ML20085G462

From kanterella
Jump to navigation Jump to search
AO BFAO-7314W:on 730919,two Relief Valves Did Not Operate within Specified Limiting Settings.Administrative Procedures Will Be Strengthened & Temporary Tech Spec Rev Permitting Valve Operation at Improper Setting Initiated
ML20085G462
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 09/28/1973
From: Eric Thomas
TENNESSEE VALLEY AUTHORITY
To: Oleary J
US ATOMIC ENERGY COMMISSION (AEC)
References
AO-BFAO-7314W, NUDOCS 8308290096
Download: ML20085G462 (2)


Text

e -

/

U \

TENNESSEE VALLEY AUTHO AITY C'""3M CHATTANOOGA, TENNESSEE :

j i

3740'I L W /</-

\

f* (fp

. 3I U September 28, 1973

/h

,/ h

-4 , .

NN S

PARTN E A GHIP Sh b dk \

p' D 4,\l .f , ,, ~ 7 T

- ('v[A.

,f \ (3' a*

p. {

V Mr. John F. O' Leary, Director f f' cJ #

AP Directorate of Licensing f, Office of Regulation U.S. Atomic Energy Commission g;

9 %@hh 'Q'/ M Washin6 ton, DC 20545 4._. --

Dear Mr. O' Leary:

TENNESSEE VALLLY AUTHORITY - EROWNS FERRY NUCLEAR PIR;T UNIT 1 -

DOCKET NO. 50-259 - FACILITY OPERATING LICENSE DPR ABNORMAL OCCUR 3ENCE REPORT EFAO-7314W The purpose of this report is to provide details concerning two Target Rock relief valves installed en unit 1 at Browns Ferry nuclear Plant having setpoints not within specified limiting safety system settings. This ccndition was reported upon discovery September 19, 1973, to Regice II Directorate of Regulatory Operations, Atlanta, Georgia.

c Description-of the Incident C Following modification and steam testing to meet delay times of 0.4 second and a response time of 0,1 second, reported to F. E. Kruesi, AEC, by J. E. Gilleland, Assistant Manager of Power, on August 29 the unit 1 relief valves were returned to Browns Ferry and installed before initial nuclear heatup and subsequent startup testing to the 150-psig condition. The reactor was placed in the COLD, ShTJTDOWN condition on September 11 to pemit modification to the dryvell ventilation system. In reviewing General Electric Company test certificatec, it was discovered that valve serial No. 59 specified to operate at 1090 + 11 psig had, in a series of four tests, operated at 10& , 10&3, 1072, and 1073 psig. Test data for valve serial No. &

specified to operate at 1100 + 11 psig shoved that it lifted at 1103, 1108,1113, and 1114 psig in a series of four tests. Test data for ODnc g all other installed relief valvec substantiated that set pressures were fdCd D within limits.

oO ~

00 bg Investigation and Corrective Action 4

00 We have recuired, .as a part of a preoperational test, verification rv <

that the certificates fo'r pressure set point of the safety and relief m

ox ;p Em / 7406

- (( 3 COPY MNP REGION u

~~'

~

r- .

_A _ _ , - .. . -.. - . -. _ _ - . - . . _ . _

,i

. ~

O O 2

Mr. John F. O'Iaary September 28, 1973 -

TENNESSEE VAILEY AUTHORITY - BROUNS FERRY NUCLEAR PLANT UNIT 1 -

DoCICT NO. 50-259 - FACILITY OPERATING LICENSE DPR ABNORMAL

OCCURRSNCE REPORT BFAO-731W valves were compared with the required set pressures. This was signed off in March 1973 In July the relief valves were returned to the vendor for modification and testing because of a response time deficiency.

Thece valves were returned to the plant and inctalled before beginning nuclear heatup on September 6. Administrative procedures'will be strengthened to assure that test certification data sheets are reviewed before valve installation. This will prevent similar occurrenecc in the future. Approval has been received from the Directorate of Licencing for a temporary technical specification revision to pemit operation with thece valves until they can be reset in the proper pressurec or replaced with suitable valves.

Very truly yours, .

TENNESSEE VALLEY AUTHORITY ,

d

  • l'Mir!:c.f:':u1

, r.* Thomas

$ rector of Poyer Production CC: Mr. Noman C. Moseley, Director Region II Regulatory. Operations Office, USAEC +

230 Peachtree Street, NW.

Atlanta, GA 30303 l

I i

1 l

l I

2- a E _

.._