guidance contained in Reference

3. The enclosed Integrated Plah is basecj on conceptual design information.

Final design details and associated procedure guidance, status of open items identified in the Enclosure, as well as any revisions to the information contained in the Enclosure, will be provided in the 6-month Integrated Plan updates required by Reference

1. The information provided in Attachment 3 to the Enclosure is considered to contain information concerning the physical protection not otherwise designated as Safeguards Information and is designated "Security Sensitive Information" as defined in 10 CFR 2.390(d)(1).

Accordingly, TVA requests that the information provided in Attachment 3 to the Enclosure to this letter be withheld from public disclosure.

The Enclosure describes the plans that TVA will use to meet the regulatory requirements outlined in Attachment 2 of Reference 1, but does not identify any additional actions to .be taken by TVA Therefore, this letter contains no regulatory commitments.

If you have any questions regarding this report, please contact Kevin Casey at (423) 751-8523.

I deClare under penalty of perjury that the foregoing is true and correct. Executed on the 28th day of February 2013. J. . Shea V ce resident, Nuclear Licensing

Enclosure:

Sequoyah Nuclear Plant, Mitigation Strategies for Beyond-Design-Basis External Events Overall Integrated Plan 1 cc (Enclosure):

NRO Director-NRC Headquarters NRC Regional Administrator-Region II NRR Project Manager-Sequoyah.Nuclear Plant NRC Senior Resident Inspector-Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission Page2 February 28, 2013 On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued an immediately effective order (Order Number EA-12"049) entitled "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies For Beyond-Design-Basis External Events" to "All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status" (Reference 1 ). The Order indicated that, as a result of the NRC's evaluation of the lessons* learned from the March 2011 accident at Fukushima Dai"ichi, the NRC determined that certain actions are required by nuclear power plant licensees and construction permit holders. Specifically, the NRC required additional defense-in-depth measures to address uncertainties associated with protection from beyond-design-basis events. With respect to this Order, the NRC determined that all power reactor licensees and construction permit holders must "develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and SFP [spent fuel pool] cooling capabilities following a beyond-design-basis external event." Specific requirements are outlined in Attachment 2 to the Order. The Order requires submission of an overall integrated plan, including a description of how compliance with the requirements described in Attachment 2 of the Order will be achieved.

The Order requires the plan to be submitted to the NRC for review by February 28, 2013. In addition, the Order requires submission of an initial status report 60 days following issuance of the final interim staff guidance and at six month intervals following submittal of the overall integrated plan, which delineates progress in implementing the requirements of the Order. The interim staff guidance containing specific details on implementation of the requirements of the order was scheduled to be issued in August 2012. Finally, the order requires full implementation of its requirements no later than two refueling cycles after submittal of the overall integrated plan, or December 31, 2016, whichever comes first, or prior to issuance of an operating license for units under construction.

The NRC issued Interim Staff Guidance on August 29, 2012 (Reference

2) which endorses industry guidance document NEI 12"06, Revision 0 (Reference
3) with clarifications and exceptions identified in Reference
2. Reference 3, Section 13.1 contains the specific reporting requirements for the overall integrated plan. By letter dated October 29, 2012 (Reference 4), TVA submitted an initial status report regarding the progress in establishing mitigation strategies for beyond"design"basis external events, as required by the Reference 1 Order. The purpose of this letter is to provide the overall integrated plan pursuant to Sec;:tion IV, interim staff guidance and has an overall integrated plan developed in accordance with the provided guidance for the Sequoyah Nuclear Plant (SQN) to define and deploy strategies that will enhance the ability to cope with cond.itions resulting from beyond-design-basis external events.

I PWR Portable Equipment Phase 2 -I Use and (potential I flexibility) diverse uses Performance Criteria 7 Maintenance List portable equipment Core Containment SFP Instrumentation Accessibility Maintenance I PM requirements Three Intermediate X 346gpm Will follow EPRI template Pressure FLEX Pumps 942 ft total dynamic head requirements (Core Cooling (TDH) Makeup} Diesel Driven Four High Pressure X lOgpm Will follow EPRI template FLEX Pumps (RCS 3561 ftTDH requirements Makeup} 480Vac 1\vo Water Transfer X X 500 gpm Will follow EPRI template pumps 247 ftTDH requirements Diesel Driven 1\vo Low Voltage X X X X X 480V Will follow EPRI template Diesel Generators 225kVA requirements Tow Vehicle X X X Capable of on-site Will follow EPRI template transport of 14,000 Gross requirements Vehicle Weight (GVW) trailer '-----------_, ------------I 7 Performance criteria of FLEX equipment is conservative and was determined during conceptual design as a basis for the selection of required FLEX equipment.

I The criteria will be re-analyzed during the detailed design phase (01 7). E-63

' -I I PWR Portable Equipment Phase 2 I Use and (potential I flexibility) diverse uses Peiformance Criteria 7 Maintenance List portable equipment Core Containment SFP Instrumentation Accessibility

_Maintenance I PM requirements Fuel Transportation X X X X 500 gallons Will follow EPRI template Equipment Minimum requirements Three Low Pressure X X X 5000 gpm Will follow EPRI template . FLEX Pumps / 350ftTDH requirements (Pressurizes ERCW Diesel Driven Headers) Three Floating Booster X X 5000 gpm Will follow EPRI template Pumps (Supplies Low 50 ft. lift requirements Pressure FLEX Pump) Diesel Driven Three Submersible X 200 gpm Will follow EPRI template Pumps (Supplies 90TDH requirements Intermediate Pressure 480Vac FLEX pump) Three Submersible X 30gpm Will follow EPRI template Pumps (Supplies High 90TDH requirements Pressure FLEX pump) Electrical E-64 --

I PWR Portable Equipment Phase 2 I Use and (potential I flexibility) diverse uses Performance Criteria 7 Maintenance List portable equipment Core Containment SFP Instrumentation Accessibility Maintenance I PM requirements I Two SFP Spray X 250 gpm Will follow EPRI template I Nozzles requirements Two Diesel Fuel X X X 200 gpm Will follow EPRI template Transfer Pumps Diesel Driven requirements Two Medium Voltage X X X X X *6900V Will follow EPRI template Diesel Generator 3MW requirements Crane or other lift X X X 5,000 lb. lift capacity Will follow EPRI template equipment (for staging Minimum requirements pumps on Auxiliary Building roof) Debris Clearing X Capable of clearing trees, Will follow EPRI template Equipment light poles, construction requirements materials and miscellaneous debris --Note: Information lin this table is based on the evaluations documented in Reference 11, which is expected to be representative of the conditions at Sequoyah.

This will be confirmed in Sequoyah specific evaluations for the 6 month update in August 2013. *This can be achiled with a 4160V DG and transformer to provide a 6900V source. E-65

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