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| {{Adams
| | #REDIRECT [[05000321/LER-1980-069-01, HPCI Failed to Inject to Reactor Pressure Vessel After Receiving Auto Initiation Signal Due to Isolating on Steam Line High Dp.Caused by Poor Turbine Speed Control Calibr & Operability Procedures]] |
| | number = ML19320C587
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| | issue date = 07/10/1980
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| | title = /01T-0:on 800626,after Reactor Scram,Hpci Failed to Inject to Reactor Pressure Vessel Per Auto Initiation Signal Due to Isolating on Steam Line High Dp.Caused by Turbine Controls Being Out of Dynamic Calibr
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| | author name = Coggin C
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| | author affiliation = GEORGIA POWER CO.
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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| | docket = 05000321
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| | license number =
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| | contact person =
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| | document report number = LER-80-069-01T, LER-80-69-1T, NUDOCS 8007170419
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| | package number = ML19320C582
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| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
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| | page count = 2
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| }}
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| {{LER
| |
| | Title = /01T-0:on 800626,after Reactor Scram,Hpci Failed to Inject to Reactor Pressure Vessel Per Auto Initiation Signal Due to Isolating on Steam Line High Dp.Caused by Turbine Controls Being Out of Dynamic Calibr
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| | Plant =
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| | Reporting criterion =
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| | Power level =
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| | Mode =
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| | Docket = 05000321
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| | LER year = 1980
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| | LER number = 69
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| | LER revision = 1
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:11)
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| LICENSEE EVENT REPORT CONTR!L DLOCK: {
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| l l
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| l lh (PLEASE PRINT Oil TYPE ALL REQUlnED INFCRMAllON) o 2 l a] Al El Il IIl 1l@l o l o l -l 0 l 0 l o l o j o l - o l 0 l@l 4l 4 Il :l1l@l l
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| lg v
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| 2h 26 LICENbE 1YPE JO bl CAT 68 8 O LICENSEE CODE 34 l'
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| LICENSE P4UMuEll alil
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| ''s "J L1.j@l o f s i o l 01013121il@loI61216lalol@lolylijolo10 1@
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| ON'T 68
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| &J EVENT DAT E 34 lb HEPollT D AT E 80 S | |
| 60 64 OOCK E T NUMUEH 6
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| EVENT DESCRIPTION AND PRC9AULE CONSEQUENCES h a l2l l Following a reactor scram on June 26, 1980, IIPCI failed to inicct to the l
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| l RPV after receiving an auto initiation signal due to isolating on steam 013 l l l
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| 0141 l line high dP, reportable per Tech Spec 6.9.1.8.a. The isolation was reset There were no l
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| and !!PCI auto initiated and controlled RPV water 1cvel.
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| o 151 l ADS, Core Spray l
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| cf fccts upon public health and safety due to this event.
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| o ls l l RCIC was inoperable. There was no impact on Unit l
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| ol7]l and LPCI were operable.
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| II. This is a repetitivo event, reference LER 50 -321/1980-o49.
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| l 80 o la l l COM P-VALVE SYSTEM
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| ==CAUSE==
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| CAUSE CODE CODE SUSCODE COMPONEN T L SDE SUSCODE SUSCOOE SI elO LoJ@ l z l@ Iz Iz I z Iz Iz Iz l@ L3J@ IM @
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| .o191 i
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| 18 19
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| .3 f
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| 8 9
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| 10 11 12 33
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| . OCCURRENCE HEPORT FIEVISION SE QUENTI AL EVENT YE AR REPORT NO.
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| CODE TYPE NO.
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| O gg,'R/RO lejol
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| [_j jol6l9l [gj jo ll l l Tj l_l [oj EEg;
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| _2D 22 23 24 76 27 23 29 30 3I 32 XEN A N
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| O PL NT ET 4 HOUllS S BP ITT F0F Ib B.
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| U Lt MAN FACTUnER l_1jj h l G l h (34_C,jh l36,C_jh l/ol3lol6l WQ l Nl@ WQ l Z l9 l9 l9 l@
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| J 40 41 42 43 44 47 JJ 34 CAUSE DE ;CRIPTION AND CONNECTIVE ACTIONS
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| !!PCI isolated on high steam line dP due to poor turbine speed control l
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| l l0l l l
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| caused *by turbine controls out of dynamic calibration. The system was l1 li l l Procedures are being l
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| calibrated to yield satisfactory dynamic response.
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| g, l ;, l l Cold quickstarts of IIPCI and l
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| lil3l l revised to assure proper system response.
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| t 4 l
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| RCIC are scheduled.
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| An update report will be submitted l
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| 80 7
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| 8 0 A S
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| % POWER OTHER STATUS IS IY DISCOVEHY DESCRIPTION [T]T] y@ l 0 l 0 l 0 l@] Scram Transient l lAl@l Operator observation l
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| LOCATION OF RREASE @
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| CO0 TENT AMOUNT OF ACTIVITY @ l ACnVITY NA l
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| NA l
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| RREWO OF RREASE li lc 1 Lz.J O I zl@l 80 44 45 7
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| 0 9 10 ti PEHSONNE E EXPOSUHES NUMilEn TYPE
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| ==DESCRIPTION==
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| l l i l il l 0 l 0 l 0 l@[ zj@l NA PEnSO~Ntt'iNaunS otSCniPnO~@
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| l l
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| NuMun NA lo jo lo l@l i n 80 7
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| 8 9 31 32 E OSS OF OH DAMAGE TO FACILITY l
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| TYPE DESCillPilON
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| "^
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| LzJ@l i 9 80 C 9 10 l2lnl hl Atlanta Journal-Constitution on June 20, 1980 l
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| lllllllllllllj l 9%Ut l
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| >ESCntPilON 68 69 80 E l 8 0 0 717 0 @[* L* Co99 n 9'12-367-77a1
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| ", l a
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| 8 O D 10 i
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| PilONE:
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| {-_
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| NAME OF PRFPAREll U
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| =
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| =NARRATIVE=
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| REPORT Georgia Power Company.
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| Plant E.
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| I. Hatch Baxley, Georgia 31513 Reportable Occurrence Report No. 50-321/1980-0G9.
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| On June 26, 1980, Plant Hatch Unit I reactor scrammed from a main turbine stop valve fast closure following a turbine trip.
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| The llPCI 'ystem received an auto initiation signal on low reactor water level but failed to inject to the RPV_due to isolating on a steam line high dP isolation signal.
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| This is a failure of a system subject to limiting safety system settings to complete
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| ~
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| ~
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| the required protective function, _ reportable per Technical Specifications 6.9.1.8.a.
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| The isolation was reset and when the inboard isolation valve was opened, the outboard isolation valve received another steam line high dP isolation cignal. The isolation was reset, the isolation valves opened and.HPCI auto started and injected to the RPV and was used to control water level.
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| ADS, Core Sptay and LPCI systems were operable.
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| The RCIC system was inoperable. There were no effects upon public health and safety due to this event. There was no impact on Unit II.
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| This is a repetitive occurrence as last reported on Reportable Occurrence Report No. 50-321/1980-049.
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| She isolation, due to steam line high dP, was determined to be caused by poor turbine speed control due to the turbine control system being out of dynamic calibration.
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| System calibration was affected over a period of time by the replacement of control system components which were statically calibrated.
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| System operability tests to verify pump rated flow and discharge pressure and quickstarts to verify time to rated flow did not adequately monitor the llPCI system dynamic response to auto start transients.
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| Following extensive testing, including manual starts and quickstarts of the HPCI system and recalibration of the llPCI turbine control sytems, the !!PCI system demonstrated satisfactory performance during hot quickstarts.
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| Cglibration, surveillance and operability procedures are being revised to [nclude quickstart test for both Unit I and Unit II IIPCI and RCIC systems.
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| In addition, performance testing procedures to monitor IIPCI and RCIC system performance are being developed and will be utilized to assure continued satisfactory system dynamic response.
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| Cold quickstarts of the Unit I IIPCI and RCIC systems are scheduled to be performed prior to placing the generator back on line.
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| An update report will be submitted following these tests.
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| ~
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| ~
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| }}
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| {{LER-Nav}}
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