ML032820590

Meeting Summary - Usnrc/Vepco & Anp - to Discuss Framatome Fuel Transition Program at North Anna, Units 1 and 2

ML032820590
Person / Time
Site:	North Anna
Issue date:	10/06/2003
From:	Stephen Monarque NRC/NRR/DLPM/LPD2
To:
Monarque S, NRR/DLPM, 415-1544
References
TAC MB4714, TAC MB4715
Download: ML032820590 (9)

Text

October 6, 2003 LICENSEE: Virginia Electric and Power Company (VEPCO)

FACILITY: North Anna Power Station, Unit 2

SUBJECT:

MEETING

SUMMARY

- DISCUSSION OF THE FRAMATOME FUEL TRANSITION PROGRAM AT NORTH ANNA POWER STATION, UNITS 1 AND 2 (TAC NOS. MB4714 AND MB4715)

On August 28, 2003, representatives of VEPCO and Framatome Advanced Nuclear Power (ANP) met with the U. S. Nuclear Regulatory Commission (NRC) staff at the NRCs office in Rockville, MD, to discuss VEPCOs proposed license amendment to use Framatome ANP fuel at North Anna Power Station, Units 1 and 2. This was a Category 1 public meeting. The meeting attendance list is included as Enclosure 1.

The public meeting began with a discussion of VEPCOs submittal to the NRC staff dated August 20, 2003. VEPCO had provided this submittal in response to a request for additional information (RAI) from the NRC staff on the realistic large-break loss-of-coolant accident (LBLOCA) analysis for North Anna Power Station. The NRC staff indicated that it had generated this RAI based on concerns about how Topical Report EMF-2103(P), Revision 0, Realistic Large Break Loss-of-Coolant Accident Methodology for Pressurized Water Reactors was being used to address plant-specific analysis at North Anna.

The NRC staff stated that it needed additional information on the thermal hydraulic parameters described in VEPCOs submittal dated August 20, 2003. The NRC staff, in its RAI dated August 6, 2003, requested VEPCO demonstrate that the thermal hydraulic parameters specified in Topical Report EMF-2103(P), Revision 0, would remain bounded by the plant-specific LBLOCA analysis at North Anna, Unit 2. By letter dated August 20, 2003, VEPCO had provided a response that included a reference to Tables 7.2-4 and 7.2-5 listed in its May 6, 2003, submittal. During this public meeting, the NRC staff stated that these tables needed to be expanded to include additional heat transfer parameters, such as Prandtl and Reynolds numbers, in order to justify the application of Topical Report EMF-2103(P). As a result of this discussion, the NRC staff indicated that it would provide VEPCO with another RAI for Tables 7.2-4 and 7.2-5 of its May 6, 2003 submittal. This RAI was presented to VEPCO after the public meeting and is included as Enclosure 2.

The NRC staff, VEPCO, and Framatome discussed the heat transfer coefficient that was used in Topical Report EMF-2103(P), Revision 0, and how this coefficient would apply to North Anna Power Station. The NRC staff stated this coefficient did not include the effect of radiation heat transfer as a significant effect. The NRC staff requested that VEPCO run the thermal radiation model in order to determine the magnitude of this effect. To facilitate resolution of this issue, the NRC staff agreed to provide VEPCO and Framatome with a rod-rod thermal radiation computer program. This model is shown in Enclosure 3.

VEPCO agreed to provide a response to the NRC staffs questions that were presented during this public meeting within 3 weeks.

Finally, VEPCO presented an overview of its schedule to implement Framatome Advanced Mark-BW fuel at North Anna, Unit 2, during the spring 2004 outage.

/RA/

Stephen R. Monarque, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339

Enclosures:

1. Meeting Attendance List

2. Request for Additional Information

3. Publicly Available Radiation Model cc w/encls: See next page

Finally, VEPCO presented an overview of its schedule to implement Framatome Advanced Mark-BW fuel at North Anna, Unit 2, during the spring 2004 outage.

/RA/

Stephen R. Monarque, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339

Enclosures:

1. Meeting Attendance List

2. Request for Additional Information

3. Publicly Available Radiation Model cc w/encls: See next page DISTRIBUTION PUBLIC OGC JUhle FOrr PDII-1 R/F ACRS UShoop TMarsh JNakoski SMonarque RLandry EHackett EDunnington (hard copy) MKotzalas LWard KLandis, RII JWermiel ADAMS ACCESSION NO. ML032820590 OFFICE PDII-1/PM PDII-2/LA PDII-1/SC NAME SMonarque EDunnington JNakoski DATE 10/6/2003 10/1/2003 10/3/2003 OFFICIAL RECORD COPY

Virginia Electric & Power Company North Anna Power Station Units 1 and 2 cc:

Mr. C. Lee Lintecum Mr. David A. Heacock County Administrator Site Vice President Louisa County North Anna Power Station P.O. Box 160 P. O. Box 402 Louisa, Virginia 23093 Mineral, Virginia 23117 Ms. Lillian M. Cuoco, Esquire Mr. David A. Christian Senior Nuclear Counsel Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. Virginia Electric and Power Company Millstone Power Station Innsbrook Technical Center Building 475, 5th Floor 5000 Dominion Blvd.

Rope Ferry Road Glen Allen, Virginia 23060-6711 Rt. 156 Waterford, Connecticut 06385 Mr. Richard H. Blount, II Site Vice President Dr. W. T. Lough Surry Power Station Virginia State Corporation Virginia Electric and Power Company Commission 5570 Hog Island Road Division of Energy Regulation Surry, Virginia 23883-0315 P. O. Box 1197 Richmond, Virginia 23209 Robert B. Strobe, M.D., M.P.H.

State Health Commissioner Old Dominion Electric Cooperative Office of the Commissioner 4201 Dominion Blvd. Virginia Department of Health Glen Allen, Virginia 23060 P.O. Box 2448 Richmond, Virginia 23218 Mr. Stephen P. Sarver, Director Nuclear Licensing & Operations Mr. William R. Matthews Support Vice President - Nuclear Operations Virginia Electric and Power Company Virginia Electric and Power Company Innsbrook Technical Center Innsbrook Technical Center 5000 Dominion Blvd. 5000 Dominion Boulevard Glen Allen, Virginia 23060-6711 Glen Allen, Virginia 23060-6711 Office of the Attorney General Senior Resident Inspector Commonwealth of Virginia North Anna Power Station 900 East Main Street U.S. Nuclear Regulatory Commission Richmond, Virginia 23219 1024 Haley Drive Mineral, Virginia 23117

ATTENDEES - MEETING ON AUGUST 28, 2003 TO DISCUSS FRAMATOME FUEL TRANSITION PROGRAM AT NORTH ANNA POWER STATION, UNITS 1 AND 2 NAME ORGANIZATION Stephen R. Monarque NRC/NRR/DLPM James F. Mallay Framatome ANP John Nakoski NRR/DLPM Matt Langschmager NRR/DSSA/SRXB Jared Wermiel NRR/DSSA/SRXB Robert Martin Framatome ANP Bert Dunn Framatome ANP Joe Cudlin Framatome ANP Larry ODell Framatome ANP John Biller Framatome ANP Gary Darden Dominion Jennifer L. Uhle NRR/DSSA/SRXB Frank Orr NRR/DSSA/SRXB Thomas Shaub Dominion Nuclear Licensing Kerry Basehore Dominion Nuclear Analysis and Fuel Rick Williamson Framatome ANP Len Ward NRR/DSSA Chris Gratton NRR/DLPM Nadiyah Morgan NRR/DLPM Brad Grimmel NRR/DLPM Ralph Landry NRR/DSSA Larry ODell Framatome ANP Enclosure 1

REQUEST FOR ADDITIONAL INFORMATION Virginia Electric and Power Company (VEPCO) is requested to expand Tables 7.2-4 and 7.2-5 of your submittal dated May 6, 2003, to include the upper and lower limits on the plant parameters, described below, that are key to the correlations during the limiting large break loss-of-coolant accident (LBLOCA). Please indicate on the same table the ranges covered by the assessment data.

For the blowdown, refill and reflood phases, provide the following:

pressure, peak linear heat generation rate, core mass flux, Reynolds number for both vapor and liquid, Prandtl number, degree of super heat For the refill and reflood phases, provide the following additional parameters:

drop size and steam super heat For the injection (prior to refill), refill and reflood phases, also provide key parameters in the correlations for condensation in the upper downcomer and cold legs.

Additionally VEPCO is requested to provide the following information:

If the built in S-RELAP5 pump performance curves were used, then verify that they apply to the North Anna plants pump curves for conditions during the LBLOCA.

Verify that hot leg to downcomer nozzle gaps were not modeled in the LBLOCA analysis.

Enclosure 2

September 5, 2003 MEMORANDUM TO: John A. Nakoski, Project Directorate Project Directorate II-1 Division of Licensing Project Management FROM: Jennifer Uhle, Section Chief /RA/

PWR Systems Section Reactor Systems Branch

SUBJECT:

PUBLICLY AVAILABLE RADIATION MODEL In response to an issue related to the North Anna, Unit 2 license amendment request to adopt Framatome ANPs Realistic Large Break Loss-of-Coolant Accident methodology and exemption request to use Framatome ANP Advanced Mark-BW fuel, the staff requested that the licensee provide additional information regarding the amount of radiative heat transfer expected in the North Anna, Unit 2 core during conditions of the limiting large break loss-of-coolant accident.

To facilitate resolution of this issue, the staff provides a thermal radiation code that will solve an nxn square array of rods for the radiation heat fluxes, assuming no attenuation by steam or water droplets between the rods. This model is publicly available. Two programs are attached.

The first program (R2RRAD.FOR) consists of the 5x5 array used to compute the equivalent heat transfer coefficient in the FLECHT-SEASET heat transfer test 31805. The second program (R2RRAD3X3.FOR) is setup for a 3x3 array to validate the model against a simple two-surface model calculation with a known solution. The source code is FORTRAN-IV. No users manual is included; however, the code contains sufficient comments to enable its use.

Any licensee using this model must justify its accuracy and applicability to the conditions of interest. A description of the code theory is also provided in APPENDIXB_Oct2002.doc and APPENDIXD_Oct2002.doc.

Enclosure 3