ML17326A025

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Informs That on 990506,NRR Staff Held Public Meeting at NRC Headquarters in Rockville,Md to Discuss Hot Leg Nozzel Gap Issues in Conjunction with Restart of Plant.Viewgraphs Encl
ML17326A025
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/23/1999
From: Stang J
NRC (Affiliation Not Assigned)
To: Powers R
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
References
NUDOCS 9907060109
Download: ML17326A025 (57)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D,C. 2055&4001 June 23, 1999 Mr. Robert P. Powers Senior Vice President Nuclear Generation Group Indiana Michigian Power Company 500 Circle Drive Buchanan, Ml 491C7-1395

SUBJECT:

SUMMARY

OF THE MAY6, 1999, PUBLIC MEETING TO DISCUSS HOT LEG NOZZLE GAP ISSUES FOR THE RESTART OF THE DONALDC. COOK NUCLEAR PLANT

Dear Mr. Powers:

On May 6, 1999, staff of the Office of Nuclear Reactor Regulation held a public meeting at the U.S. Nuclear Regulatory Commission (NRC) headquarters in Rockville, Maryland, to discuss hot leg nozzle gap issues in conjunction with the restart of the Donald C. Cook Nuclear Plant, Units 1 and 2 (D. C. Cook). Formal presentations were made by the licensee.

A list of attendees for the meeting is provided as Enclosure 1. Enclosure 2 is a copy of the slides used by the licensee.

The public meeting with the licensee and NRC staff was designed to provide technical information to NRC staff members regarding the application of hot leg nozzle gap issues to the D. C. Cook loss-of-coolant accident (LOCA) analysis.

The licensee's presentation consisted of two parts. The first part outlined hot leg switchover subcriticality. The second part covered large break LOCA peak clad temperature (PCT) issues.

The discussion of hot leg switchover subcriticality detailed background information, problem statements, intended solutions, and an implementation strategy.

The discussion of large break LOCA PCT consisted of background information, problem statements, and solution. The two presentations were followed by an overall summary outlining the licensing strategy and expected submittal dates.

The licensee did not provide any expected dates for restart of either unit; however, the licensee did identify Unit 2 as being the lead unit for restart.

Following the conclusion of the presentation, the licensee answered questions presented by the NRC staff. NRC staff stated that the meeting was productive and well presented.

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R. Powers June 23, 1999 1

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC's Public Document Room.'incerely, Original signed by:

Docket Nos. 50-315, 50-316 License Nos.: DPR-58, DPR-74

Enclosures:

As stated John F. Stang, Sr. Project Manager, Section 1

Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation ccw/encls:

See next page DISTRIBUTION Hard Copy (w/ encls):

J. Stang Docket File K. Leigh PUBLIC OGC ACRS LPD31 RF E-mail:

S. Collins B. Sheron S. Black W. Lyon F. Orr G. Grant R. Zimmerman J. Zwolinski C. Craig E. Weiss T. Hiltz C. Sochor p/ S)

DOCUMENT NAME: G:>PDIII-1>DCCOOKFDc0506.wpd

  • See previous concurrence OFFICE NAME DATE PGEB KLeigh*

6/23/99 LA LPD3 Q,

EBarnhill, 6/2)/99 PM:LPD3 JStang 6/2 /99 SC:LPD3 CcraigW 6//99 OFFICIALRECORD COPY 1

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R. Powers June 23, 1999 In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC's Public Document Room.

Sincerely, Original signed by:

Docket Nos. 50-315, 50-316 License Nos.: DPR-58, DPR-74

Enclosures:

As stated cc w/encls: See next page DISTRIBUTION John F. Stang, Sr. Project Manager, Section 1

Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Hard Copy (w/ encis):

J. Stang Docket File K. Leigh PUBLIC OGC ACRS LPD31 RF E-mall:

S. Collins B. Sheron S. Black W. Lyon F. Orr G. Grant R. Zimmerman J. Zwolinski C. Craig E. Weiss T. Hiltz C. Sochor DOCUMENT NAME: G:)PDIII-1EDCCOOK)Dc0506.wpd See previous concurrence OFFICE NAME DATE PGEB KLeigh*

6/23/99 LA:LPD3 Q,

PM:LPD3 JStang EBamhill 8<2)ice 6/z /99 OFFICIALRECORD COPY SC:LPD3 CCrai+~Q 6//99

R. Powers ln accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures willbe placed in the NRC's Public Document Room.

Sincerely, John F. Stang, Sr.

oject Manager, Section 1

Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315, 50-316 License Nos.: DPR-58, DPR-74

Enclosures:

As stated cc w/encls:

See next page

Robert P. Powers Indiana Michigan Power Company Donald C. Cook Nuclear Plant Units 1 and 2 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532%351 Attorney General Department ofAttorney General 525 West Ottawa Street Lansing, Ml 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Ml 49127 Jeremy J. Euto, Esquire Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 Mayor, City of Bridgman P.O. Box 366 Bridgman, Ml 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Ml 48909 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P.O. Box 30630 CPH Mailroom Lansing, Ml 48909-8130 David F. Kunsemiller Director, Regulatory Affairs Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 A. Christopher Bakken, Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 Michael W. Rencheck Vice President, Nuclear Engin'eering Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107

OFFICIALRECORD COPY Attendance Hot Leg Nozzle Gap Issues/American Electric Power (AEP)

May 6, 1999 9:00 a.m. -11:30 a.m.

- Name

1. Thomas Noonan
2. Mike Rencheck
3. Jeb Kingseed
4. Gordon Arent
5. Warren Lyon
6. Eric Weiss
7. Frank Orr
8. Michael Emery
9. David Kunsemiller
10. Daniel Garner
11. John Stang
12. Kim Leigh
13. Gregory Hill 14.

15.

Affiliation AEP AEP AEP AEP NRC NRC NRC Westinghouse AEP Westinghouse NRC NRC AEP Enclosure 1

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Technical Meeting May 6, 1999

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COOK NUClEARPlAM Hot Leg Nozzle Gap Issues Gregory J. Hi I Engineer Nuclear Safety 8 Analysis

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COOK NUQEAR PLANT r

HLNG Issues

- Introduction

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Introduce Participants

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Purpose of the Meeting Discuss Hot Leg Nozzle Gap Credit in the Cook LOCA Analyses Two Part Presentation

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Part 1: Hot Leg Switchover Subcriticality => ECCS-recirculation (cold leg injection -> hot leg injection)

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Part 2: Large Break LQGA PCT => ECCS-injection

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AM MICAH'LECTRIC POWER

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COOKNUQEAR PlANT HLNG Issues

- Participants M. W. Rencheck - Vice President of Nuclear Engineering T. P. Noonan - Fuels, Safety, and Analysis Director D. F. Kunsemiller - Regulatory Affairs Director J. B. Kingseed - Fuels, Safety, and Analysis Asst. Director G. P. Arent - Nuclear Licensing Engineer D. C. Garner - Westinghouse Fellow Engineer M. A. Emery - Westinghouse Senior LOCA Analyst G. J. Hill - Nuclear Safety 8 Analysis Engineer

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COOK NUClEARPlANT HLNG Issues

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~ Analysis Benefits due to Hot Leg Nozzle Gap Part 1: ECCS-Recirculation => post-LOCA Subcriticality

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Sump dilution minimizes by borated coolant flow path

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Early analytical solution used HLNG benefit during cold leg recirc Part 2: ECCS-Injection => LOCA Peak Clad Temperature (PCT)

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Reflood phase benefit due to steam vent path

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HLNG benefit applied to past Cook Large Break LOCA analyses

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COOK NUCLEARPlANT Hof Leg Nozzle Gap Issues Part 1

Hot Leg Switchover Subcriticality

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COOK NUClEARPlANT HLSO Subcri ticali ty - Agenda

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Problem Statement for Hot Leg Switchover Subcriticaliiy

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Early Solution

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New Problem

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COOK NUQEAR PLANT HLSO Subcriticality - Background

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10 CFR 50.46 Requirement (b)(5) Long-term cooling. After any calculated successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptably low value and decay heat shall be removed for the extended period of time required by the long-lived radioactivity remaining in the core.

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COOK NUCLFARPlANT HLSO Subcriti cali ty - Background rqly ')i"'aI.

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ECCS-recirculation, hot leg injection alignment

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COOK NUCLEARPLANT HLSO - Problem Statement

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Sub-regions of the containment sump

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Reduced active mixing volume

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Challenge to subcriticality

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COOK NUCLEARPlAM'LSO - Early Solufion

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Not an issue for Hot Leg Breaks

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Cold Leg Breaks credited Hot Leg Nozzle Gap

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COOK NUClEARRANT HLSO - New Problem

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COOK NUCLEARPIANT HLSO - New Solutions

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Preferred Solution is Control Rod Insertion Credit Regulatory Documentation on Control Rod Insertion

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10 GFR 50 Appendix K, Section l.A.2. Fission Heat, "Rod Trip and Insertion may be assumed ifthey are calculated to occur."

Back-up Solution is Cycle-specific Analyses

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~ W Cook-specific Control Rod Insertability Analysis Definitions Current Methodologies Analysis Objectives and Methodology Rod Insertion Acceptance Criteria D. C. Cook Structural Margin Results Conclusions

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HLSO-Control Rod Insertion Credit

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Definitions Design Basis (Cold Leg} Breaks

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1.Q ft'eactor Vessel Inlet Nozzle (RVIN) break

~ Guillotine Reactor Coolant Pump (RCP) Outlet Nozzle break MULTIFLEX1.0 Code

~ W code use for LOCA forces analysis, NRC reviewed and approved MULTIFLEX3.0 Code

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Revised W code for LOCA forces analysis

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NRC accepted in SER on Baffle-Barrel-Bolt Program

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COOK NUClEARPlAM HLSO-Control Rod Insertion Credit

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Long Term Cooling - "The ECCS water has enough boron concentration to maintain core shutdown."

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COOK NUCtEARPlANT HLSO-Control Rod Insertion Credit Tf j7l

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~ Analysis Objective Demonstrate control rod insertion for post-LBLOCA reactivity calculations during long term cooling.

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COOK NUClEARK4NT I

HLSO-Control Rod Insertion Credit

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Fuel Data > Internals Data > LOCA & Seismic Forces > Core Plate Motion >

Grid Loads MULTIFLEX3.0 Design Basis Break Sizes

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COOK NUClEARPlANT HLSO-Control Rod Insertion Credit Structural Margin above Design Limits D. C. Cook Unit 1 Break Size I Location Structural Margin for LimitingGuide Tube Structural Margin for Limiting Fuel Assembly Grid 1.0 ft'VInlet Nozzle DEGL RCP Outlet Nozzle 101'/

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Structural Margin above Design Limits-D. C. Cook Unit 2 Break Size/Location Structural Margin for Limiting Guide Tube Structural Margin for Limiting Fuel Assembly Grid 1.0 ft2 RV Inlet.Nozzle DEGL RCP Outlet Nozzle 146%

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Conclusions LOCA blowdown forces based upon Design Basis Break Sizes Seismic loads combined with LOCA blowdown loads Allowable Limits not exceeded for

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Upper Internals Guide Tubes

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Fuel Assembly Grids at Control Rod Locations Control rods will insert as demonstrated by the calculation

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COOK NUClEARRANT Hl SO-Control Rod Insertion Credit

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Implementation Strategy Tech Spec BASES change & USQ Submittal for NRC review and approval to be mar!e June 15, 1999

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COOK NUClEARPlANT HLSO-Cycle-specific Analysis I 44 i 'P' vv.v.

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Backup Solution

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No credit for control rod insertion

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Requires extensive analysis effort each fuel cycle

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COOK NUClEARKANT HLSO-Cycle-specific Analysis II (

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Refined Xenon calculation based on conservative power history Physical Plant Modifications to increase active sump volume Maximum HLSO time driven by available sump boron

~ Significant reduction in maximum HLSQ time (52 => 4.5 nours)

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COOK NUQEARPlAM'LSOSubcriticality Summary

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Preferred Solution => Control Rod Insertion Credit offers bounding analysis only solution for Unit 2 at this time lead unit for restart

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Backup Solution => Cycle-specific Analyses current methods / revised assumptions / no credit for RCCAs extensive analysis each fuel cycle HLSO window significantly reduced for operators success is not certain for fresh reload cores

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~ Submittal for NRC review and approval

- June 15, 1999

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COOK NUCtFAR PlANl Hot Leg Nozzle Gap Issues Part 2 Large Break LOCA Peak Clad Temperature

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COOK NUQEAR PlANT Large Break LOCA PCT - Agenda

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COOK NUClEARAANl'BLOCAPCT - Background

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PSSM withdrawn / replaced with ESHAPE in 1995

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Hot Leg Nozzle Gap during ECCS-injection

~ Cook LBLOCAPCT credits HLNG during ECCS-injection

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COOK NUCtFAR PlANT LBLOCA PCT-Problej;> Statement C ~

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COOK NUClFARPIANT LBLOCA PCT - Strategy

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New Analyses Unit 1 Cycle 16

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uses ESHAPE methodology

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no credit for HLNG Unit 2 Cycle 12 and beyond

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resubmit LBLOCAanalysis performed to support core uprating to 3600 Mwt

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uses ESHAPE methodology

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no credit for HLNG

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New analyses docketed via 10 CFR 50.46 submittal.

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COOKNN2&VIK4NT LBLOCA PCT-Summary

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New analyses do not rely upon Hot Leg Nozzle Gap credit NRC-approved ESHAPE methodology used

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Part 1: HLSO Subcriticality Analysis Third-party review Licensing Strategy Submittal

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Part 2: Large Break LOCA PCT Licensing Strategy Submittal AMERICAN ELECTRIC POWER'

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