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Forwards AO-14-74.Detailed Event Analysis Encl
	ML20031C294
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/23/1974
From:	Sewell R; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Oleary J; US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20031C295	List: ML20031C294; ML20031C302;
References
	10079, NUDOCS 8110070034
	Download: ML20031C294 (6)
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Hr. John F. O' Leary, Director Re: Docket 50-155 Directorate of Licenair.g License DPR-6 US !.to=ic Encrcy Cct.21ssion k'ashington, DC 205h5

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Dear P.r. O' Leary:

Attached is a ecpy of r.n abnormal occurrence report for the

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Big Rock Point Phnt.

Yours very truly,

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F23/ce Ralph B. Sevel) nj W

Uuclear Licensing A &inistrator M

CC: JGKeppler, USAEC E

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Report flu =ber - AD-lh-74 Docket 50-155 2a. Repor t Date - I'.ay 23, D7h 2b. Occurrence Date - !.ay 7,1974 (C1'issified as Abnornal occurrence on May 13, 1974) 3 Facility - Big Sock Point h.

Identification of Occurrence - Controllen Increa:e in Reactor Power 5

Condition: Prior to Occurrence - Increasing Reactor Output Following a Refueling Outage 6.

Description of Occurrence - The reactor power was being increased r.t a rate preceribed by written operating procedures. Tne reactor engineer's instructions in the daily order book were as follows: Following out-of-core flux calibration while at 160 IGT (100 percent en the picos to be set equivalent to 220 !GT) the power level should be increased to 200 7

l#T and held.

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w The power level vas increased to creater than 200 lL*f about 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months T&c on May 4, 197k. The power was inerenced to r. bout 220 MT during that A'i shift nnd the chift cuperticor was nade aware of the incrence acove E

200 lGT ct about 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months . The situation was reviewed by the reactor y

engineer when he reported for work at r_ bout 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months . The pc:Or level O

vas reduced co:rencing at 0611 hears so that flux vire irradiation for 9_.[

in-core calibration could proceed at the previously prescriben power g

level.

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Designation of Cause - Operator Error. Due to a nisunderstanding of k

verbal in tructions, the control operators increased the power level Q

to 100 percent using the out-of-core flux ronitors as a guide.

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Analysis of Occurrence - Duriig power escalction folleving c refueling, h;;

the reactor power level is conservatively increased in step fashtun to BN allov irradiation of flux vires for in-core neutron flux nonitor cali-

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bratio.. at a significant power level prior to escalation to the pro-64

.jected full power level, hp M

Wire irradition data is used to verify calculated c.xial power dittribu-M tion as a core perforretace check. Analycin of the !&y 9-10 flux vire M"-/

data at 200 !"iT revealed cood correlttion with expected axiti flux pro-M files. No technical cpecification van execeded.

L'e feel that no undue M

hazcrd existed tcccuse of this occurrence.

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2 ABNOR"A1, OCCURRE?:CE REPORT

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Big Rock Point Plant (Contd) 9 Corrective Action - The reactor power was reduced to 200 KdT after review of the situation by the reactor engineer. Subsequent action includes:

a.

Initiate use of a calibration sticker for the out-of-core flux monitor recorders to include the current heat balance calibra-tion data.

e b.

Require a review of the incident with all shift supervisors and operators.

c.

Revise the appropriate procedures and checklists to reflect the power escalation instructions for future ste.rt-ups.

Item a is now in use and detailed instructions are being processed.

I Item b is being implemented.

Item e is being initiated for approval.

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Failure Data - Not Appliccble C

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. u.cmo, moi. 4,.. coc. su 1..osso Hay 23,19Th Mr. John F. O' Leary, Director Re: Docket 50-155 Directorate of Licensing License DPR-6 US Atomic Pr.ercy Cc=ission k'achington, DC 205h5

Dear Mr. O' Leary:

Attached is a copy of an abnor a1 cecurrence report for the kh h

Big Rock Point Plant.

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n Yours very truly, mKW ni:

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RBS/ce Eciph B. Sewell Nuclear Licensing Administrator p

CC: JGKeppler, USAEC

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AB:10F5dOCCURRE'ICEREPORT M0M

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Report liumber - A0-lk-74 ~ Docket 50-155; 7

2a. Report Date - May 23,197h 2b. Occurrence Date - May 7,1974 (Classified as Abnormal Occurrence on May 13,197h) 3 Facility - Big Rock Point 4.

Identification of Occurrence - Controlled Increase in Reactor Power 5

Conditions Prior to Occurrence - Increasing Reactor Output Following a Refueling Outege 6.

Description of Occurrence - The reactor power was being increased at a rate prescribed by written operating procedures. The reactor enginecr's lastructions in the daily order book vere as follows: Following out-of-core flux calibration while at 160 INT (100 percent on the picos to be set equivalent to 220 IMT) the power level should be increased to 200 If4T and held.

The power level was inercased to greater than 200 f.'WT about 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months on 1:ay 4,1974. 'nte power was increased to about 220 !NT during that shift and the chift supervisor was made avarc of the increase above M

200 !%T at about 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months . The situation was reviewed by the reactor l"M engineer when he reported for work at about 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months . The power IcVel N3 was reduced co:::encin;; r.t 0811 hours0.00939 days 0.225 hours 0.00134 weeks 3.085855e-4 months so that flux vire irradiation for I; %]

h in-ccre calibration could proceed at the previously prescribed power level.

6;1 7

Designation of Cause - Operator Error. Due to a misunderstanding of vertal in:tructions, the control operators increased the power level

' 'fp to 100 percent using the out-of-core flux conitors as a guide.

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Analysis of Occurrence - During pcVer escalation following a refueling, gg the reactor pcVer level is conservatively increased in step fashion to tf allow irrad'.ation of flux vires for in-core neutron flux r.onitor cali-y,-j bration at a significent power level prior to escalation to the pro-jfp jected full power level.

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1172 Wire irradition data is used to verify calculated axial power distribu-M tion as a core perforrance check. Analysis of the !.'ay 9-10 flux vire y

data at 200 l~47 revealed good correlatica with expected axial flux pro-ua files. Ilo technical specification was exceeded. We feel that no undue hazard existed becau c of this occurrence.

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/00 71 AE"0P".AL OCCUEur!CE REPORT Big Rock Point Plant (Contd)'

9 Corrective Action - The reactor power was reduced to 200 MIf after reviev of the situation by the reactor engineer. ~ Subsequent action includes:

a.

Initiate use of a calibration sticker for the out-of-core flux monitor recorders to include the current heat balance calibra-tion data.

b.

Require a review of the incident with all shift supervisors and operators.

c.

Revise the appropriate procedures and checklists to reflect the power escalation instructions for future start-ups.

Item a is nov in' use and detailed instructions are being processed.

Item b is being implemented.

Ite::t c is being initiated for approvcl.

10.

Failure Data - Not Applicable

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ML20031C294

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Dear P.r. O' Leary:

Dear Mr. O' Leary:

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