ML18024A751
| ML18024A751 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/13/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903220269 | |
| Download: ML18024A751 (2) | |
Text
- 4~m EGG+TORY INFORMATION DISTRISUlN SYSTEM (RIDS)
ACCESSION NBR:7903220269 OOC ~ DATE! 79/03/13 NOTARIZED:
NO DOCKET FACIL:50~259 BROGANS FERRY NUCLEAR POWER STATIONS UNIT 1g TENNESSEE 05000259 5
BROGANS FERRY NUCLEAR POWER STATION UNIT 2 TENNESSEE 05000260 0-296 RnwNS FERRY NUCLEAR POWER STATIONS UNIT 3>
TENNESSEE 05000296 A
~
AUTHOR AFF ILIATION G ILLELANDt J s E ~
TENNESSEE VALI EY AUTHORI TY REC IP ~ NAME RECIPIENT AFFILIATION STELLOSV ~
DIVISION OF OPERATING REACTORS SUBJFCT:
IN FURTHER
RESPONSE
TO 790208 LTR >/IE BULLETIN 79~pie INIFORMS THAT THERE ARE MOTORS USED ON CERTAIN VALVE OPERATORS IN CONTAINMENT aREA WHICH ARE NOT QUaLIFIEO FOR USE IN LOCA ENVIRON ~ NO SAFETY CONCERNS EXIST ~
DISTRIBUTION CODE:
A002S COPIES RECEIVED:LTR g ENCL +
SIZE:
T I TLE i INC lDENT REPORTS NOTES'EC IP IENT ID CODE/NAME AC T ION l 05 BC ogegg INTERNALe 0
REG FILE 0
14 "A/EDO 16 EEB 18 PLANT SYS BR 20 AO PLANT SYS 22 REAC SAFT BR 20 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS E JORDAN/IE EXTERNAL: 03 LPOR 29 ACRS COPIES LTTR ENCL IS REC IP IENT IO CODE/NAME 02 NRC PDR il MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 I&C SYS BR 21 AD SYS/PROJ 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC BR 29 AUX SYS BR 00 NSIC COPIES LTTR E'NCL TOTAL NUMBER OF COPIES REQUIRED:
LTTR 06 ENCL
CHAT ~ ANCQQA. 7:"~li~lESSK= 37AQ I 500C Chestnut Street Tower II March 13, 1979 Mr. Victor Stello, Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stello:
This report is in further response to James P. O'Reilly's letter to H.
G. Parris dated February 8, 1979, which enclosed IE Bulletin 79-01.
We have determined that there are motors used on certain valve operators in the containment area of Browns Ferry Nuclear Plant units 1, 2, and 3
which are not qualified for use in a LOCA environment.
These motors are used on the following valves at Browns Ferry:
FCV-1-55 (main steamline drain) and FCV-74-78 (RHR head spray).
The above motors are wound with Class B insulation which has a maximum continuous temperature rating of 115 C (239 F).
This temperature rating is exceeded by the transient temperature present in a postulated LOCA environment.
We have examined the service requirements of the subject valves during a postulated LOCA and have determined that no safety concerns exist.
Supplemental information will be provided in the 14-day followup report.
Very truly yours, J.
E. Gilleland Assistant Manager of Power cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303