IR 05000302/1985042
| ML20138P113 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/16/1985 |
| From: | Panciera V, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20138P102 | List: |
| References | |
| 50-302-85-42, IEIN-80-21, NUDOCS 8512240302 | |
| Download: ML20138P113 (14) | |
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NUCLEAR REGULATORY COMMISSION
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REGION 11 p
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101 MARIETTA STREET,N.W.
'e ATLANTA, GEORGI A 30323
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Report No.:
50-302/85-42 Licensee:
Florida Power Corporaticn 3201-34th Street, South St. Petersburg, FL 33733
- Docket No.: ~50-302 License No.:
DPR-72 Facility Name':
Crystal River 3 Inspection Conducted:
October 24. November 25, 1985
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Inspector:
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m T. F. -Stet ca, seniorlesWntfinspiectWr Date Signed
' Accompanying Person
. E. Tedrow, Resident Inspector Approvedby:k. [l (h,, o /Aa
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-/2.// 6/#
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W.~ Padcier~a,' Se~ction Chief hate Signed Division of Reactor Projects
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SUMMARY Scope:
This routine unannounced inspection involved 142 inspc.ctor-hours on site by two resident inspectors in the areas of plant operations, security, radiological controls,- licensee event reports 'and nonconforming-operations reports, licensee action on previous inspection items, and ' licensee action on Information Notice 80-21.
Numerous facility tours were conducted and facility operations ~ observed.
Some of.these tours and observations were conducted on -
-backshifts.
.Results:
One violation was identified:
(Failure to perform an adequate plant modification as required by 10 CFR 50, Appendix B, Criterion V; paragraph 7.)
8512240302 851218
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- :: REPORT-DETAILS
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.. Persons Contacted-
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S censee' Employees.
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5*MAlberdi, t Manager,' Site ' Nuclear, OperationslTechnica11 Services
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)**G..t Boldt,7 Nuclear 4 Plant Operations: Manager P'
D.iBreedlove,; Nuclear Records: Management Supervisor-
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p JM.iCulver, Senior. Nuclear Reactor. Specialist-
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- J.?Bufe',oNuclear. Compliance' Specialist'
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'E.0Howard, Director,' Site, Nuclear!0perations
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}*WNJohnson, Nuclear. Plant-Engineering.. Superintendent
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nV, t*J./Kraiker,10utage and1 Modification Superintendent
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Ex j*K9LancasterpManager, Site Nuclear Quality Assurance
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/ P.;McKee,5 Nuclear Plant' Manager
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3*T.fMiller, Nuclear Shift Supervisor
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- S.3Powell,ESenior NuclearLLicensing Engineer
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' (*V.lRoppel',; Nuclear Plant: Engineering and Technical:~ Services Manager.
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D*W.(Rossfeld,:NuclearLCompliance'.Managert
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- P.iSkramstad,LNuclear? Chemistry and Radiation Protection-Superintendent'
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t*D.ESmith,LNuclear Maintenance' Superintendent-
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tR.i Wittman, Nuclear Operations. Superintendent
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' 10thEripersonn61 contacted 5 included ' office, operations, engineering,
" maintenance chem / rad :and corporate personnel.
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- Attehde'd exit interview 1
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I2L Exit-Interview
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HThe.in'spector. met:with licensee representatives (denoted in paragraph 1) at a "
sthe' conclusion of the inspection-of November 25, 1985.
During this meeting,
.I Lthe Linspectorisummarized the scope ~ and findings with particular' emphasis of
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- the i vi ol ati on and i nspecto r... fol l owup ~' i tems.
- TheinspectorsL also. discussed : the ' following observations -they had with
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irespects.to 1the plant' shutdown and ? startup during the period of
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, November'22-23:'
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Lackiofc data for; the" testing.of reactor building equipment hatch gn
d personnel. J door seals.
ThisJ test was completed:in accordance with
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+ procedure SP.430,' however data supporting an initial test failure was-
' not available: (though the ' failure. was identified in - the Shift
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4, Supervisor's11og).
~ C-ILogging, omission regarding the' return to service of control rod 7-5.
The-logs were.not sufficiently clear as to the time the control rod was
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returned to service.
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pg'nclusion 'of?theicomputer print' out with:the completed ' data for the:
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- ,,;: shutdown ~ margin" calculation completed on November,22;in accordance.with:
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- 7 procedure SP.421.
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.. W iThesel;observationsi werO discussed with and ' acknowledged by ;the licensee '
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ji-repres'e_ntati ves ! att the i meeti ng. ? While (these items L are : not considered
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, ! enforcement issuesWit ; indicates ' a' lack of ~ attention Jto detail: that.should -
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dThellicensee didinot(identify ras proprietary any of the. materials' provided
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l Licensee' Action on1PreviousiInspection-11tems
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- f (0 pen) JInspector (Fol 1owup x Item i(302/85-05-03)- LIn:a recentL1etter to the
1NRC; dated November 19,?1985,cthe licensee statedithat the-November 20, 1985,
'F Ldue?date? for the Dealibration ofa theimidnand high rar.ges of _ radiation o
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u monitorsi-RM-Al-and RM-A2 had to'be extended to March 31, 1986. :In addition, m
Otheilicensee indicated that ~ their efforts to: calibrate these instruments
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frevealed 'that~ their main'~ steam line (MSL) radiation monitors which had been'
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?previously installedJand tested,91acked detecti_on. sensitivity. -The111censee-
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Jhas41nitiated'a modification to correct.this sensitivity problem.onithe MSL
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~ jhe711i:ensee LhasDnot3yet' completed development of a surveillance procedure 6 W:
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It is expected :that this procedure
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%This' item' remains:open pending completion of these' activities..
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. ' ' $(0 pen)LIn_spector Followup Item (302/85-29-09): 'The> inspector has reviewed.
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'the. licensee's. investigation into-thel inadvertent water transfer between the?
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- Borated WaterJStorage Tank (BWST) and the Lspentifuel pools. -The licensee 9<
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- has:determinedithat the' cause:for this event was due to :an operator. failing
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ito' follow L the :BWST" restoration valve lineup specified by procedure SP-320.
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j(Operabilityfof;: Boron ' Injection Sources :and Pumps).
Failure to adhere to
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f the requirementsFof 4SP-320 isicontrary to the requirements.of-Technical
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jSpecification'(TS).6.8.~1.a.andfisconsi_deredtobe'a. violation.
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1Thi.s" item-will be - addressed concurrently with a violation described in
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l paragraph l5.b.(9)f of this: report.
This item remains open pending review of
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't the;. licensee's c respon'se -
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f(0 pen)j.spector; Followup Item-(302/85-29-10):- The inspector has reviewed W
ithe?11 ensee'sLinvestigation into.a: spill.from the BWST through a vent valve
^during the functional test 'of valve.MUV-58.
The licensee has determined'
DM that ;thelcause: fore this event.was due.to 'an inadequate clearance being f',
dissued to' establish'the system's test boundaries'(the vent valve should have tbeen closed during the' functional test).
This clearance was not verified by
'a SeniorJReactor Operator-(SRO) as required by procedure CP-115 (In-Plant Equipment clearance'and Switching Orders).
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. 'sid/che$kTforiurtherf compliance with lCP-115, the inspector reviewedfrecent E
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H clearances: for the months of' October. and November 1985. ' As a result of.this.
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> review, Gthe Hnspector11dentified ' 4 clearances (clearances 110-38,11-222
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511-33tand 11-96) in which 'no evidence existed that a SRO had verified the
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iclearanceiprior ito: the a commencement; of. work.. Failure:to adhere to the-
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frequirements !of CP-11511s contrary to-the requirements.of TS '6.8.1.a 'and is
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l considered to be a' violation.-
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' ?Thisfiten will ibs : addressed concurrently ;with "a violation described 'in
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(paragraph 5.b_.(9)/ofthis' report.
This.ites'will ' remain open pending review
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<of;theLlicensee's response.
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f f(Closed)^ Inspector. Followup Item _(302/85-29-07):
The licensee has evaluated
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the effects-of out' of tolerance instrumentation-identified by NCOR 85-103.
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Jand!has determined;that: the ' operation ~ of safety. systems was not affected.
- The
- inspector has ireviewed :the 1icensee's evaluation,and has L no ' further
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- (Closed); Inspector FollowupfItem (302/85-07-04)
The_ licensee.has corrected
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Vthe ; discrepancies 'in their. reactor trip breaker maintenance program by
1revisi.ng procedure PM-118:(AC and DC Breakers - Control Rod _ Drive-System).
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!The flicensee has fdstermined that General Electric Service' Tip No.~ 3-79 is gnotf applicables toithe -testing. ofl the reactor trip breakers 'since these
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breakers fare tested underfa no load icondition and no. rated short-time-currentL tests ^are performed on, breakers during the performance of procedure -
PM-118.'
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ag The Linspector-hasf reviewed this : procedure and has observed the performance
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of reactor trip breaker maintenancei The inspector has'no further questions i
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LUnresolved Items.
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? Unresolved.i.tems-were not identified during this inspection.
<g L5.- JReview ofoPlant Operations iThe plant' started thisiinspection period in power operation (Mode 1).
On
_ Octoberl24,1985, an increase in unidentifled Reactor Coolant System (RCS)
i 1 eakage - (from !about 0.3.gpm to 0.6' gpm)-was observed and the plant.was
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voluntarily shutdown :to the hot standby mode (Mode 3)' at 3:10 p.m. on
,~Octoberf25 for investigation.
The leakage was determined'to be seat leakage
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by ' drain 11ines - on ' the primary -side of the steam ' generators.
Drain line
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isolation ~ v'alves Lwere torqued. shut and RCS leakage-decreased back to
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iprevious' values. 'The' reactor 'was restarted at 6:45 p.m. on October 25 and t
ithe" plant entered Mode 1 at 7:27_p.m.
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On October-26,-:an anticipatory reactor trip from 97% power occurred when the
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Jmain ' turbine wasJ. tripped 1during an electrical loss of the "A"1 Inverter
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E (V8IT-1A).. L(See; paragraph - 8. A fors details. ) After repairs 'were completed :
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to? V81T-1A theireactor was restarted.at'3:26 a.m. on October: 27 followed by ;
- entrysinto Mode 11at=3:47 a.m.
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?0nfNo'v' ember 8,Jat 3:56 a.m.' the reactor tripped on high RCS pressure due to -
e(the11ossiofi a condensate-booster pump (see paragraph 8 for details).. : After.
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-. the : booster pump ' was Linspected ' and ; tested satisfactory,. the reactor was'.
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takenLcritical at 1:32 p.m. followed by entry into' Mode.1lat 1:55 p.m.
'TOnNoemher-22,La'l4:05'a'.m.acontro'1 rod'droppedintoithereactorcore.
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- plant' shutdown was. commenced inorder to replace the control rod'.s stator.-
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?At11:01'p.m. Ethe; reactor tripped on ' high pressure -from 18% power due-to,
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o feedwater transients'-(see paragraph' 8.c for details 'of these.two events).
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-Following the contro1Lrod's stator replacement,-the reactor.was:restartedLat-
':4:10 a.m. <on ' November ~24 andithe-plant reentered Mode 1 at.4:35 a.m.xwhere
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lit-remained.for the; duration of thisiinspection period.
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Shift LogsLand Facility Records'
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. /Thef inspector reviewed records and discussed various entries with -
ioperations personnel to : verify compliance with ~ the - Technical Specifications-(TS) and the-licensee's administrative procedures.
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lThe following' records were reviewed:
> Shift' : Supervisor's-Log; Reactor > 0perator's Log; - Equipment'
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- 0ut-cf-Service. ' Log; ; Shift Relieff Checklist; Auxiliary Building
,0perator's Log; Active Clearance Log; Daily Operating Surveillance Log;
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WorknRequest > Log;; Short Term Instructions ~ (STIs); :.and selected
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Chemistry / Radiation Protection Logs.
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a' dition to these' record reviews, the inspector independently
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JIn.ified clearance order tagouts.
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- No violations or deviations were identified.
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Facility-. Tours'and Observations
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Throughout Jthe inspection period, facility tours "were conducted to
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Some operations and maintenance activity observations were conducted during
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backshifts.. Also, during this inspection period, licensee meetings-
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activities..
.The facility tours and observations encompassed the following areas:
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- Security Perimeter -Fence; Control Room; Emergency Diesel Generator Room;J Auxiliary Building; Intermediate Building; Battery Rooms; and Electr_ical Switchgear Rooms.
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- During.theseLtours, the following observations were made
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t (1)RMonitoring Instrumentation
' The following instrumentation was
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lwith'the TS for the current operational mode:
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[Eq0fpmentoperatingstatus;-Area,' atmospheric ~andliquidradiation-
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imonitors;; Electricalisystem lineup; Reactor operating parameters;.
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fand_ Auxiliary equipment operating. parameters,
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No' violations orideviations were' identified.
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'(2)!. Safety:Syst' ens Vilkdown '- The : inspector conducted a walkdown of
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Edecay heat ~ closed ~ cycle cooling. system-(DCV) to verify that the
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< lineup wasL in accordance with > license requirements for' system '
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~ perability and that the system drawing.and; procedure correctly
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reflect "as-built" plant conditions.
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x CNo' violations orideviations were identified.
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L(3) : Shift LStaffing - " The inspector verifled. that1 operating -shift
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. staffing was. in(accordance with CTS requirements and that control
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room operations: were being conducted innan orderly and
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professional manner., LIn addition, the inspector observed = shift
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-: turnovers on various occasions to verify the continuity'of-plant
status, foperational problems, :and other pertinent plant iinformation during these turnovers.
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'No: violations or. deviations were-identified.
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(4)M Plant Housekeeping Conditions - Storage of material and components
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- and cleanliness-conditions of various areas throughout the facil-
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ity.were observed to determine-whether safety and/or fire hazards
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existed.
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No: violations or deviations were identified.
.(5) LRadiation' Areas'- Radiation Control Areas (RCAs) were observed to verify ' proper identification and implementation.
These observa-gW tions included selected :: licensee conducted surveys, revfew of-
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step-off' pad conditions, disposal of contaminated clothing, and
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y Larea. postings. ' Area' postings were independently verified :for'
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? accuracy through the use of the ' inspector's own radiation
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monitoring instrument.
The inspector also reviewed selected
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radiation work permits and observed personnel. use of protective
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clothing, respirators, and personnel monitoring devices to assure
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followed.' -
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1(6)';Securityiontrol - Security controls were' observed to; verify that'
security' barriers are-intact, guard forces lare on duty,.and access-~
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J to 1the - Protsw:ted ' Area' (PA) - is controlled in accordance with 'the e
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- facility security plan.e: Personnel'within the PA were observed to,
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! verify; proper display of L badges 1 and that personnel 1 requiring
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escort :were, properly escorted.
Personne1'within vital: areas'were
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observed lto ensure: proper authorization:for the area.
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.No violationsior. deviations were identified.-
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.,31)l. Fire. Protection - Fire protection activities,. staffing and equip-
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' ment iwere : observed to : verify that: fire brigade staffing was
appropriate L and: that fire 1 alarms,f extinguishing equipment,:
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. actuating controls, fire fighting. equipment, emergency equipment, P
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'No violations-or deviations were identified.
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2 (8)1 Surveillance - ~ Surveillance'. tests were observed :to verify -that.
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' approved procedures.were being used;. qualified personnel.were
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' conducting the L tests; stests were adequate;toiverify equipment
foperability; calibrated equipment, as required, were utili:ed;'and
- TS requirements were followed.' ^
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g The:following tests-were observed and/or data reviewed:
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- SP-110,fReactor Protective System Functional Testing;-
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.SP-141,-Operability and Functional' Check of Valve Monitoring.
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1 P-192, High~ Density Rack Poison Sampling; S
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sp.337,.RC System Water Inventory Balance; (#.. w$%
SP-324,: Containment Inspection;
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a SP-350,: Turbine-D' riven Emergency Feedwater Pump 3B Overspeed Trip s
Test;'
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SP-370,: Quarterly. Cycling of Valves;
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SP-401' Control Rod Programming Verification;
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SP-409, Temperature and Vibration Methods and Bearing Temperature
[4 Acquisition for Section XI Pumps;
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SP-421, Reactivity Balance Calculations;-
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a lSP-422,j.RCSyst'emHeatup;andCooldown' Surveillance;>
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-:SP-425,LCon' trol Rod Drive Patch Panel Access Control; and
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rSP-430,, Containment; Air Locks.
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'As a result of these reviews the following items were identified:'
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I f('a)ilDur'ing.rperformance ::of L SP-19', Dthe ' reactor specialist '
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. determined _ that the' percent weight ' loss for the' Carbone
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- Tetraboratei _(B,C) : poison 1 material Jsamples failed - the
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z procedure's'. acctptance criteria..The 8,C_ poison-material'in
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the1high Edensity ~ spent-- fuel ! storage facks =is used in ~
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i6 calculating Kthe Effective Neutron Multiplication _ Factor:
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'(Keff)? for;the spent fuel pool and ensures that criticality
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% a cannot be' achieved.in the spent fuel _ pool.. In accordance.
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<- with the licensee's procedures, the boron concentration in
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_the spent fuel pool's cooling water has been increased to
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- refueling concentrations-:and the B C samples have been
idimensionally measured.
The' licensee.is presently evaluating-
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theseLmeasurements and weights for comparison-with previous
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values.'
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Inspector. ' Followup Item - (302/85-42-01): _ Review the'
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flicensee's analysis to determine the: adequacy. of-the 8 0
-
.
- poison material in the spent fuel storage racks.-
.(b) During performance 'of -SP-141; the valve monitoring acoustic monitor signaliamplifier's --filter. function _ voltages were
' found to.be out of: tolerance.
Th.is voltage drift was also
. ~ observed during the previous. performance ~of SP-141 and the licensee lisJ presently evaluating the net effect this' out' of
"
9-
-
. tolerance condition has on-the acoustic. monitor indication.
Inspector _ Followup Item (302/85-42-02):
Review the ir
- licensee's-determination of the effect of out of tolerance voltages on the amplifier filter function of the acoustic
.
monitors.
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,
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No violations or. deviations were identified.
,
- (9) Maintenance Activities - The inspectdr observed maintenance
"b',
? activities. to verify that correct equipment clearances were in
.
effect;1 Work Requests and Fire Prevention Work Permits, as
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required, were ' issued and being followed; Quality Control personnel were available for inspection activities as required; and TS requirements were being followed.
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. sintenance was : observed;and' work packages were reviewed fAr' ~the
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following' maintenance' activities:
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- -U ITroubleshooting ' noise in the:"B". Nuclear : Services 1 Closed
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i jy 1 Cycle : Cool _ing Pump.-(SWP-18)l gearbox and 1 disassembly in ('
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Taccordance withtmaintenance. procedure MP-509;-
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Jl 1 Replacement..of ~one^ AC :asd two DC reactor tNp. breakehskirk,
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?accordance1 with : procedure PM-118, and; associated testing; in yp
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.accordance with' surveillance procedure SP-110; V
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Replacement of a-cooling fan on the."A" inverter (VBIT-1A)L
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- LTroubleshooting of the: r6d control. system' auxiliary power
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1 supply;
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Replacement'ofoexpansion joint on discharge-piping of(SWP.-1A c'
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Lin :accordance with procedure MP-132, and pump alignment' ig M-accordance with_MP-509;-_
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- Troubleshooting.the. 'overspeed trip mechanism for theisteam Y
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- driven Emergency Feedwater Pump (EFP-2);:and~
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. Troubleshooting of the power supply for control rod number 51
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7in< rod groupLnumber 7.
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While: rev.iewing"t hs vorkipack' age / for troubleshooting th'el overspeed.
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> ; trip ' mechanism for EFP-2,: the inspector noticed;an interoffice -
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fletter?attacheda toithe, work package.. Thish letter-provided.
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- instru'ctions. stolvisually : inspect and remark 1o11_ : level sight
' y Q, iglasses(to: establish' mini' us' andfmaximum ' oil 11evel. indications.
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'-, rThesefinstructionshimplemented a ' previous. modification!on EFP-2,.
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- MAR -81-06-12-01,::that: had been closed _ on December-
.
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28, 1984. ~The
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b" Qf inspectorf noted J that L the workl request? did ; not specify any-l maintenance; to ~ be performed on the oil level - sight glasses and 9 s,
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.thatt theluse off an interoffice ~ letter. to ' authorize and document:
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A this work wasi not in accordance'with procedure AI-600-(Conduct ~ of.-
g Maintenance). ~ Failure ;to ! adhere to the requirements of Procedure-
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'AI-600 is consideredcto be a violation of TS-6.8.1.a.
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- NRC/ Report c 50-302/85-41.
Since this report covered inspection'.
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The licensee was 'issuedia similar_ violation against TS 6.8.1.a in.
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factivities E for-theJ month of 0ctober 1985, there has been-
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. insufficient; time for-tde licensee to respond.
Therefore, the
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c iviolations discussed in this-paragraph and in paragraph 3 of this
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, reportL will :not be, cited but will be considered to be further
.
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,e'xamples:ofiviolation:50-302/85-41-01.
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- This ' violation 'was - discussed in the Exit Meeting conducted on
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' November. 25','
1985.
The licens4e will address their corrective-actions 1to - thisi violation concurrently with their response to
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w iviolation-50-302/85-_41-01.
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(10) RadioactiveIWaste Control's < : Solid Wa' teMompacting.and selecte'd.
s 111guid and = gaseous: waste (releases; were otnerved to. verify that j approved 7 procedures 'were utilized, that' appropriate release
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. < capprovals;werelobtained,land that: required surveys were taken.-
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(Nolviolationsoreviationsweretidentified.
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I(11) Pipe diangersland Seismic Restra'ints,- Several pipe : hangers and -
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- seismic a restraints :-(snubbers) _on: safety-related systems were
..
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Eobserved toJensure that fluid levels-were adequate.and no leakage'
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~waso evident, that restraint -settings, were f appropriate, and that anchoring points were'not~ binding.
No violations orfdeviations'were identified.
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~ 76.. ; Review'offLicenseel Event Reports and Nonconforming' Operations Reports
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"Licenseel Event': Reports -(LERs)Twere reviewed for potential generic
.
simpact, :to; detect trends, andito determine whethericorrected actions
, cc appeared ; appropriate.~ ; Events, which were repor_ted Limmediately, ~were:
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1 reviewed ~as:they occurred to determine if:the TS were' satisfied.
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- LERs185-18) 185-19',- 85-20, 85-21,- and 85-22.were' reviewed in accordance'
'
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Jwith J.currentL NRC enforcement : policy. : LERs 85-19 through 85-23 '.are l considered Lto. be' closed.
LER 85-18 remains open for the following n
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/ reason:
-
u iL' R 85'-18 lreportedithe failure to -ident'ify.out; of service-seismic W
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Jmonitoring; instrumentation.
The licensee!s corrective actions for-
'
~ thislevent' included the' counseling of1 personnel involved.
This
a
Lcounseling(hasJnot beenJcompleted. LThe LER, remains-open pending
,
completion ofathisicounseling.
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- The Sinspectoi
- reviewed Non-Conforming:OperationsLReports:(NCORs) to
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.
Everify the~ following: scompliancef with the TS,< corrective actions as
"identifiediin the i reports or during - subsequent reviews have ~ been
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.
~accomplishedLoriare being pursued for completion, ~ generic -items' are.
-
.
Jidentified anc' reported as. required. by 10 CFR Part 21, and items are
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, ' reported as required byLTS.
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- A11LNCORs;were trMswed in"accordance 'with the current NRC enforcement
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fpolicy.
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(No~ violations or deviations were identified.
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,jgj7C!DesignjDesignChangesandModification's
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- Installation! of newlor -modified systems were reviewed to verify that the
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i changes)were'reviewedfand. approved in accordance with 10 CFR 50.59, that the t
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- changes (were'
- performed inaccordance with technically adequate and approved
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orl.devia'tionstwere resoldedlin an acceptable-manner,.and that appropriate f l'.
~ ldrawingsEandl facility; procedures were revised as necessary.
This review
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p4 included selected observations of modifications and/or testing in progress.
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.The : followingj modification - approval f records (MARS). were reviewed and/or
~ associated testing: observed:
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?-1 ' In_ stall'at'ioni off support ~ plat.es. around pipe. support pedestals jfor
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~ nuclear: services seawater. piping and insta11ation of:a new pipe support
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- ion n the nuclear ' services seawater'. system _ in accordance with, MAR-
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(T85-11-01-01;
"o InstallationLof) expansion joint rest'raints' to nuclear services seawater
~
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- heat exchangers.in accordance with MAR T85-11-01-02; y:
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- 1 Replacement-ofthe oil :le' vel indicating _ system on the Steam Driven
~ EmergencyL Feedwater Pump (EFP-2) in accordance with MAR 81-06-12-01; e,
M:H.
..and.
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j Replacement of ': valve.SW-5921on the nuclear services seawater -heat -
O1 exchanger in'accordance__with MAR 85-10-17-01.
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' As?a result of these reviews the:following item was identified:
~
? uring Itroubleshooting Jofithe EFP-2 overspee'd trip mechanism, the vendor D
' representative noticed that damage had occurred to the turbine. bearing._ The
'
,
.
' ; inspector / questioned the Lvendor : representative 'as to the11ikely'cause'for o
1/".
thisidamagetand:was i.nformed that' an inadequate oil level was maintained in-
,
t-the bearing's-oi1Lsump. reservoir:which p~revented adequate lubrication of the
-
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~ obearing'ar# resulted in damage to the bearing.
i'hednspector1 researched the ~ modification which installed the oil level-
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sindicating system to,EFP-2,(MAR '8106-12-01).
Field 1 change notice number-3
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to this:modificationLprovided instructions to ' install oil. sight glasses and
~toraffix ' maximum' and minimum oil" sump -: level ; indications to these sight (glasses.: "The; minimum and maximum sight glass oil. level. dimensions provided
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- bysthis? field change 1 notice ~were~ not adequate. in that they.resulted _in oil
'
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reservoirdievels: being ' maintained below that specifled.in the vendor
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ate'chnicalimanuallforfproper lubrication _~of the' turbine bearing.
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..! Implementing a plant modification with. inadequate instructions is contrary
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to; theJrequirementsf of -10 CFR Part 50, Appendix B, Criterion V as
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bisplemented-by1FPC's~ Operational-Quality Program, paragraph 1.7.1.5 and is w
- iconsidered'to.be-a violation.
'd (Violation f(302/85 42-03)i ' Implementing a plant modification with inadequate
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instructions which-is' contrary to 10 CFR 50, Appendix B, Criterion V.
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ta';. { At'-2:10 p.m.' on October 26,1985, the "A"1 Inverter (VBIT-1A) failed.
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' - This caused' asloss of :thei"A" Main Feedwater Pump? (FWP-2A), a plant?
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~ / Integrated 3ControllSystem.(ICS) runbackito:55% power, tripping of the '
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i-4 "A" ' Reactor. Protection - System.-(RPS) ; cha'nnel e and interrupted. the
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- primary. power supply-to;theJControll Rod, Position ' Indication (RPI)
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1 system.. NoJreactort trip ~ had yet-occurred since two RPS channels arei
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' required:toLtrip;to_ generate'_a reactor trip..
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'Due toj an limproperly(adjusted backup-. power. supply, the RPI system -
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?momentarilyf indicated that:all control rods'were on.the bottom of the
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. core.
This information combined with - the alarms-from _ the' tripped.RPS
,
- channel. caused controliroom operators to' believe a reactor <tripz had~
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_ R occurred.: LInnaccordance with' plant' procedures for a reactor trip, i
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operatorsi manual.ly. tripped the main turbine when'it was observed that:
.the main turbine _ had {not automatically tripped.. Tripping the main
.
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Eturbine' caused an anticipatory reactor trip.
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Thel: inspector ~ reviewed the plant's. parameters, conditions, and the
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Slicensee's; post trip evaluation and; has no further-questions on this"
" event.-
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$tU. j At? 3i56 i a.m.',fon November 8, theireactor tripped on high Reacter
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f Coolant' System: (RCS) pressure..The plantfwas operating'at approxi-matelyi95%: power when the '"A" Feedwater Booster Pump -(FWP-1A) tripped.
-
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- Loss of the',feedwater: booster; pump caused.an ICS: plant runback to lower:
.
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,
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power'to 55%. iThis power' reductio'n resulted in less heat transfer from
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, ipressure J tripi Licensee-'. representatives Ainspected 1the.: feedwater
_
? booster ; pump but= could;not' determine the ~ resson' it tripped.
The pump
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- was tested satisfactory and.the' plant. restarted.
v iThe Linspectorf reviewed the-plant's parameter's', conditions and the-
.
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-
(licens'ee's L post trip evaluation ~.and has no further questions 'on 'this
.
evente
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- 05 a.m'.",- on: November 22, control rod number 5 in rod group. number t, c,,
- 7' dropped into the re'actorccore. =Troublesho'oting of the affected rod's
power ; supply. revealed that;a problem existed with the control rod
.
'
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Edrive's i stator. l A1 plant shutdown ' was commenced to-replace the
~
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c.. defective f stator. ; At 1:01 p.m.
the reactor tripped on high RCS
]7 (pressureEfrom-approximately 18% power.
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eat 118% power 1 feedwaterJflow to the Once Through Steam Generators -
'
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wo o(OTSGs);is.normally' through their respective startup flow control-valve
',
- andilow' _ load control valve.
These two valves provide a parallel
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_flowpath toj the main;feedwater line to the associated 0TSG..0perators
- experienced excessive leakage through the startup flow control valve to
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- valve. ;The olow load control valve responded. sluggishly to the change
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fin' feedwater flow' to the'.0TSG resulting in a decrease in the "A" OTSG
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, #1evel.CThe 310w level in the A"' OTSG. tripped. the. Emergency Feedwater d -,
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~' iInitiation G and JControl l(EFIC).. system 'which started L the : emergency?
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2feedwater a pumps.1 1The additioniof ; coo 1E emergency.feedwater_ to the >.
- 0TSGs ? resulted :in aTslight power; excursion 1(18% to approximately 28% L e
i power)f and, contributed; to 'RCS temperature andi pressure: oscillati.ons. -
, (TheSoperators : secured the~ emergency,feedwaterlbecausenthe initiation
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isignal hadicleared, _ the-0TSG levels were. satisfactory, Land the reactor,
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3 gwasj at L powerswith; the 7 main c turbine * on : line.
After secur_ing the L
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iemergencycfeedwaterfsystem, the continued sluggish 1 response of the low
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dioad. controlt valve 1 caused level to again decreaselin tthe "A";0TSG.
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!cau' sing.thefreactor,to_ trip ~on high pressure.
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7The inspectorcarrived inithe control; room -shortlyf after the ! reactor.
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Ja tripi had. occurred ^and1 verified the status. of, safetv ' systems, plant-istatusJ and h plant (parameters.
The-_ inspectors also reviewed the'
Lli.censee's: post trip evaluation'.'
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' INoLviolatisns.'orideviations were identified.
'
,9k:Rev[ewofjIEhInformation'Noticel(IN80-21)..
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iThe[inhectobreNewed$ the' licensee's activitiesjwith respect to IN 80-21,
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" fAnchorage Tand/Supl rt of; Safety-Related Electrical Equipment. L As'a' result-
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>1 z fg this4 review,;th Sinspector.noted that the. licensee'did not address all"of~
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, rthe'_ itemsYdiscussed in.the(IN.
Specifica11y,'.the licensee!did not discuss
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Jort take anyf action to.lcontro11 ancillary items J(e.g., dollies, block ;and a
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! tackle igear,s scaffolding,lladders; jetc.): that{may be located in thelplant'
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- suchthattheycouldp'otentiallydislodgel, impact,1and-damagesafety.related'
~
equipment!duringian earthquake.
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zTh'ellidenseeD presentlyf had work ~goingion.in the plant that involves 'aslarge-nR
, 'amountJof gladders and scaffolding. :Thes'efscaffolding~and 1 adders are not
.
isecured. Land -have been observed lin the vicinityLof safety _ related equipment'.
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.
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7TheseLobservations were1 discussed :with the -licensee at which time: the?
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' $inspectorJnoted s that :the': licensee. has Eno apparent < procedures to cover
<controlfof these ccnditions.
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$hejlicensee;; will review! their actions' with-respect-to IN 80-21 and
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determineiwhat.: actions 1should.be' taken to control the use of ancillary
._
items.1
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cInspectorFoll'owup' Item (302/55-42-04): 'Rev'iew the 11censee's-activities.to-
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controls the L use.of ancillary items - (e.g., ladders. and. scaffolding).ini
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response to'IN 80-21.
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