ML20084T887
| ML20084T887 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/30/1976 |
| From: | Fox H TENNESSEE VALLEY AUTHORITY |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20084T892 | List: |
| References | |
| LER-BFRO-50-259-761, NUDOCS 8306240247 | |
| Download: ML20084T887 (3) | |
Text
LICENSEE EVENT REPORT CONTROL BLOCK:l l
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LEA".E PR1 hit ALL REQUIRED INFORMATION) 1 6
TYPE UCENSE NUMBER AME l AlL lB lR lF l1 l l0 l0 l-l0 l 0 l 0 l 0 l 0 l-l 0.l 0 l l 4 l 1 l1 l1 l1 l lOl1l o1 25 26 30 31 32 7 89 14 15 TvYE OCCKET AUV8ER EVENT OATE RE OATE O 1 CGNT l l
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[0 l5 j0 l-l Ol 215 l9 l l0 l9 l2 l217 l6 l l
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5J CATECORY 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESC;tPTION While bringing the reactor to rated pressure and temperature, the heatup l
gl 80
' rate of 100 degrees per hour as specified in Technical Specification 3.6.A.1 l
7 89
-@ l 80 7 39 l
ll l was exceeded.' (BFRC-50-259/761%
80 7 89 l
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MA t U R VOLATON dEE CODE COMPONENT CODE
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48 7 89 10 11 12 17 43 44 47 CAUSE DESCR'PTION l
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See attachment.
80 7 89 l
@l 83 7 89 l
bl 7 89
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% FOWER OTHER STATUS O SCO ERY OfSCOVERV OESCRPTON h
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l Al l Routine startup surveillance l
80 7 8 9
10 12 13 44 45 46 LOCATON OF F.ELEASE A LE SED CF LEASE AMOUNT OF ACTMTV I
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I ta 80 7 8 9
10 11 44 45 FERSONNEL EXPOSURES NUMBER TYPE DESCA.PfiON l
DE lO (O lOl l zl l ?M 60 7 89 11 12 13 V.
PERSONNEL INJUA.ES l
PauMetR CESCR F TON DE I lo lo l I ra 7 89 11 12 OFFSITE CONSECUENCES l
8l NA 7 89 1
LOSS CR OAMACE TO FACILITY 8306240247 760930 Tvrt DEsCmPTON PDR ADOCK 05000259 j
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PDR 7 89 10 DUBLICITY f
bl IE so 7 69 ADDITIONAL FACTCPS l
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ATTACIDENT CAUSE DESCRIPTION As control rods were being pulled and bypass valves were opening, the operator noticed the pressure was reaching a point where the condensate booster pumps could not supply water to the vessel. The reactor pressure was not high enough to get reactor feed pump in service. The operator increased the pressure regulator setpoint to reduce the steam flow and maintain proper water level.
This resulted in a heatup rate that exceeded the technical specifications value of 100 F/ hour.
ADDITIONAL FACTORS ine Technical Specifications and Operating Instructions associated with reactor heatup will be reviewed by all licensed personnel.
An analysis will be performed and vesselusage not considered in the original design will be added 1,o I,he cumulative usage for the vessel.
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o otuncm a-TENNESSEE VALLEY AUTHORITY 5g CHATTANOOGA. TENNCSSEE 374ot t>
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septo:.tber 30, 1976 DCT 5 1976 4
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esiksens Cb Mr. lior an C. Monoloy, Director U.S. I?nclear Ec3nlatory Corsiasion 4
6 Offico of Inapection and Enforcenent N
1 Region II 230 Feachtree Street, IM., 8th Floor
'ta, Georcia 30303 Doe Mr. Moseley:
T.CEIESSEE VALLEY AUDIORITY - BRtNH3 FERRY ITUCLEAR FIAITf UNIT 1 -
DOCKET 110 50-253/ - FACILTW n%ATIIU LICEIi3E DPR REPORTABLE OCCURREiCE REPORT Ba M -25)/7blD Tho enclosed report is to provido de' tails concerning the heatup rate of 100 decrees por hour as specified in the technical speci-fications that was exceeded while bringing the reactor to rated prosauro and toaporature. Ulia report is sui.:itted in accordance with Hro.ma Furry Technical Grecifications section 6.
itlia event occurred on Browns Ferry Ifuelcar Plant unit 1.
j Very truly yours, TEIRESEE VALLEY AUDICRITY I
I I
H. 8. Fox Director of Power Production Enclosure (3) i CC(Enclosure):
Director (3)
Offico of Manag acnt Infomation and FrogInn Control U.S. Huclear P ;ulatory Coanission Washington, D.C 20555 d
Director _(ho)k Offico of Innpoetion and Enforcoaont U.S. Iluclear Regulatory Couraission Washington, D.C.
20555 1
10114 I
copy SENT REGION
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An Equal Opportuoity Employer I
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