ML20056G191
| ML20056G191 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/26/1993 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-526, NUDOCS 9309020219 | |
| Download: ML20056G191 (3) | |
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\\11tGINIA ELEcTitic AND POWEit COMi%NY Hicit>soxn,VanoixtA 2006:
I August 26, 1993 i
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{
United States Nuclear Regulatory Commission Serial No.93-526 l
Attention: Document Control Desk NL&P/CGL R0 Washington, D. C. 20555 Docket No.
50-338 i
l License No.
NPF-4 i
Gentlemen:
i VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 REVISED SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE The North Anna Unit 1 surveillance capsule X was scheduled to be removed from the l
North Anna Unit 1 reactor vessel during the early 1993 outage. On January 20 and March 16,1993, attempts were made to withdraw reactor vessel material surveillance l
capsule X from its holder on the thermal shield. These attempts were unsuccessful.
l Therefore, it became necessary to prepare a revision to the North Anna Unit 1 surveillarce capsule withdrawal schedule that meets the requirements of ASTM E185-82.
The revised surveillance capsule withdrawal schedule, which meets the requirements of ASTM E185-82, is presented in the attachment. The revised schedule includes cumulative burnup and fluence estimates for each capsule at time of removal or at end l
of license, as well as a capsule relocation plan. This schedule supersedes the schedule previously provided by a June 1,1988 letter (Serial No.88-202). Fluence i
estimates in the revised schedule are based on the fluence analysis documented in WCAP-11777, entitled " Analysis of Capsule U from the Virginia Electric and Power Company North Anna Unit 1 Reactor Vessel Radiation Surveillance Program."
The North Anna Unit 1 revised surveillance capsule withdrawal schedule will be included in a future update of the North Anna UFSAR.
In addition, North Anna Unit 1 is currently at a cumulative core burnup of approximately 10 effective full power years (EFPY). The heatup and cooldown curves, as well as low-temperature overpressure protection system (LTOPS) PORV r
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selpoints, currently in the North Anna Unit 1 Technical Specifications expire at 12 EFPY. Therefore, a Technical Specification change to incorporate revised heatup and cooldown curves and LTOPS setpoints applicable to a cumulative burnup beyond 12 EFPY will be submitted to the NRC for review by the end of March 1994.
If you have questions regarding this information, please contact us.
Very truly yours,
'O @ ( wl In) w
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W. L. Stewart l
Senior Vice President - Nuclear i
Attachment - Surveillance Capsule Withdrawal Schedule for North Anna Unit 1 l
l cc:
U. S. Nuclear Regulatory Commission j
Region ll 101 Marietta Street. N. W.
Suite 2900 l
Atlanta, Georgia 30323 NRC Senior Resident inspector North Anna Power Station l
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l
)
i ATTACHMENT SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (a)
(INCLUDING SHUFFLE AT 14.7 EFPY(b))
FOR NORTH ANNA UNIT-1 Estimated Capsule Capsule Lead Withdrawal insertion Fluence l
l Identification Location Factor EFPY/ Year EFPY/ Year (10E19 n/cm2y l
1 V
165 1.6 1.13/1980 NA 0.249 (c) l U
65 1.0 5.90/1987 NA 0.828 (c) l W
245 1.03 14.70/1999 NA 1.94 (d) l l
j Z
305 0.69 14.70/1999 NA 1.27 (d) i Z
165 1.6 NA 14.70/199S NA Z
165 1.6 30.70/2018 NA 4.237 (d) l T (e) 55 0.69 14.70/1999
. NA 1.27 (d)
T (e) 245 1.03 NA 14.70/1999 NA T (e) 245 1.03 30.70/2018 NA 3.18 (d)
Y (e) 295 1.03 30.70/2018 NA 3.81 (d)
S(e) 45 0.55 30.70/2018 NA 3.18 (d) l X (e)(f) 285 1.6 30.70/2018 NA 5.92 (d) i Notes:
i (a) Withdrawal schedule meets requirements of ASTM E185-82.
(b) Effective Full Power Years (EFPY) from plant start up.
(c) Based on plant specific evaluation.
l (d) Based on WCAP-11777, " Analysis of Capsule U from the Virginia Electric and Power Company North Anna Unit 1 Reactor Vessel Radiation Surveillance Program."
(e) Standby capsule.
(f)
Cannot be removed.
NA Not applicable.
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