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{{Adams
#REDIRECT [[05000278/LER-1989-006-04, :on 891023,during Reactor Temp Adjustment, Reactor High Pressure Scram Occurred.Caused by Improper Planning & Coordination of Multiple Evolutions.Surveillance & Hydrostatic Test Revised]]
| number = ML19332D340
| issue date = 11/22/1989
| title = LER 89-006-00:on 891023,during Reactor Temp Adjustment, Reactor High Pressure Scram Occurred.Caused by Improper Planning & Coordination of Multiple Evolutions.Surveillance & Hydrostatic Test revised.W/891122 Ltr
| author name = Cribbe T, Smith D
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000278
| license number =
| contact person =
| document report number = LER-89-006-04, LER-89-6-4, NUDOCS 8912010036
| document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT
| page count = 5
}}
 
=Text=
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I      N--        M"%b  A PHILADELPHIA ELECTRIC COMPANY PIACil BOl'II)M alt)MIC POWI'.R S'IX1'lON R. D.1, Ika 208                                  *
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Delta,Itnnsylvania' 17314                              .
nach morum-nir xman on txcruanct                          (717)456-7014--                              '[
          - D. M. Smith Vice President -                                                                                          i 4
4 "e ,
November 22, 1989
      .                                                                                  Docket No. 50-278
:' Document Control Desk                                                                        :
U.!S. Nuclear Regulatory Commission                                                          l Washington, DC 20555-
 
==SUBJECT:==
Licensee Event Report (LER)
Peach Bottom Atomic Power Station - Unit 3 i                              This LER concerns an unplanned Engineered Safety Feature (Reactor Protection System) actuation.
 
==Reference:==
Docket No. 50-278
                              . Report Number:          3-89-006 l Revision Number:        00 Event-Date:            10/23/89 Report Date:            11/22/89 Facility:              Peach Bottom Atomic Power Station RD 1, Box 208, Delta, PA 17314
                                            ~
i l                                This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(iv).
Sincerely, 1
;                        cc:      J. J. Lyash, USNRC Senior Resident inspector
;                                W. T. Russell, USNRC, Region I jfh20gggj$$              c s
 
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        ;;5      8 y  es tC te,m age i                                                                                                                      U.S Ga8CLEA2 6 Etut!.TWY COMMisseON
              ;  .                                                                                                                                    ' APPROvtD OMB NO 310..t.4 LICENSEE EVENT REPORT (LER)                                                      ' """' 8 ''3 0 "
i I                                                                                                                                                                                              I F ACILITY NAME (H                                                                                                          DOCE ST NUMStR (21                              PAGI (34      'J
      ' Peach Bottom Atomic Power Station'- Unit 3                                                                              o is t o l o l o l 217 l 8 1 loFl014                            ,
      "'''''' Reactor High Pressure Scram During Reactor Temperature Adjustment Due To Improper-Planning and' Coordination of Multiple Evolutions IVINT DAf t (SI                    LIR NUM84R (el                    REPORT DATI 17                      OTMth F ACILITits INVOLVED ten MONTH        DAY    YEAR    YEAR          ''0$$ g' h"'    [*f,*,$  MONTH      DAY  Y E Ar;            f actLe t hAuts                          DOCetti NUMBtHISI O15101010 1 1l
                                              -                ~
1l0        2l 3    8 '9    8l 9            0l0l6            0l0 1l1 2lP 8l9                                                                      0 1 5l0l0;O i -l                l THIS REPORT 18 BUSMITTEC PUR$UANT TO THE REQUIREMINTS OF 1. CFR l (ChecA one er more of ,ae rouperaffHU
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to 4 64.H1 Hist                        to.T3i.H21(si                    So.73t.H2 HvileHS 20 406taH1Het                        ' 50.T3taH2Hiid                    to.T34eil2He)
L8CENSEE CONT ACT POR THIS LER H2)
NAug                                                                                                                                                TE LEPHONE NUM86H Atti A CODE T. E..Cribbe, Regulatory Engineer 71 117                41516 l -l 7101114 COMPLEf t ONE LINE FOR EACM COMPONENT F AILURE DESCRISED IN TMiB REPORT 1131 R ORTA d                                                            ""      #C CAUSE      SYSTEM    COMPONENT                  'gAC.      o qpq g                        CAU50 systtY    COMPONENT                                  "fD NPR I        I I I              I I i                                                  l        i l I              l l I I        I I I              I I I                                                  I        I I I              I I I SUPPLEMENTAL REPORT EXPECTED H46                                                                              MONTH    DAY    VIAR SUBMIS$40N VES tir en.
v eavete EJtPECTED S'J0 MISSION OA TEI                              NO                                                                                              l l      l A..mCTm,.--,..,,......,,,...,_,,....,..,o.,
On October 23, 1989 at 0900 while performing a Hydrostatic test of the Reactor Pressure Vessel (RPV), RPV pressure and temperature were required to be maintained around 1000 psig and greater than 175 degrees Fahrenheit (F). RPV pressure and l'      temperature were being maintained by adjusting the Reactor Water Cleanup (RWCU) discharge to radwaste flow (192 degree.F water) to match the Control Rod Drive flow entering the vessel (65 degree F water). RWCU discharge to radwaste was reduced to l        maintain RPV drain temperatures above 175 degrees F. During this evolution, RPV pressure indication on the process computer display remained unchanged leading the l
Reactor Operator to believe RPV pressure was under control. The process computer,
      -however, had stalled'and was not providing updates, in actuality, RPV pmssure had l'      begun a 6 psi per minute increase. At 0939, reactor pressure reached 1056 psig and L      .the reactor scrammed on high pressure. The root cause of this event was inadequate planning and coordination of the multiple work activities being performed resulting in the RPV narrow range pressure recorder being out of service and the RPV high pressure alarm (1040 psig) being inoperable. As corrective actions: (1) a Unit Coordinator will be established to coordinate numerous work activities, (2) this                                                                                                        ,
event will be reviewed by appropriate Licensed Operators, and (3) the RPV Pressure Surveillance and Hydrostatic Tests will be revised to ensure the RPV narrow range pressure recorder is operable.
l NRC Fe.m 366
    . %D .              ,                . ,                                                                                    ,_          . - . -                                - - .
 
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                                                                                                                                                      ,q
        . (). :                                                                    -
                                                                                                                                  ,                    =;
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                                                                                                            . n Nucts AnioutAtoRv coMMmeioN                ,
m                              LICENSEE EVENT REPORT (LER) TEXT CONTINUATION -                                    emoveo ous Ro. mo-om                    !
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DOCML) NUMBER (21                    LER NUM8(R (0) -                      PA06 (3)
YEAR NW      Ab                                      ~
LPeach Bottom Atomic: Power Station
                                                                                                        " "'"            " '''                              i
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          -Requirements'for the' Report                                                                                                                ''
lThis report is required per 10 CFR 50.73(a)(2)(iv) because of an unplanned Engineered                                                          1 L            Safety Feature (Reactor-Protection System (RPS) (EIIS:JC)) Actuation.                                                                      -)
1 0            Unit Status at-Time of the Event Unit 3 Reactor Mode Switch (EIIS:HS) was in the Refuel position. Reactor Pressure Vessel (RPV):(EIIS:RPV) Hydrostatic (Hydro) testing was in progress..                                                                        ]
Unit'3 process computer-(EIIS:ID) had stalled -failing to update the most recent                                                          'l displayed plant parameter process variables.                                                                                                    '
i
:The RPV narrow range pressure recorder (EIIS:PR) was out of service.
            ' Unit 3 RPV high pressure alarm (1040 psig) was inoperable.
Description of the Event On October 23, 1989 while performing the RPV Hydro test procedure, RPV pressure and-temperature were required to be maintained around 1000 psig and greater than 175 degrees-Fahrenheit (F), respectively. RPV pressure was being maintained around 1000 psig to simulate normal operating pressure during the performance of Excess Flow Check Valve:(EFCV) (EIIS:V)_ testing per Surveillance Test (ST) 13.8-2 and Control Rod
          . Drive (CRD) (EIIS:AA) scram insertion time testing per ST 10.13. At 0930, the RPV drain (EIIS:DRN) temperature was-logged as required by ST 9.12-1 " Reactor Vessel                                                            ,
Temperatures" as decreasing to 179.7 degrees F. In' order to increase the RPV drain                                                          r temperature, the Unit 3 Reactor _ Operator (RO) (Utility, Licensed) bumped open MO            ~12-68-_" Unit 3~ Reactor Water Cleanup (RWCU) (EIIS:CE) Outlet Isolation Valve" increasing the RWCU recirculation flow of 192 degree F water back to the RPV which resulted in a decrease of_RWCU discharge to radwaste flow. The purpose of this action is to minimize the. amount of 192 degree F water being discharged from the RPV                                                      >
to offset the 65 degree F CRD water being supplied to the RPV. In a Hydrostatic condition a change in the mass flow rate of water either entering or being-discharged from the RPV will affect RPV pressure. During this evolution RPV pressure indication displayed on the process computer remained unchanged leading the R0 to believe RPV                                                          .
            . pressure was under control and therefore, it was not necessary to reduce CRD flow                                                          .
entering the vessel. The R0 did not realize the process computer was stalled, not                                                            ,
updating the displayed plant parameter process variables. In actuality, RPV
          -pressure had begun a 6 psi per minute increase. At 0939, reactor pressure reached 1055 psig and the reactor scrammed on high pressure. At the time of the scram the Control Rods were fully inserted. Seconds after the scram the RPV high pressure condition cleared. At 1122, the scram was reset.
            -Cause of the Event The root cause of this event was inadequate planning and coordination of the multiple work activities being performed resulting in the narrow range pressure recorder being out of service and the RPV high pressure alarm (1040 psig) being inoperable. A contributing cause associated with this event was the process computer stalling (not updating the displayed plant parameter process variables),
                                                                                                                        .u.. . co, i...mo. s.o ooo io gagrow a
 
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fm emC a Form astA ,
U S NUCLEA3 EE2WLt. TORY CceAMissioes
[                      ,
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION -                    mtovio ove No maiom                i
                ' _ '~                                                                                                (XPtRES: 8/31/WI -
F ACILBTY NAME (1)                                              Docetti NUE.R (2)            LtR NUMSER (6)                    PA0613)
              .Psach Bottom Atomic Power Station                                                  ^^"      "EW'            "UsN Unit 3 0 l5 l0 l0 lO l 2] 7l8 8l9 -
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fEXT (# mo,e space e soviewed, ese emanans/ MC Form JlsEA sf (In Inadequate planning and coordination ~1ead to multiple Control Room activities which                                                      ,
distracted the RO from monitoring other available RPV pressure indications. On going                                                      '
concurrent activities that the R0 was involved with during his shift included:                                        (a)
              . Control Rod Drive Stroking (performed by a second licensed RO), (b) troubleshooting L
              - RPV high' pressure alarm (1040 psig), (c) swapping CRD discharge filters (EIIS:FLT),
(d)troubleshootingM0-14-26B"CoreSprayFullFlowTest. Valve,"(e)EFCVtesting, (f)_RPV parameter readings every 15 minutes in accordance with (IAW) Technical Specifications (IS), (g) RPV parameter readings required every hour IAW TS, and (h)
Local Leak Rate Testing.
The RPV: narrow range pressure recorder and RPV high pressure alarm (1040 psig) were not operable at the time of'the event. Had the narrow range pressure recorc'er been available, it would ha'se been used to~ monitor RPV pressure. Because the narrow range-pressure recorder was out or service the R0 was using the process computer to monitor RPV pressure. During this event, however, the process computer was in a stalled condition (not updating the displayed plant parameter process variables) indicating a
              . pressure value corresponding to_the one at the time of the stall. There was no indication that the process computer had stalled, thus the R0 was unaware that the
              ' computer was not functioning.
I Additionally..had the RPV high pressure alarm (1040 psig) been operable the Operator would.have been alerted to a high RPV pressure condition and the scram may have been prevented. .The annunciator was inoperable because of incomplete maintenance activities.
Analysis of the Event No safety consequences occurred as a result of this event.
At the time'of the event, the Control Rods wcre fully inserted. The RPS initiated the scram signal and its logic functioned properly. Therefore, there were no adverse consequences.
The Main Steam Relief Valves (Ells:RV) were operable and could have functioned to terminate.the pressure rise.
This event would not have occurred at power because the initial conditions, in which the RPV is in a hydrostatic test condition maintaining pressure and temperature using the RWCU and CRD systems, would not be duplicated during power operations.
Corrective Actions The. role of Unit Coordinator will'be established and implemented. The responsibilities of the Unit Coordinator will be to coordinate numerous work e            activities to minimize their impact on the operation's shifts.
This avent will be reviewed by Appropriate Licensed Operators.
            , The Unit 2 and Unit 3 RPV Prer, ure Test STs (Check Off List (COL) ST 25.1-2 and COL 93T 25.1-3 "RPV Pressure Test Instrumentation") and the Unit 2 and Unit 3 RPV Hydro Test.STs (COL ST 25.2-2 and COL ST 25.2-3 "RPV Hydrostatic Test Instrumentation")
                                                                                                                            *V.S. CFO: 1988-520*$84i00070 5 43)
      .        -~          -      -          .-      _ _ _ _ _ , . . .                    .                                            -
 
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                    ,          -d a
      ,  efAC Poem EISA -                                                                                            U.S NUCLE A3 Et1ULATORY COMMISSMNu
                      .,                        LICENSEE EVENT REPORT (LER) TEXT CONTINUATION                              s,renovto ous No 3ino-oio4            -<
              , ' * .'"                                                                                                    EXPIRES: 8/31/M .
PACILITY 8sAME (1),                                                DOCKl1 NUMBER G)                LER NUMetR (Si                    PAOL (3)
Peach Bottom Atomic Power Station                                                  "'"    "UW ' YEO Unit-3' o l5 j o l0 l 0 l 217 l 8 819 -
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will be revised to ensure the RPV narrow range pressure recorder is operable prior to                                                          '
the commencement of a RPV Hydro test.
Previous Similar Events One previous'LER 2-85-02 was identified in which a high pressure scram occurred
'                  during.a RPV Hydro test and EFCV testing. The corrective actions in LER 2-85-02 r
would not have prevented this event because its cause was poor communications. The Control Room R0 increased CRD flow responding'to a pressure decrease caused-by a leaking EFCV. The Test Engineers stopped the EFCV leak without notifying the Control                                                            i
                  ' Room and.the subsequent rapid pressure rise resulted in a RPV scram                            .
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        / NRC FORM 366A                                                                                                        O 'J , 0 , CFOs 1988-5 M-504 W4}}

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