ML080880178

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Summary of February 28, 2008, Meeting with Entergy on the Response to Generic Letter 2004-02 for Indian Point Nuclear Generating Unit Nos. 2 and 3
ML080880178
Person / Time
Site: Indian Point  
Issue date: 03/27/2008
From: Boska J
NRC/NRR/ADRO/DORL/LPLI-1
To:
Boska J, NRR, 301-415-2901
References
GL-04-002, TAC MC4689, TAC MC4690
Download: ML080880178 (20)
v • d • e


Text

March 27, 2008 LICENSEE:

Entergy Nuclear Operations, Inc.

FACILITY:

Indian Point Nuclear Generating Unit Nos. 2 and 3

SUBJECT:

SUMMARY

OF FEBRUARY 28, 2008, MEETING WITH ENTERGY ON THE RESPONSE TO GENERIC LETTER 2004-02 FOR INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MC4689 AND MC4690)

On February 28, 2008, a Category 1 public meeting was held between the Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (licensee), at the Hyatt Regency, 7400 Wisconsin Avenue, Bethesda, Maryland. The purpose of the meeting was to discuss the licensee's response to NRC Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage On Emergency Recirculation During Design-Basis Accidents At Pressurized-Water Reactors" and potential revisions to the plant licensing basis for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3). A list of attendees is provided as Enclosure 1, but may not be all-inclusive.

The licensee presented information on how they are responding to the NRC concerns expressed in NRC GL 2004-02. See Enclosure 2 for the handout used by the licensee. The licensee described the existing containment sump configuration for both units, and the modifications completed and those under consideration to address GL 2004-02. They noted that the improved sump strainers have already been installed in IP2 and IP3, although some additional modifications will be installed in IP2 during the spring 2008 refueling outage and in IP3 during the summer of 2008. The licensee discussed their plan to submit license amendments for IP2 and IP3 to revise the current licensing basis for passive failures during the recirculation phase of the loss-of-coolant accident. The licensee also noted that further extensions to the GL 2004-02 target dates may be needed to resolve certain analysis issues.

A member of the public was in attendance, but no Public Meeting Feedback forms were submitted. Please direct any inquiries to me at 301-415-2901, or by email to jpb1@nrc.gov.

/RA/

John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosures:

1. List of Attendees
2. Licensee Handout cc w/encls: See next page

Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:

Vice President, Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Senior Vice President Entergy Nuclear Operations, Inc.

P.O. Box 31995 Jackson, MS 39286-1995 Vice President Oversight Entergy Nuclear Operations, Inc.

P.O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc.

P.O. Box 31995 Jackson, MS 39286-1995 Senior Vice President and COO Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Assistant General Counsel Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Manager, Licensing Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Paul Tonko President and CEO New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. John P. Spath New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

'Senior Resident Inspector's Office Indian Point 2 U. S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Senior Resident Inspector's Office Indian Point 3 U. S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Raymond L. Albanese Four County Coordinator 200 Bradhurst Avenue Unit 4 Westchester County Hawthorne, NY 10532 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511

Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:

Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Phillip Musegaas Riverkeeper, Inc.

828 South Broadway Tarrytown, NY 10591 Mr. Mark Jacobs IPSEC 46 Highland Drive Garrison, NY 10524 Mr. Sherwood Martinelli FUSE USA via email

March 27, 2008 LICENSEE:

Entergy Nuclear Operations, Inc.

FACILITY:

Indian Point Nuclear Generating Unit Nos. 2 and 3

SUBJECT:

SUMMARY

OF FEBRUARY 28, 2008, MEETING WITH ENTERGY ON THE RESPONSE TO GENERIC LETTER 2004-02 FOR INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MC4689 AND MC4690)

On February 28, 2008, a Category 1 public meeting was held between the Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (licensee), at the Hyatt Regency, 7400 Wisconsin Avenue, Bethesda, Maryland. The purpose of the meeting was to discuss the licensee's response to NRC Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage On Emergency Recirculation During Design-Basis Accidents At Pressurized-Water Reactors" and potential revisions to the plant licensing basis for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3). A list of attendees is provided as Enclosure 1, but may not be all-inclusive.

The licensee presented information on how they are responding to the NRC concerns expressed in NRC GL 2004-02. See Enclosure 2 for the handout used by the licensee. The licensee described the existing containment sump configuration for both units, and the modifications completed and those under consideration to address GL 2004-02. They noted that the improved sump strainers have already been installed in IP2 and IP3, although some additional modifications will be installed in IP2 during the spring 2008 refueling outage and in IP3 during the summer of 2008. The licensee discussed their plan to submit license amendments for IP2 and IP3 to revise the current licensing basis for passive failures during the recirculation phase of the loss-of-coolant accident. The licensee also noted that further extensions to the GL 2004-02 target dates may be needed to resolve certain analysis issues.

A member of the public was in attendance, but no Public Meeting Feedback forms were submitted. Please direct any inquiries to me at 301-415-2901, or by email to jpb1@nrc.gov.

/RA/

John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosures:

1. List of Attendees
2. Licensee Handout cc w/encls: See next page Memo: ML080880178 OFFICE LPL1-1/PM LPL1-1/LA LPL1-1/BC NAME JBoska SLittle MKowal DATE 3/27/08 3/27/08 3/27/08

DATED: March 27, 2008

SUMMARY

OF FEBRUARY 28, 2008, MEETING WITH ENTERGY ON THE RESPONSE TO GENERIC LETTER 2004-02 FOR INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MC4689 AND MC4690)

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Subject:

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NRC Meeting with Entergy Nuclear Operations, Inc., on the Implementation of NRC Generic letter 2004-02 at Indian Point Nuclear Generating Unit Nos. 2 and 3 Date: February 28, 2008 Location: Hyatt Hotel, Bethesda, MD PLEASE PRINT ALL INFORMATION LEGIBLY NAME ORGANIZATION cF A --

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,ndian int Ene-rgy Center Generic Letter 2 004-02 February28, 2008 L

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  • Introduction of 0Person nel.
  • Pat Conroy.Director, Nuclear Safety Assurance
  • BobWalpole -Manager, Licensing
  • Roger Waters - LicenSing Engineer
  • Tom McCaffrey.- Manager, Design Engineering
  • Valerie Cambigianis - Supervisor, Design Engineering LouvLiberatori:-

Senior Lead Engineer

  • Ad 1rani Supervisor Nuclear Analysis u"

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  • Purpose Of Meeting
  • Provide NRC an overView of pland anes the licensing basis regarding passive'failure assumptions as related to GL-2004-02.-

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  • .CurrentStatus of Physical Activities Unit 2
    • Summary of physical hanges compled ar.*

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. IR sump increased from 48 sq ft to 3200 sq ft

  • VC sump increasedfom 14 sq ft to 440-sq ft
  • lo bI0 arriers over the incore tunnel
  • Gates at personal entrances through-crane wall phy Iobpet

.. Summaryof physical changes tobe compl ed.i n Spring 2008 refueling outage.

r Screens on crane wall penetrations

  • VC Sump increased from,440 sq ftto 1200 sq ft SBuffer "change out
  • At the completion of-the Spring 2008 refueling outage, all physical changes to the plantfor GSI-191 resolution n will be in place.

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  • Current Status of Physical Activities-Unit 3.
  • Summary of physical changes-completed
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  • m p~let
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SI R sump increased from 48 sq ft to 3200 sq ft

  • VCsump increased from 36 sq ft to 1000 sq ft
  • Flow barriers over.the-incore tunnel
  • Gates at personal entrances through the.crane wall cre cranenwallpenetrations screens ran a
  • New internal recirculation. pumps o Summary of physical. changes remaining to be complete d
  • -Buffe chang.e out
  • By June 30, 2008,all physica changes top the plant for GSl-191.resolution will be in place.

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  • PEC Containment Sum Desin
  • ,,Primary:-. Internal-Recirculation (IR).sump feeding two

.. interna(low head) recirculation pumps.

S-° Backup*:lnternal Vapor Containment (VC) sump feeding two

-external (low head)-RHR pumps.

  • . Both capable of providing post-LOCA recirculation with original deterministic design assumption of 50% sump screen blockage.

- External.VC sump system credited for alternative recirculation flow path'in the event-of an assumed single passive fail'ure in ECCS or

.supportcoion, systems.

I Impact of GL-2004-02

  • NeW mechanistic treatment of post-LOCA plant specific debris, transport and loading.

, Postulated large breakLOCA combined with an-assumed single passive failure upon completion of the switchover from injection -to recirculation could challenge the smaller backup

_ VC sump capab~ility.....

T For smaller postulated break scenarios, debris amounts and/or transport are not expected to challenge the VC sump

,.capability.

  • . POssible Approaches to Addres s-VCSum Loading 0, Revise the current licensing basisfor single passive failure SassumptionS (i~e.,timing of passive failure, natre ofpassive re ature v
  • Employ the alternative break methodology option permitted under GL-2004-02.

o Preferred Option

  • , Revise the assumed timing of a.,postulated single passive failure until at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after event initiation. -
  • No change proposed for the types of single: passive failures considered in current licensing basis
  • Only a change in timeframe for postulating a single passive.

failure is being proposed (i.e., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) consistent with the NRC guidance, (SECY-77-439) for the. following piping systems:

- Unit-2 and Unit 3 Emergency -Core Coolin sy stemr

  • Unit 2 Component Cooling Water System SU:sed Inlileu of applying alternative break methodology.
  • Does not require. aregulatory exemption

U[JQC) LIýa L('QUah LýDýjg SStatus of Licensing Activities

  • Buffering change out - License amendment request
  • e :Unit'2 -Approved by NRC -February 7, 2008

.Unit 3.- Target date to NRC - March 7, 2008

- To be submitted by-February 29, 2008

  • License Basis Change Request (LAR) for Single Passive "FailureAssumptions

- Target date to NRC -:March -7

-2008.,*

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  • OChallengeS to projectcompletion Lidcense amendm.ent reqest

'ad physical for buffer change out-unit 3

  • License 'basis change request for passive failure/sump redundancy review changes
  • Completion of ongoing analytical studies
  • .Updating of report and submission of final letter

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  • Discussion
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