ML20236F480
| ML20236F480 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/23/1987 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20236F484 | List: |
| References | |
| NUDOCS 8711020157 | |
| Download: ML20236F480 (3) | |
Text
'
October 23, 1987 Docket Nos. 50-338 DISTRIBUTION and'50-339 MDocket;111e 3 LEngle
}
NRC & Local PDRs OGC-Beth PD#22 Reading EJordan Mr. W. L. Stewart.
SVarga JPartlow Vice President - Nuclear Operations Glainas ACRS (10)
Virginia Electric and Power Company Gray Files DMiller Post Office Box 26666 Richmond, Virginia 23261
Dear Mr. Stewart:
SUBJECT:
NRC SAFETY EVALUATION FOR STEAM GENERATOR (SG) D0WNCOMER FLOW RESISTANCE PLATE (DFRP) INSTALLATION AND RESULTANT INCREASE IN STEAM GENERATOR TUBE RUPTURE (SGTR) DOSE RATES / NORTH ANNA POWER STATION, UNITS N0. 1 AND 2 (NA-1&2)
By letter dated September 25,'1987, the Virginia Electric and Power Company (VEPC0) provided a Safety Evaluation (SE) to assess the impact of the SG DFRP modification on the NA-1&2 Updated Final Safety Analysis Report (UFSAR)
Chapter 15 accident analyses. The conclusions in the VEPC0 SE indicated that reanalysis of SGTR accident analysis with the SG DFRP modifications resulted in a calculated offsite dose rate greater than originally reported in the NA-1&2 UFSAR. Therefore, pursuant to 10 CFR Part 50.59, VEPC0 requested NRC review and approval of these modifications.
The staff has completed its review of these matters and finds the NA-1&2 SG DFRP modifications to be acceptable for operation at all power levels.
Finally, it is noted that the staff's evaluation of these matters, as stated in the enclosed SE, will be included in the staff's SE of the SGTR event addressing operation of NA-1 at power levels greater than 50% of rated thermal power.
Sincerely.
Original signed by B. A. Boger for Steven A. Varga, Director Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page
- See previous concurrence
- LA:PD22
- PM:PD22
- D:PD?2
- ADR 7
DMiller LEngle:bd HBerkow Glainas SVarga 10/21/87 10/21/87 10/21/87 10/22/87 10/y3/87 8711020157'871023 DR ADOCK 0500 8
UNITED STATES
((
p, NUCLEAR REGULATORY COMMISSION
)
g
- l WASHINGTON, D. C. 20555 j
/
October 23, 1987 Docket Nos. 50-338.
and 50-339 Mr. W. L. Stewart Vice President - Nuclear Operations Virginia Electric and Power Company l
Post Office Box 26666 Richmond, Virginia 23261' l
Dear Mr. Stewart -
SUBJECT:
NRC SAFETY EVALUATION FOR STEAM GENERATOR (SG) DOWNCOMER-FLOW RESISTANCE PLATE'(DFRP) INSTALLATION AND RESULTANT INCREASE
.IN STEAM GENERATOR TUBE RUPTURE (SGTR) DOSE RATES / NORTH ANNA POWER STATION, UNITS NO. 1 AND 2 (NA-1&2)
By letter dated September ?5, 1987, the Virginia Electric and Power Company
-(VEPCO) provided a Safety Evaluation (SE) to assess the-impact of the SG DFRP modification on the NA-1&2 Updated Final Safety' Analysis Report (UFSAR)-
Chapter 15 accident analyses. The conclusions in the VEPC0 SE. indicated that reanalysis of SGTR accident analysis with the SG DFRP modifications resulted in a calculated offsite dose rate greater than originally reported in the NA-182 UFSAR.- Therefore, pursuant to 10 CFR Part 50.59, VEPC0 requested j
NRC review and approval of these modifications.
The staff has completed its review of these matters and finds the NA-182. SG DFRP modifications to be acceptable-for. operation at all power levels.
Finally, it is noted that the staff's evaluation of these matters, as stated in the enclosed SE, will be included in.the staff's SE of the'SGTR event addressing operation of NA-1 at power levels greater than 50% of rated thermal power.
Sincerely, br 1
Steven A. Varga, Director Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page O
Mr. W. L. Stewart:
North' Anna Power Station E
Virginia Electric & Power Company' Units 1 and 2-N cc:.
Richard M. Fos _ter, Esq.
Atomic Safety and Licensing Appeal.
Cockrell, Quinn & Creighton Board Panel U.S. Nuclear Regulatory Commission L
516 Cherry Tower Washington, DC 20555 920 South Cherry Street 4'
Denver, Colorado ~ 80222 Regional Administrator, Region.II Michael W. Maupin, Esq..
U.S. Nuclear. Regulatory Commission Hunton, Williams, Gay and Gibson Office of Executive Director P. 0. Box 1535 for Operations.
j Richmond, Virginia 23212 101 Marietta Street N.W., Suite 2900 i
Atlanta, Georgia 30323 Mrh W. T.: Lough Mr. E. W. Harrell Virginia Corporation Commission Division.of Energy. Regulation P. O. Box 402 P. O. Box 1197.
Mineral,' Virginia 23117-Richmond, Virginia. 23209 Old Dominion Electric Cooperative
-t Ellyn R. Weiss, Esq.
,c/o Executive Vice President.
Harmon, Weiss and Jordan Innsbrook Corporate Center.
2001 S Street NW 4222 Cox Road, Suite 102 l
l Washington, DC 20009
' Glen Allen, Virginia 23060 Mr. J. T._ Rhodes Mr. William C. Porter, Jr.
Senior Vice President - Power Ops.
County Administrator Virginia Electric and Power Co.
-Louisa County a
Post 0ffice Box 26666 P. O. Box 160 Richmond, Virginia 23261 Louisa, Virginia 23093 Mr. Patrick A. O' Hare James B. Kenley, M.D., Commissioner
- Office of the' Attorney General Department of Health l
Supreme Court Building 109 Governor Street 101; North 8th Street-Richmond, Virginia 23219 Richmond, Virginia. 23219 Resident Inspector / North Anna c/o~U.S. NRC Senior Resident Inspector Route 2 Box 78 Mineral, Virginia 23117 i
u
_u_.m
__.m___.__,_,__..,,
m__m.____.__.__,,__,__,_,,,_s,_
_,, _ _