ML19344A691

From kanterella
Jump to navigation Jump to search
LER 80-030/03L-0:on 800716,during Valve Operability Test, Electromagnetic Relief Valve D Failed to Open.Plant Shut Down.Caused by Deficient Maint Procedure.Valve Plunger & Pilot Valve Operating Lever Clearance Adjusted
ML19344A691
Person / Time
Site: Oyster Creek
Issue date: 08/11/1980
From: Ross D
JERSEY CENTRAL POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19344A674 List:
References
LER-80-030-03L, LER-80-30-3L, NUDOCS 8008210467
Download: ML19344A691 (3)
v • d • e


Text

U. S. NUCLEAR ReiGul.AToHY CoMMISSloh

  • N RC V ] 36G (777 bt j V LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l l@

6 (PLEASE PRINT OR TYPE ALL REQL .tD INFORMATION)

-l0 l t8l-l9 N l JLICfl(t l C l P l 1 l@l Ol 0l -l' 0lLICENSE 0l 0lNUMBER 0l 0 l -l 0l 0 l@l 26 4 l ILICENSE 26 l 1 l ITYPE l 1 J0l@l57 CAT l

$8 l@

7 %5EE COOE 14 15 CON'T IOlil $O,%lLl@l0l5l0l010l2ll DOCKET NUMgER l9 l@l68 0171 69 IEVENT l 6lQATEfd O l@l 018 REPORT 74 75 l I I ilDATE81 o80I@

7 8 60 61 EVENT OESCRIPTION AND PROSABLE CONSEQUENCES h 10121 l On July 16, 1980, Electromatic Relief Valve "D" did not ocen during a l i01ai l valve operabl1ity test. The other four EMRV's operated satisfact6-Ilv l 10141 l during the test. The plant was shutdown and depressurized. An Invest- I lois] I igation revealed that the distance between the "D" EMRV solenoid plunoer I 10l6l l and the pilot valve operating lever was excessive. Acoarentiv the l l0l7ll clearance had not been adjusted properly followino the removal and I i O ia i i the repair of the valve in January, 1980. 80 I

7 8 9 "'

Y$$" "#$E C0 S8Ci$E COMPONENT CODE SLS OO'E S

  • 10191 7 8 l Sl Fl@ d@ l Z l@ l V l A l L l V l 0 l P l@ ldG 9 to 11 12 13 18 i9 LZ_J '@ 23 SEQUENTIAL OCCURRENCE REPORT REVISIOP' R EPORT NO. CODE TYPE NO.

LER RO EVENT YEAR

@s,*jg 18l01 as 21 22 l-l 23 10l3l0l 24 26 M

27 I 01 31 N M lLI 30 L-1 31 l 0l 32 K N AC O P NT M HOURS S8 i POR 8. SUP Li MANUP CTURER LE_j@lGl@

3J 34

[Aj@

35 lMM i@ l010l2l4l 37 40 l41 Yl@ l42N l@ lN 43 l@ l44D l Z l h I'347l@ .

CAUSE OESCRIPTioN AND CORRECTIVE ACTIONS h

.tilOIl The cause of this occurrence is attributed to a daffetant maintananca l 1i ii l i procedure. The clearance between the "D" EMRV olungar and nile univ. I

[Tl 7] l operating lever was adjusted to the proper distance. The valve was act- 1 i,i3l l uated and found to operate correctly. The maintenance orocedure will be I ti#4i l revised to incorporate a reouirement to verify the orocer distance. I 7 8 g 80 STA '6 POWER OTHER STATUS 015 RY DISCOVERY QESCRIPTION y [C_,,j@ l 0 l 216 l@l NA J lBl@l Valve Operability Test l 48TiviTY CO$ TENT RELEASEO OPRELEASE AMOUNT OP ACTivtTY LOCATION OP RELEASE l i I s l (Z_,,j @ l Z l@l NA l l NA l 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NU*.18 E R TYPE DESCRIPTION lt l 7' l '10 l0 l0 l@l Zl@l" NA 8

l PE RSONNE L iNau' dies Nuv8ER oESCRiPTiONh Ii l l8l09 l0 10 l@l 7 11 12 NA 80 l

'NS T E ' $EsCNPT om

(.__l 2 l (_,Z_jh! -

h NA l 7 a 9 10 80 ISSUE D

  • M l Y lhl ESCRIPTION Weekiv News Release l lllllllll1ll l5 8'uo ddi o@uAusAsone.Anan. 7 201-4 M-8784 "1g

[ Donald _A. Ross PHONE:

r Jersey Central Power & Light Company

.' N. ---

ff () Madison Avenue at Punch Bowl Road

'd 3rnstown. New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Repo.-t Reportable Occurrence No. 50-2i9/80-30/3L Report Date e

August 11, 1980 Occurrence Date July 16, 1980 Identi fication of Occurrence Operation in a degraded mode permitted by Technical Specifications, paragraph

3. 4. 2. b. 2 when "D" Eli
  • omatic Relief Valve (EMRV) failed to open during testing following a refueling shutdown.

This event is considered to be a reportable occurrence as defined in the Tech-nical Speci fications, paragraph 6.9.2.b(2).

Conditions Prior to Occurrence The plant was being restarted following a refueling / maintenance outage.

Plant Parameters at the time of occurrence were:

Power: Core, 502 MWt Electrical, O MWe 4

Flow: Reci rculation, 5 3 x 10 gpm Feedwater, 0.9 x 10 6 lb/hr Pressure: 1002 psig Level: 73" Stack Gas: 7.6 x 103 pci/sec Description of Occurrence On July 16, 1980 at approximately 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br /> while performing the Electromatic Relief Valve ' Operabili ty Tes t, "D" EMRV did not open. The valve open light was on, however, an accompanying increase in the torus downcomer line temperature and an audible indication of steam flow were not obtained. The other four EMRV's operated satis factorily during the test.

The plant was shutdown and depressurized to less than 110 psig by 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on July 17, 1980.

Jersey Central Power & ught Company is a Member of the General Public Utihties System

46. .

. Reportable Occurrence tha. 50-219/80-30/3L Ptga 2 August-8, 1980 Upon further ' investigation i t .was found that the distance between the "D" EMRV

-solenoid plunger and the pilot valve operating lever was excessive. This pre-sented the solenoid plunger from contacting and actuating the EMRV pilot valve.

Apparently,:the clearance had not been adjusted properly following removal and repai r of the "D" EMRV In: Janua ry,1980.

Apparent Cause of Occurrence The "D" EMRV pilot valve operating lever to solenoid plunger clearance was not adjusted properly following maintenance.

~ Analysis of Occurrence LThe relief valves of the automatic depressurization system enables the core spray system to provide protection against the small break In the event the feedwater system is not active. . Since the "D" EMRV was inoperable, the A.D.S.

was considered to be operable in a degraded mode. The loss of one EMRV has been addressed in the loss of cooling accident analysis.

Also, the relief ' valves are provided to remove sufficient energy f rom the pri-mary system to prevent the safety valves from lifting during a transient. The t ' iting pressure transient is a turbine trip from rated design power with a failure of the bypass to function. The , fi ve rel ief val ves a re requi . sd to operate to prevent reaching the lowest. setpoint of the primary system safety valves. With core thermal power below 1740 MWt, only four operable EMRV's are requi red to perform this. function. The re fo re, the safety significance of the event .are considered minimal .

Corrective Action The clearance between the "D" EMRV solenoid plunger and pilot valve operating lever was adjusted to the proper distance. The clearance on the other four

~

EMRV's was checked and veri fied to be correct. During subsequent operations, the "D" EMRV was actuated and determined ,to operate correctly.

The maintenance procedure (702.1.007) will be revised to incorporate a require-ment to verify the 'pror4 r-distance between the pilot valve opersting lever and the solenoid plunger.

Fa i l u re Da ta ~

Not applicable.

_.

Retrieved from "https://kanterella.com/w/index.php?title=ML19344A691&oldid=2349814"