ML20140D065
| ML20140D065 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 01/23/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20140D070 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR 85-628, TAC-59988, TAC-59989, WCAP-11015, NUDOCS 8601290115 | |
| Download: ML20140D065 (2) | |
Text
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i VanulNIA 131.IOC~rHIC AND POWIC H CO M I%NY
((IC]tMOND, Y1HO INIA 3:5 261 w.I.. srn w u r Verm Punainent Ni < s_ man Orm uATION80 January 23, 1936 Mr. Harold R. Denton, Director Serial No.85-628 Office of Nuclear Reactor Regulation E&C/DMB/amc Attn:
Mr. Lester S. Rubenstein, Director Docket Nos.
50-280 PWR Project Directorate #2 50-281 Division of PWR Licensing-A 50-338 U.S. Nuclear Regulatory Commission 50-339 Washington, D.C. 20555 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 PRESSURIZED THERMAL SHOCK FINAL RULE SUBMITTAL Pursuant to 10 CFR 50.61, the Virginia Electric and Power Company is providing a submittal of the values of the current and projected reference temperature for pressurized thermal shock (RT
) for Units 1 and 2 of the Surry and North Anna Power Stations.
The submittal consists of two reports prepared by W%cinghouse. Plant specific analyses were performed and are documented in WCAP 11015 for Surry Units 1 and 2,
and in WCAP-11016 for North Anna Units 1 and 2.
Fifteen copies of each report are provided.
The values of RT for the reactor vessels were calculated in accordance with the requirements of 10 CFR 50.61(b)(2).
The fluence analyses are based on actual power distributions for past cycles.
The power distribution in the current cycle is used to determine the projected fluence until the date the operating license expires. The current cycle is designed using an eighteen month low-leakage fuel management scheme.
The fluences were calculated using an adjoint analysis technique consisting of importance functions derived from transport calculations.
Actual material properties were used when possible.
Otherwise, the material properties were determined based on a search of the Westinghouse Owners Group (WOG) Reactor Vessel Beltline Region Weld Metal Data Base.
i 0601290115 960123 i
PDR ADOCK 05000290 p
PDR l
AD - J. KNIGitT (1tr only) h.EB(HALLARD) t EICSH (HOSA) psa (cAwILL)
PSB (BERLINGER)
FOB (BENAROYA)
V[aorwu Etzernic awn Powza COMPANY TOMr. Ilarold R. Denton O
The present RT, values and the projected RTpg, values at the expiration date of the operating license were calculated for each material in the pt, values do not exceed the vessel beltline region for each unit. The RT PTS screening criteria. This assessment will be updated in accordance with 10 CFR 50.61(b)(1) whenever changes in core loadings, surveillance measurements, or other information indicate a significant change in projected values.
Very truly yours,
~
W. L. Stewart Attachments 1.
Fifteen copies of WCAP-11015 2.
Fifteen copies of WCAP-11016 cc:
Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. Donald J. Burke-NRC Resident Inspector Surry Power Station Mr. Morris W. Branch NRC Resident Inspector North Anna Power Station Mr. Terence L. Chan NRC Surry Project Manager PWR Project Directorate #2 Division of PWR Licensing-A g&
Mr. Leon B. Engle NRC North Anna Project Manager PVR Project Directorate #2 Division of PWR Licensing-A L
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