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{{#Wiki_filter:REGULA..Y INFORMATION DISTR IBUTl YSTEM (R IDS)ACCESSION NBR FACIL: 50-315 AUTH.NAME ALLARDI J.D.SMITHS W.G.RECIP.NAME 8707220579 DOC.DATE: 87/07/14 NOTARIZED:
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NO Donald C.Cook Nuclear Power Planti Unit iI Indiana 5 AUTHOR AFFILIATION Indiana u~Michigan Electric Co.Indiana 8<Michigan Electric Co.RECIPIENT AFFILIATION DOCKET N 05000315
 
==SUBJECT:==
LER 85-023-01:
on 850502I auxiliary bldg crane traveled over spent fuel pool w/heavy loadI contrary to Tech Spec 3.9.7.Caused bg misinterpretation of NUREG-0612.definition of"heavy load." Tech Spec 3.9.7 revised.W/870502 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR 1 ENCL j SIZE: 5 TITLE: 50.73 Licensee Event Report (LER)I Incident Rpti.etc.NOTES: REC IP IFNT ID CODE/NAME PD3-3 LA WIGGINGTQNI D COPIES LTTR ENCL 1 1 1 REC IP IENT ID CODE/NAME PD3-3 PD COPIES LTTR ENCL 1 1 INl ERNAL: ACRS MICHELSON AEOD/DQ*AEOD/DSP/ROAB DEDRO NRR/DEBT/ADS NRR/DEBT/ELB NRR/DEBT/MEB NRR/DEBT/PBB NRR/DEBT/SGB NRR/DLPG/GAB NRR/DR EP/R AB N NA LRB G-02 RES TELFQRDI J RQN3 F ILE 01 EXTERNAL: EGD<<G GROH>5 LPDR NSIC HARRISI J 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 1 1 1 ACRS MOELLER AEOD/DSP INAS AEOD/DSP/TPAB NRR/DEST/ADE NRR/DEST/CEB NRR/DESTI ICBB NRR I DEBT/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DQEA/EAB NRR/DREP/RPB NRR/PMAS/PTSB RES DEPY GI RES/DE/EIB H BT LOBBY WARD NRC PDR NSIC MAYBI Q 2 2 1 1 1 1 0~1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 43 NRC Form 355 (943)LICENSEE EVENT REPORT (LER)US.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3)600101 EXPIRES: 5/31/SS FAClLITY NAME (Il D.C.Cook Nuclear Plant, Unit 1 DOCKET NUMBER (2)PA E 3 o s o o o 315>0F 4 TITLE (CI Travel of Heavy Load over Spent Fuel due to NUREG 0612 misinterpretation EVENT DATE IS)YEAR YEAR NI MONTH DAY LER NUMBER (5)SEQUENTIAL CNS NUMBER REPORT DATE (7)OAY YEAR RB~MONTH NUMBER OTHER FACILITIES INVOLVED (5)DOCKET NUMBER(S)o s o o o3 16 FACILITY NAMES D.C.Cook-Unit 1 0 5 2 8 585 0 2 3 010 714 87 0 s 0 0 0 OPERATINO MODE (9)POWER LEVEL p p 0 II 0)Sr'jc arty"3 ,I)..0,.ks~~'t:: Sc 50.73(x)(2)(Ir)50.734)(2)(vl50.73(s)(2)(rB)9),73(s)(2)(rIB)(A)50.73(s)(2)(rIII)(5)50,73(~)12)(x)20.405(c)SOW(c)(I)50.35(cl(2) 50.73(s)(2)(I)50.73(s)(2)(B) 50.73(s)(2)BII)20.C02(B)20.COS(~)(I)(B 20A05(s)(1)(Bl 20.sos(s)(1)(III)20AOS(s)(1)(lv)20.405(v)(1)(v)LICENSEE CONTACT FOR THIS LER (12)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR ()t (Chock ons or mors ol Ills Iollortlnp)
(11)73.71(B)73.71(cl OTHER (Spsclly ln Aors'sct (Nlotrsnd In TsxL HRC Form 3SSAJ NAME J.D.Allard, Maintenance Superintendent TELEPHONE NUMBER AREA CODE 6 16 465-5 901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT I'13)CAUSE SYSTEM COMPONENT MANUFAC-TURER-EPORTABLE TO NPRDS r~: CAVSE SYSTEM COMPONENT MANUFAC.TURER TO NPRDS.x..g: xos I'.,...,., cL x x SUPPLEMENTAL REPORT EXPECTED (IC)YES (II yct, complctt EXPECTED SUBMISSIDIY DATEI NO ABSTRACT (Limit to lc00 tpscst, Is., spproxlmstsly 5!tscn tlnplscpscs typsrrrlttsn linctl HB)EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR On May 2, 1985 with the Unit 1 Reactor in Mode 6 (Refueling) and Unit 2 Reactor in Mode 1 (Power Operation) at 100 percent thermal power, the Auxiliary Building Crane traveled, unloaded, over the Spent Fuel Pool.This condition was contrary to Technical Specification 3.9.7 in that the crane's load block was at that time defined as a heavy load.The cause of this event has been determined to be the failure of Plant Personnel to recognize that the main load block on the Auxiliary Building Crane constituted a heavy load.It was believed that heavy loads were applicable to items being transported by the crane and not components of the crane.The corrective action taken was to change Technical Specification 3.9-7 by adding a footnote which defines the conditions necessary in order to place the main load block over the Spent Fuel Pool.'The preventive actions were to impose restrictions on the crane and provide training to the operators.
8707220579 870714 PDR ADOCK 05000315 S PDR NRC Form 355 tBWBI NRC Fono 38SA (94)3)LICENSEE E ENT REPORT (LER)TEXT CONTINUAT ON US.NUCLEAR REOULATORY COMMISSION APPROVED OMS NO.3180-0104 EXPIRES: 8/31/88 FACILITY NAME ll)OOCKET NUMBER (3)YEAR LER NUMSER (8)+~i SEQVSNTIAL
'I)xI/NVMSSR'~j'EVISION
'..: NVM SR PACE (3)D.C.Cook Nuclear Plant, Unit 1 TEXT/$44>>>><<>>c>>SI/4)MS'>>o aSSM>>o/NRC F>>RII 38M 3/(17)0 S 0 0 0 3 15 85 0 2 3 0 1 0 2OF0 Conditions Prior to Occurrence Unit One-Mode 6 (refueling) at 0 Percent Reactor Thermal Power Unit Two-Mode 1 (power operation) at 100 Percent Reactor Thermal Power Descri tion of Event I On May 2, 1985 during a review of NUREG 0612 requirements, it was determined that on occasion, between June 1982 and April 1985, the Auxiliary Building Crane's interlocks (EIIS/33)were defeated, allowing the Auxiliary Building Crane's main load block (EIIS/CRN) to travel over spent fuel assemblies in the Spent Fuel Pit (EIIS/RK).
This condition was contrary to Technical Specification (T.S.)3.9.7.The interlocks had been bypassed by the key-operated bypass switch (EIIS/HS)in order to allow the Auxiliary Building Crane to be used for normal maintenance activities such as retrieval of refueling tools (EIIS/FHM) from storage and maintenance of lighting fixtures over the Spent, Fuel Pit.At no time was any load carried over the Spent Fuel Pit on the main hook.During operations which resulted in traversing of the main hook over the pit area, virtually the same conditions subsequently required by the footnotes to T.S.3.9.7 were in effect.Although the main hoist breaker (EIIS/BKR) was not open, the hoist mechanism was never operated, therefore, it remained de-energized.
There were no other inoperable structures, components or systems that contributed to this event.Cause of Event The cause of this event has been determined to be the failure of Plant Personnel to recognize that the main load block on the Auxiliary Building Crane constituted a heavy load.It was believed that heavy loads were applicable to items being transported by the crane and not components of the crane.~t)RC FORM 3>>SA"(883)~USOPO:IOS(LO83A.S38/SSSIN NRC Form 388A)883)LICENSEE E NT REPORT (LER)TEXT CONTINUAT N US.NUCLEAR REOULATORY COMMISSION APPROVED OM8 NO.3160&104 EXPIRES: 8/31/88 FACILITY NAM E 11)DOCKET NUMBER I2)YEAR LER NUMBER)8).'san 8EOUENTIAL
%%1 NUM SII'Nr~IIEVISION N U M 8 8 II PACE 13)D.C.Cook Nuclear Plant, Unit 1 TEXT 13//Noro deco 8 ro0rkord Iso akN5wo/H/IC
%%drIII 38/A8/OT)o s o o o 31 58 5 023 0 1 0 30F 04 Anal sis of Event lt is concluded that this event is reportable per 10CFR50.73(a)
(2)(i)(B).Technical Specification 3.9.7 prohibited loads in excess of 2500 pounds to travel over fuel assemblies stored in the Spent Fuel Pit.The Auxiliary Building Crane's load block weighs 4.25 tons.The immediate preventive actions taken were to place additional administrative controls on the movement of the crane.The main hoist breaker was de-energized and a clearance permit taken to prevent operation of the hoist or the key operated bypass switch.Training sessions were held for all crane operators to reinforce the requirements of NURZG 0612 and T.S.3.9.7.Exxon Nuclear performed an analysis of a load block drop over the spent fuel assemblies and concluded that the damage to assemblies due to the drop of the load block would not cause a release of radiation exceeding the limitations imposed by 10CFR100.This load drop analysis was submitted to the NRC for review on January 9, 1987.Based on the results of the load drop analysis, Technical Specification 3.9.7 was changed by Amendments 79 and 93, adding a footnote which states;"This does not include the main load block, which weighs approximately 4.25 tons.Whenever the load block is moved over the pool, the'main hoist must be de-energized and be carrying no load." The changes made to Technical Specification 3.9.7 constitute permanent corrective measures.'NR C'PO'RM 1883)*U.S.OPOII 0880824438/1
: 66.
hRC Form 3BBA (083)LICENSEE E NT REPORT (LER)TEXT CONTINUATI N US.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31 I(6 FACIU NAME (1)DOCKET NUMBER (3)YEAR LER NUMBER (B)SEOVENTIAL rIVM ER%&#xc3;REVISION NVM ER PACE (3)D.C.Cook Nuclear Plant, Unit 1 TEXT (PIRoro N>>co Jr roBMBad oro aki5ans'NRC ForIII 3(ELBE)((7)0 5 0 0 0 3 l 5 8 5 023 0 1 0 4 OF 0 4 Corrective Actions The appropriate Plant Procedures have been modified to clearly indicate that the load block of the Auxiliary Building Crane is to be considered as a heavy load.Administrative controls regarding movement of the Auxiliary Building Crane over the Spent Fuel Pit have been strengthened.
Technical Specification 3.9.7 has been changed defining conditions required whenever the load block is moved over the Spent Fuel Pool, i.e.the main hoist must be de-energized and be carrying no load, Amendments No.79 and 93.Failed Com onent Identification None Previous Similar Events None identified at this time.N)IC FORM SOBA BALI)m ().SOP(3I198()4()
SI.S38/add,.
er4tsn leotrlo~ye/INDIANA I&MICIIIGA N ELEC 78IC COMPA N Y DONALD C.COOK NUCLEAR PLANT P.O.Box 456, Brldgemen, Ml 49106 Telephone (616)465 5901 July 14, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555'perating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:
85-023-01 Sincerely, W.G.Smith, Jr.Plant Manager WGS:afh Attachments cc: A.B.Davis, Region III R.C.Callen, MPSC D.Hahn, MDPH G.Charnoff, Esq.Dottie Sherman, ANI Library D.L.Wigginton, NRC Records Center, INPO J.E.Dolan M.P.Alexich R.W.Jurgensen H.B.Brugger NRC Resident Inspector PNSRC A.A.Blind R.F.Kroeger File J.G.Feinstein/B.
P.Lauzau}}

Revision as of 15:31, 23 October 2019

LER 85-023-01:on 850502,auxiliary Bldg Crane Traveled Over Spent Fuel Pool W/Heavy Load,Contrary to Tech Spec 3.9.7. Caused by Misinterpretation of NUREG-0612 Definition of Heavy Load.Tech Spec 3.9.7 revised.W/870502 Ltr
ML17325A210
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 07/14/1987
From: Allard J, Will Smith
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0612, RTR-NUREG-612 LER-85-023, LER-85-23, NUDOCS 8707220579
Download: ML17325A210 (6)
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