ML19270G373: Difference between revisions

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:                                                                L.lCENSEE EVENT codnot otock: I                    l    l    l  l    l      l@                    (ettASE PRWT OR TYPE ALL REQUIRED IMORMAUOM i                                .
:                                                                L.lCENSEE EVENT codnot otock: I                    l    l    l  l    l      l@                    (ettASE PRWT OR TYPE ALL REQUIRED IMORMAUOM i                                .
[[G      8 9 l A l LICENSEE E l I l11    CODE l 2 14l@l0 10 - l 0 10 15 l0 10 10 l- l0 10 l@l4 l 1 LeCLPest LICLrest NuMastH                            J 's      to l 1 l 11 ls et1Jol@lSi LAI  l ts l@
((G      8 9 l A l LICENSEE E l I l11    CODE l 2 14l@l0 10 - l 0 10 15 l0 10 10 l- l0 10 l@l4 l 1 LeCLPest LICLrest NuMastH                            J 's      to l 1 l 11 ls et1Jol@lSi LAI  l ts l@
l 6r E
l 6r E
8 Zns[L_J@l0l5101010131616l@l01511 6J            61          DO ALTP.U*.*UEH                tA    b'J 14    17 19 l@ l 01 51NLPOH EVENT DATL                24      7b 2l 11      71 94#0 @
8 Zns[L_J@l0l5101010131616l@l01511 6J            61          DO ALTP.U*.*UEH                tA    b'J 14    17 19 l@ l 01 51NLPOH EVENT DATL                24      7b 2l 11      71 94#0 @

Latest revision as of 12:35, 16 March 2020

LER 79-034/01T-0 on 790514:instruments in Remote Shutdown Panel H21-P173 & Heating,Ventilation & Air Conditioning Panels H11-P654 & H11-P657 Did Not Meet Seismic Requirements.Caused by Installation Error.Proper Instruents
ML19270G373
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/21/1979
From: Thomas Greene
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19270G371 List:
References
LER-79-034-01T, LER-79-34-1T, NUDOCS 7906060227
Download: ML19270G373 (2)


Text

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L.lCENSEE EVENT codnot otock: I l l l l l l@ (ettASE PRWT OR TYPE ALL REQUIRED IMORMAUOM i .

((G 8 9 l A l LICENSEE E l I l11 CODE l 2 14l@l0 10 - l 0 10 15 l0 10 10 l- l0 10 l@l4 l 1 LeCLPest LICLrest NuMastH J 's to l 1 l 11 ls et1Jol@lSi LAI l ts l@

l 6r E

8 Zns[L_J@l0l5101010131616l@l01511 6J 61 DO ALTP.U*.*UEH tA b'J 14 17 19 l@ l 01 51NLPOH EVENT DATL 24 7b 2l 11 71 94#0 @

T D AT E EVENT DESCRIPTIOPJ AND PROGABLE CONSEQUENCES h E I During a cold shutdown while reviewinq instrumont calibration procedures using Is tru- 1 g i ment Data Sheets (IDS) It was discovered that three instruments in the remote sht.t- l ,

i' E I down panel ll21-Pl73 [2T48-R070 (torus water level indicator), 2T48-R071 (dryaell ores-1 E I sure indicator), 2 Ell-R071 (RHR Service water flow indicator)1 and six instruments

  • l l

E I at the HVAC panels Hll-P654 and Hil-P657 in the ma'in control room [2T48-R622A and 1 El B (torus water level indicator), 2T48-R631 A and B (drywell pressure indicator), and I I'

l 2T48-R632A and B (torus pressure indicator) did not have the (continued) l ..

83 .

DE CO E SveCO E COMPONENT CODE SUSCODE SU OE  ! '

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9 to 11 12 13 18 to 20 l

,,. SE QUE N TI AL OCCUR RE NCE REPORT REVISION LER EVf f4T YE A R REPORT P.O. CODE TYPE NO. ,

O ,atg' u AO l719lu [---J l 0 l 3141 y l0 l1 l lTl l-l 10l

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T 'A$TY$s! cSe#LAST , NE HOvns 22 #s Se#EIT N r $ U s. #"'5'PLTE7 $ MAN A A l

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h . -

%l The transmitters to this instrumentation was chanced out to seismically aualified l

@l instruments, but the seismic indicators were inadvertently left unchanced due to I

gl incomplete review of the blant documentation and FSAR in asst; ring that all commit- l

@l ments were fulfilled prior to initial fuel loading. The Siara Instruments, Inc. I EI8 9 (continued) l 5 80 D:SCOs RY 5A S  % PO.'!E R OTHEFt ST ATUS Ot%COsERY DESCRIPTION

] [G_J@ l 0101 Ol@l" N/A l Bi@lProcedure and focument review l

' ' " 8 i A!TiviTy CO0 Test ,

= Elf ASED OF RELE ASE LOCATCP4 0F RELE ASE @

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AMOUNT N/A Or" ACTivtTY l

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l i eERsonsEl ExposOEs 1 uu .,e E R TveE cEsCRirTiOs@

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1010101@l 8 9 11 12 N/A 80 l

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L055 T,rE OFo EOR sC m,DAP.9 nO~ ACE TO FACILITY 042 7oosoeo p 7 N/A [

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Tal ,m0, @0E CR ,nOn

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@ N/A N AC UsE ONLY lllll1llllI1l5 L1 3 9 to 68 69 80 ~

NAME OF PDEPAREH T. V. Greene, Sunt. Plt. Eng. Serv. ,, , 912-367-7781 f

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Georgia Power Company I Plant E.. I. Hatch Baxley, ; Georgia 31513 Event Description and Probable Consequences (continued) I instruments installed as designated by Bechtel Po.<er Corporations's lat- I est design. The installed instruments were General Electric model 180 meters which did not meet seismic requirements as did the Sigma Instrum- .,

ents Inc. instruments later prescribed by Bechtel, the FSAR subsection ,

6.5.l.3.2 filed with Amendment 22 in May,1979, and the response to ftRC question 221.56 in the FSAR. .

There was no significant consequence from this event so far as safety or operability is concerned since the installed instruments did meet all quality assurance requirements except for seismic qualifications and there-fore were available. The instruments were not required to be operable at the time that the condition was' discovered because the reactor was al-ready in a cold shutdown.

Cause Description and Corrective hetions (continuet) f f

instruments which are now on site will be verified to meet the quality I assurance requirements, and they will be installed pri;r to startup of i Unit 2. ,

e 2274 279 i

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