ML20071N565
| ML20071N565 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/04/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.24, TASK-TM NUDOCS 8210080218 | |
| Download: ML20071N565 (2) | |
Text
m b
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II October 4, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 By letter from D. B. Vassallo to H. G. Parris dated July 8, 1982, we were requested to provide additional information regarding NUREG-0737. Item II.K.3.24, " Adequacy of Space Cooling for HPCI and RCIC," for the Browns Ferry Nuclear Plant. Enclosed is our response to that request for additional information.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Subscribe,p p d sworn j b fo e t
me this NJ& day of n)/
0 982.
i Notary Public My Commission Expires
~~
Enclosure oc (Enclosure):
U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue b
Bethesda, Maryland 20014 fl
,' B210000218 B21004 PDR ADOCK 05000259 P,
PDR An Equal Opportunity Employer
1 3
- ENCLOSURE RESPONSE TO D. B. VASSALLO'S LETTER TO H. G. PARRIS DATED JULY 8, 1982 NUREG-0737, ITEM II.K.3 24 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3
(
Reference:
TVA letter from L. M. Mills to H. R. Denton dated December 30, 1981)
The following is additional information regarding NUREG-0737, Item II.K.3.24 for Browns. Ferry to that'provided.by the referenced letter.
Additional calculations have been performed to verify TVA's position on adequacy of HPCI space cooling during a loss of offsite power event.
The analysis performed was a time-dependent dynamic heat balance of the HPCI pump room with the following assumptions.
1.
Initial HPCI pump room temperature of 80CF, consistent with the Browns Ferry harsh environment analysis, 2.
Normal SGTS operation but no normal reactor building ventilation system operation, 3
No RHR pump operation or RHR pump room cooler operation. The coolers are designed to remove somewhat more heat than the RHR pumps produce, 4.
All walls act as vertical passive heat sinks.
With additional conservatisms included, the space temperature at the end of two hours was calculated to be approximately 1140F, well below the environmental qualification temperature of the equipment.
f
.__