FVY-81-100, Responds to NUREG-0737,Item II.K.3.25,effect of Loss of Ac Power on Pump Seals.Recirculation Pump Seals Are Cooled by Reactor Bldg Closed Cooling Water Sys.Item Considered Closed
| ML20005B487 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/01/1981 |
| From: | Rich Smith VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20005B488 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.25, TASK-TM FVY-81-100, NUDOCS 8107080286 | |
| Download: ML20005B487 (2) | |
Text
r VERMONT Y AN KEE NUCLEAR POWER CORPOR ATION SEVENTY SEVEN GROVE STREET 2 4.2.1 RUTLAND. VERMONT 05701 FVY 81-100 REPLY TO:
ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGH AM, M ASS ACH USETTS 017o1 TELEPHONE 617 872-8100 July 1,1981 8
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JUL 0 71981
- Q-United States Ncclear Regulatory Commission y,3,gg " f2 9
Washington, D.C. 20555 Atten tion :
Office Of Nuclear Reactor Regulation 9
Mr. Darrell G. Eisenhut, Director
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N Division of Licensing
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b) Letter, USNRC to All Licensees of Operating Plants, dated October 31, 1980 (c) Letter, VYNPC to USNRC, WVY 80-170, dated December 15, 1980 (d) Letter, D. B. Waters to D. G. Eisenhut, BWROG-8142 Subject : Response to NUREG 0737 Item II.K.3.25, Effect Of Loss Of Alternating
- Current Power On Pump Seals Daar Sir:
The subject NUREG Item regnired licensees to determine the consequences of a loss of cooling water to the reactor recirculation pump seal coolers. That item also required that the pump seals should be designed to withstand a loss of power for at least two hours. An acceptable alternative to meeting the two hour requirement was to provide a source of emergency power to the pumps which supply seal cooling water.
At Vermont Yankee, the recirculation pump seals are cooled by the reactor building closed cooling water (RBCCW) sys tem.
In the event of a loas of off site power, the RBCCW system is automatically restarted when AC power is restored by the emergency diesel generators.
I Reference (d) concludes that with the RBCCW seal cooling system in operation, "the seal temperatures remain well below 2500F and no seal deterioration should occur."
Reference (d) further concludes that even in the entremely unlikely event of a loss of both seals the resultant leakage:
- 1) does not influence the result of any loss of coolant accident analysis; 2) is well within the capabilities of normal or emergency vessel water level control sys tems ; and 3) does not lead to a safety concern.
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'U. S. Nuclear Rsgulatory Commission July 1,1981 Attention:
Mr. Darrell C. Eisenhut, Director Page 2 In light of the 'information presented above, Vermont Yankee is planning no further action and considers Item II K.3.25 closed.
We trust this information is satisfactory; however, should you have any further ques tions, please contact us.
Very truly yours,
-l VERMONT YANKEE NUCLEAR POWER CORPORATION R. L. Smith Licensing Engineer RLS: dad 4
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