ML19326C127
| ML19326C127 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/26/1976 |
| From: | Mardis D ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326C126 | List: |
| References | |
| NUDOCS 8004210502 | |
| Download: ML19326C127 (4) | |
Text
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i 7 89 80 NAME:
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PHONE: {Sd/ 37/ ~ N N S r.P O 469 667
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Reportahic occurrence Report th>.
50-313/76-17 2.
Report Date:
7/26/76 Occurrence Date:
7/14/76
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FaciIity:
Arkansas Nuclear One-Unit 1 l
Russellville,, Arkansas I
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Identification of Occurrenec:
Exceeding power level cutoff (82.5%) without proper xenon reactivity conditions per Technical Specification 3.5.2.5.4.
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Conditions Prior to Occurrence:
Steady-State Power Reactor Power _
NWth llot Standby Not Output MWe t
Cold Shutdown Perecnt of Full Power
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Refueling Shutdown Load Changes During Routine Power Operation 57% to 95%
Routine Startup Operation Routine Shutdown
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Operation 1
Other (specify]
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Description of Occurrence:
,t At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on July 14, 1976,. it was identified that the Reactor Power Level cutoff was exceeded at approximately 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on July 13, 1976, without proper: xenon reactivity worth (xenon worth was not within 10%.of
,l full power equilibrium value by 0.09% AK/K and power IcVel was increased approximately 50 minutes carly).
The reactor power had been reduced from 99% power commencing at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on July 13, 1976, to 57% to remove "B" Main Feed Pump from service to repair a lube oil leak. Power was held at 57% until 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> j
following repairs to Feed Pump, at which time power was. increased. At
.approximately 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> power was taken above 82.5%.
v Attachuent "C"
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!! arch 23,1976 NSP-10 Rev. 4 Page 2 of 4
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!!eport able Occurrence i!cport No.
50-313/76-17
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Designat ion o f Appa rent Cause of Occurrence:
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Design Procedurc l,-
i thnu fac t urc Unusnai Service Condit ion including I!nvi ronmental Installation /
)I' Construction Component Failure t
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Operator X
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Other (specify) i The operator misinterpreted the xenon worth from the computer calculation of xenon worth.
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Analysis of Occurronec:
There was no reactor core safety significance associated with.this occur-j rence.
Reactor Coolant Iodine samples were within normal range on i
7/14/76 and 7/15/76.
Due to the small amount of xenon worth involved (0.09% AK/K)', this incident did not affect the health and safety of the
- public, i
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Attnehment "C"
Ma rch 23,.1976 f4SP-10, Rev. 4 Page 3 0f 4 d
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-s j-Neportable decurrence Report ilo.
'50-313/76-17 10.
Corrective Actioni:
ll' Thisincidentwasdiscussedwiththeoperatorsinvolvedandtiteshift
' l, supervisors of the other operating crews for discussion with their respective crews. The determination of proper xenon reactivity will
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l also be stressed during requalification training.
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Failiarc Dat:::
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None.
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/it tricliirteilt "C" 4treli 23, 1976 NSP-10. Itev.
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