05000325/LER-1979-018-03, /03X-1 on 790414:main Steam Relief Valve 1B21-F013J Opened at 520 Psi During Plant Startup.Valve Immediately Reseated.Possible Cause May Be Excessive Pilot or Second Stage Seat Leakage

/03X-1 on 790414:main Steam Relief Valve 1B21-F013J Opened at 520 Psi During Plant Startup.Valve Immediately Reseated.Possible Cause May Be Excessive Pilot or Second Stage Seat Leakage

ML19261D894
Person / Time
Site:	Brunswick
Issue date:	06/26/1979
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19261D893	List: 05000325/LER-1979-018, Forwards LER 79-018/03X-1 05000325/LER-1979-018-03, /03X-1 on 790414:main Steam Relief Valve 1B21-F013J Opened at 520 Psi During Plant Startup.Valve Immediately Reseated.Possible Cause May Be Excessive Pilot or Second Stage Seat Leakage
References
LER-79-018-03X, LER-79-18-3X, NUDOCS 7906280088
Download: ML19261D894 (2)

LER-1979-018, /03X-1 on 790414:main Steam Relief Valve 1B21-F013J Opened at 520 Psi During Plant Startup.Valve Immediately Reseated.Possible Cause May Be Excessive Pilot or Second Stage Seat Leakage

Event date:
Report date:
3251979018R03 - NRC Website

text

h J O U

5 J7 77)

LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFoRMATION) 1 6

M l N l C l B l E l P l 1 l@l 0 l 0 l - l 0 l 0 0 l 0 l 0 l IO l 0 l@!4 l1 l 1l1 l1 l@l 7

8 9 LICENSEE CODE 14 15 Lir NSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T

"'[n"C l L j@l 0 l 5 l 0 l - l 0 l 3 l 2 l 5 @l 014 l1 l 4 l 7 l 9 l@l 0l6l2 6l 7 9lg o

1 3o 7

8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o

2 lDurine olant start-uo and nrosettri>neinn fn11nuing, vafitaling nitenga

,,4n acanm va-o 3

l lief valve 1B21-F013J. opened at 520 osi and immediate1v reseated. The setpoint for 1

O 4

Ithis valve is 1125 osi t 1%.

The result of this event was a reactor scen, dita en n 0

5 l high flux spike on the IRM's.

I O

6 I (Technical Specifications 6.9.2.9b) l O

7 l

l 0

8 l

l 7

8 9 80 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUSCODE COMPONENT CODE SU8 CODE SUSCODE l C l C l@ lE l@ lB l@ l V Al Ll Vl 0l Pl@

Jl@ W @

O 9

7 8

9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR R EPORT NO.

CODE TYPE NO.

@ REPORT l 7l 9l

_l l 0l 1 8[

l,,,, -

0[3l lX l l_

l 1l 21 22 23 24 26 27 28 29 30 31 32 T KN A ON O PL NT M

HOURS 22 S 8 I FOR b 8.

SUPPLIE MANUFACTURER lBlgl34Z lg l35 Clg l6C lg j 0l 0l 4l l

lY g l Y l g l Nl g lT l0 l2 l0 lg 33 3

37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lThe valve actuator was removed and sent to Wyle Laboratories for repair by Target-Rock 4 i

o gg Target-Rock attempted to determine the set pressure of the actuator, but could not dueI g lto excessive pilot leakage. The actuator was disassembled and the pilot disc, second l l stage disc, pilot seat, and second stage seat were all found to be steam cut. While l

,i 3

lno specific reason was found for the valve to open at 520 psi, it is suspected (Con't) i 4

7 8 9 80 ST S

% POWER O THER STATUS DIS O RY DISCOVERY DESCRIPTION l C [@ l 0l 0[ 0l@l NA l

l Al@l Reactor Scram l

i s

ACTIVITY CO TENT RELEASE @D OF RELEASE lZ lg[NA l

l NA l

AMOUNT OF ACTIVITY LOCATION OF RELEASE lZl 1

6 7

8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

l0]0l0l@lZl@l HA l

1 7

PERSONNEL INJURIES NUMBER

DESCRIPTION

1010101@l NA

??im 022 i

i a

7 8 9 11 12 80 LOSS OF OR OAMAGE TO FACILITY 7006280off g "fEg 3

DESCRIMlON 7

d 0 10 go isSuEo@OESCRIPTION e

lNj l

NA ll l

lllll llj 2

O 7

8 9 10 68 69 80 7.

NAME OF PREPARER

LER CONTINUATION -- RO# 1-79-018 Facility:

BSEP Unit #1 Event Date:

4-14-79 that excessive pilot and/or second stage seat leakage contributed to the leakage. The pilot and second stage seats and discs were resu-faced. The actuator was reassembled, tested, and reset to 1125 psi. Valve testing will continue in accordance with ISI : c quirements.

2210 023