ML070860684
| ML070860684 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/19/2007 |
| From: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 07-0169 | |
| Download: ML070860684 (5) | |
Text
L.I VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 19, 2007 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Serial No.
NAPS/JHL 07-0169 Docket Nos.
50-338 50-339 License Nos.
NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2
SUMMARY
OF FACILITY CHANGES, TESTS AND EXPERIMENTS Pursuant to 10 CFR 50.59(d)(2), enclosed is a summary description of Facility Changes, Tests and Experiments identified in Regulatory Evaluations implemented at the North Anna Power Station during 2006.
If you have any questions, please contact us.
Very truly yours, D. G. Stoddard Site Vice President Attachment cc:
U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station 17Z~LF7
a ATTACHMENT 10 CFR 50.59
SUMMARY
DESCRIPTION OF FACILITY CHANGES, TESTS AND EXPERIMENTS North Anna Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion)
NORTH ANNA UNITS 1 & 2 10 CFR 50.59
SUMMARY
DESCRIPTION OF FACILITY CHANGES, TESTS AND EXPERIMENTS REGULATORY EVALUATION: 99-SE-MOD-04 Document Evaluated: DCP 99-003 - Fuel Assembly Repair/ NAPS / Units 1&2 Brief
Description:
Reconstitution of fuel assemblies following N2C13 shutdown.
Reason for Change: Dominion policy is such that fuel assemblies with known defective fuel rods may not be considered for reuse in subsequent reload designs.
- Also, Dominion has not always determined the root cause failure mechanism of discharged fuel assemblies.
Reconstitution will allow fuel assemblies to be considered for subsequent core reload designs, and potentially aid in determination of the root cause failure mechanism of the assemblies.
Summary:
DCP 99-003 describes the reconstitution of fuel assemblies following N2C13 shutdown.
Reconstituting fuel assemblies, also known as fuel repair, is the process of removing fuel rods and replacing them with solid stainless steel filler rods.
North Anna Vendor Procedure FP-VRA/VGB-FI1 controlled the performance of all fuel repair work, and had provisions for fuel inspections that are beyond the scope of DCP 99-003.
REGULATORY EVALUATION: 06-SE-OT-01 Document Evaluated: Technical Report NE-1473, Rev 0, Addendum 001, "Reload Safety Evaluation, North Anna 1 Cycle 19 Pattern AVE" Brief
Description:
Evaluate the effect on the Large Break LOCA (LBLOCA) accident analysis of a previously unevaluated change to the AREVA Advanced Mark BW (AMBW) top nozzle that resulted in a reduced flow area and increased hydraulic resistance in the AMBW fuel assembly.
Reason for Change: Determine the effect on the LBLOCA accident analysis.
Summary: The evaluation considers the effect on the Large Break LOCA (LBLOCA) accident analysis of a previously unevaluated change to the AREVA Advanced Mark BW (AMBW) top nozzle that resulted in a reduced flow area and increased hydraulic resistance in the AMBW fuel assembly. The change results in a marginal increase in calculated Peak Clad Temperature (PCT) for AREVA AMBW fuel. The LBLOCA analysis of record for Westinghouse fuel is unaffected by the change to the AREVA ABMW top nozzle flow area and hydraulic resistance, since the analysis of Westinghouse fuel conservatively disregards the benefit of flow diversion from AMBW fuel to Westinghouse fuel.
REGULATORY EVALUATION: 06-SE-OT-02 Document Evaluated: Technical Report NE-1453, Rev 0, Addendum 002, "Reload Safety Evaluation, North Anna 2 Cycle 18 Pattern MOE" Brief
Description:
Evaluate the effect on the Large Break LOCA (LBLOCA) accident analysis of a previously unevaluated change to the AREVA Advanced Mark BW (AMBW) top nozzle that resulted in a reduced flow area and increased hydraulic resistance in the AMBW fuel assembly Reason for Change: Determine the effect on the LBLOCA accident analysis.
Summary:
The evaluation considers the effect on the Large Break LOCA (LBLOCA) accident analysis of a previously unevaluated change to the AREVA Advanced Mark BW (AMBW) top nozzle that resulted in a reduced flow area and increased hydraulic resistance in the AMBW fuel assembly. The change results in a marginal increase in calculated Peak Clad Temperature (PCT) for AREVA AMBW fuel. The LBLOCA analysis of record for Westinghouse fuel is unaffected by the change to the AREVA ABMW top nozzle flow area and hydraulic resistance, since the analysis of Westinghouse fuel conservatively disregards the benefit of flow diversion from AMBW fuel to Westinghouse fuel.
REGULATORY EVALUATION: 06-SE-MOD-01 Document Evaluated: DCP 06-109, "Abandonment of Incore Thermocouples", NAPS Unit 1 UFSAR Change Request FN 2006-006 Brief
Description:
Incore thermocouples 1-RC-TE-T20, 1-RC-TE-T29 and 1-RC-TE-T40 will be removed from service. Associated computer inputs to the Inadequate Core Cooling Monitor (ICCM) and Emergency Response Facility (ERF) /Plant Computer System (PCS) will be removed from scan.
Reason for Change: UFSAR Figure 4.4-20 requires revision to reflect abandonment of the thermocouples.
Summary: Three incore thermocouples have failed and a UFSAR change was required to support their abandonment. The abandoned incore thermouples will be sealed with a compression tube fitting which will seal the RCS at the incore thermocouple high pressure fitting. Plugging the high pressure fitting will ensure that the pressure boundary integrity of the RCS is maintained. The remaining thermocouples provide sufficient data for monitoring core exit temperatures.
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 19, 2007 Attention: Document Control Desk Serial No.
07-0170 Director, Spent Fuel Project Office NAPS/JHL Office of Nuclear Material Safety and Safeguards Docket Nos. 72-16 United States Nuclear Regulatory Commission 72-56 Washington, D. C. 20555-0001 License No. SNM-2507 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
SUMMARY
OF FACILITY CHANGES, TESTS AND EXPERIMENTS Pursuant to 10 CFR 72.48(d)(2), a report containing a brief description of any changes, tests, and experiments, including a summary of the evaluation of each, must be submitted to the NRC - Office of Nuclear Material Safety and Safeguards, at intervals not to exceed 24 months. This letter is to notify you that there were no evaluations affecting the North Anna Power Station ISFSI facility during 2006.
If you have any questions, please contact us.
Very truly yours, D. G. Stoddard Site Vice President cc:
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station