ML20083E155

Telecopy RO 50-296-83060:on 831214,nine of 13 two-stage Relief Valves Tested Initially Failed to Lift within Allowable Range.Cause Being Evaluated W/Manufacturer.Nine Valves Will Be Reset & Retested Prior to Installation

ML20083E155
Person / Time
Site:	Browns Ferry
Issue date:	12/15/1983
From:	Jones G TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RO-50-296-83060, NUDOCS 8312280481
Download: ML20083E155 (2)

Text

. . . - .

. y' TELFCOPY TO NRC Dec. 15, 1983 U. S. Nuclear Regulatory Comggg8 7.1 Region II 101 Marietta Street, NW Suite 3100 Atlanta, Georgia 30303 BFRO-50-296-83060 Reported under Technical Specification 6.7 2.a.1 Telecony Date 12/15/83 .T.imit Date of Occurrence: 12/14/83 Time of occurrence: 1530 Unit 3 Technical Specification Involved: 2.2.A Conditions Prior to Occurrence Unit 1 - Refueling Outage Unit 2 - 1050 MWe Unit 3 - Refueling Outage Identification and Descriotion of Occurrence See Attached Anoarent cause of Occurrence :

As stated in previous LERs (BFRO-50-259/83036, -260/82027, -259/81025,

-296/81074), the cause is being evaluated with the manufacturer.

Other Related Events :

(See Attached)

Corrective Action Taken or Planned :

These nine valves will be reset and retested prior to installation, f

a p

I G. T J nes Pow r lant Superintendent Br Ferry Nuclear Plant

• R.it. ' q p'};gy'.

8312280481 831215 PDR ADOCK 05000296 c S PDR 1g6 2 7_

l/i

i., y est TELECOPY TO NRC Dec. 15, 1983 IDENTIFICATION AND DESCRIPTION OF OCCURRENCE Through verbal notification, we have received data indicating that nine of the thirteen two-stage Target Rock relier valves tested at Wyle Laboratories for as-found set pressure initially failed to lift within the allowable range. Tabulated below are the valve serial numbers, set pressures, as-found set pressures, and percent deviation for the first lift.

Valve Serial Number Set Pressure As-Found Percent Deviation 1018 1115 1 11 psig 1130 psig 13 1019 1125 1 11 psig 1161 psig 32 1023 1105 11 psig 1121 psig 1.4 1024 1125 i 11 psig 1179 psig 4.8 1029 1125 1 11 psig 1176 psig 4.5 1030 1115 . 11 psig 1158 psig 39 1063 1105 1 11 psig 1197 psig 83 1078 1125 11 psig 1149 psig 2.1 1085 1125 1 11 psig 1170 psig 4.0 The total average deviation is 3 72 percent.

OTHER RELATED EVENTS

Reference:

BFRO-50-259/83036, -260/82027, -296/80054, -259-81025,

-296/81074. The evaluations performed in the referenced LERs remain valid in that this problem does not result in an overpressure condition of the reactor vessel piping nor does it result in any appreciable increase in MCPR operating limit. Previous calculations performed by the General Electric Company indicated that for the previous unit 3 operating cycle, a total average deviation in relief valve setpoint of 5.0 percent could have existed with no significant effect on nuclear safety.

. - - _ - _ ._ _ _ . ____ ____ ___