05000317/LER-1982-021, Updated LER 82-021/03X-1:on 820417,main Steam Safety Valve RV-3993 Did Not Lift at Required Setpoint.No Cause Stated. Valve Reset & Retested

Updated LER 82-021/03X-1:on 820417,main Steam Safety Valve RV-3993 Did Not Lift at Required Setpoint.No Cause Stated. Valve Reset & Retested

ML20062B893
Person / Time
Site:	Calvert Cliffs
Issue date:	07/19/1982
From:	Huseby D, Lagiewski J BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20062B876	List: 05000317/LER-1982-021, Forwards Updated LER 82-021/03X-1
References
LER-82-021-03X, LER-82-21-3X, NUDOCS 8208050092
Download: ML20062B893 (2)

LER-2082-021, Updated LER 82-021/03X-1:on 820417,main Steam Safety Valve RV-3993 Did Not Lift at Required Setpoint.No Cause Stated. Valve Reset & Retested

Event date:
Report date:
3172082021R00 - NRC Website

text

'

NRC FORM 336 U.S. NUCLEAR REGULATOR COMMISSION (7 77)

• ** LICENSEE EVENT REPORT Updating Report 3 ., Previous Report Date 17-82 lh CON TROL BLOCK: l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l0 l 1H l9 l Ml D 7

l C l C l N l 141 l@l LICENSEE CODE IS 0 l 0 l - l 0 LICENSE l 0 l 0NUMBEH l 0 l 0 l -- l 0 l 026l@l2b4 l 1LICENSE l1l1 l 1 l@lb7 TYPE JO l

GAI $8 l@

CON'T lol1l 5$R] l60L @l 610l 5 l 0DOCKET l 0 l 0NUVBERl 3 l 1 l 768l@l690 l 4EVENT l 1 DATE l 7 l 8 l 274 l@l75 0 l REPORT 7 l 1 DATE 19 l 8 l802 lh 7 8 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l At 0940, during normal shutdown operation while surveillance testina. 1 1013 l l main steam safety valve (RV-3993) did not lift at the required setpoint. l l O 14 l l The valve was declared inoperabic (T.S. 3.7.1.1.a). The reactor was l I o l 31 l placed in cold shutdown at 2335. All other main steam safety valves l

lo lc l l remained operable during this event. Repetitive events

50-317/79-16, 1 -

I lOl7ll 50-318/78-34. l l O IR I I l 7 8 9 80 DE CODE SUPC E COMPONENT CODE SUBC DE SU ODE O 9 l c l c l @ Lx_l@ LZ_J @ l v l Al L I v l E l x lO LP_j h [B_j h

• 7 8 9 10 11 12 13 18 19 20

- SEQUENTIAL OCCUR RE NCE REPORT REVISION LER RO EVENT YE AR REPORT NO. CODE TYPE NC.

ORg _ 21 l8 l 2l 2/

[-- j 23 l0 l2 l1 l 24 76 y

27 l 0l 3 l 78 73 lX l 30 l--J 31 lIl 32 AKEN ACT O 0 4 PLA T T4 HOURS 22 SB IT D FO b 8. SUPPLIE MANUF C URER y@l X l@ [Z 33 J4 35 _

jg l36Zl@

l0l0l0l0l J/ 40 JQ 41 l42N l@ l43 Al@ l44D l 2 ] 4 l 347l@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li l0 l l Valve lifted below specified pressure (951 psig vice 985 10 psig) but I

lijil l showed good repeatability in testing. Valve was reset and retested. I

, 7 l Eight additional valves were also tested to insure setpoint accuracy l

., ji l3l [ and repeatability. l 11 14 1 l l 7 8 9 80 ST S  % POWE R OTHE R STA TUS DISCO RY DISCOVERY DESCRIPTION I1 15 l [ Djh l0 l0 l0 l@l NA l lB l@l Surveillance Test l A TIVITY CO TENT 4

eE L E ASE D OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 1 6 (,_Z_j @ [Z_j@l NA l l NA l 7 8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION l i l 71 l o l o l o l@L7J@l13 N^ l 7 8 9 11 12 80 PERSONNE L INJURIES NUMBER DESCRIPitON 7

1 R 8 9 l0l0l0l@l n i2 NA 8

l LOSS OF OR DAMAGE TO FACILITY Q 8208050092 820719 E DESCRIPTION  %,,/ PDR ADOCK 05000317 l 1 l 9 l [_Z_jhl NA S PDR l 7 8 9 10 80 NRC USE ONLY ,

2 0 ISSUE10 @ DESCRIPTION l NA l lllllllllllll{

7 8 9 68 69 80 E J

NAME OF PREPARER J. S. Lagiewski/D. E. Huseby PHONE: 301-269-4747/4816 {

LER NO. 82-21/3X, Rev. I DOCKET NO. 50-317 LICENSE NO. DPR-53 EVENT DATE 04-17-82 REPORT DATE 07-19-82 ATTACHMENT CAUSE DESCRIPTION AND CORRECTIVE ACTIONS When tested, this safety valve was lif ted three times. Although the valve lif ted at a pressure below the specifitd range (951 psig vice 985 +/-10 psig), it did show excellent repeatability. No physical damage or anomalies to the valve were found, so the valve was reset, retested, and returned to service at the manufacturer's recommendation.

Periodic statistical samplings of our main steam safety valve setpoints are performed specifically to identify these discrepancies. Upon failure of one safety valve to lif t at the required presure, additional testing is performed to verify setpoints of other redundant valves. Testing of eight other main steam safety valves, as well as retesting of this valve af ter it is reset, was performed near the end of 1982 refueling outage. Had a second failure occurred, all remaining main steam safety valves would have been tested for setpoint accuracy and repeatability. Because an on-going program of surveillance testing already exists, no other corrective or preventive action is deemed necessary.