ML17325A210

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
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)

Text

REGULA .. Y INFORMATION DISTR IBUTl YSTEM (R IDS)

ACCESSION NBR 8707220579 DOC. DATE: 87/07/14 NOTARIZED: NO DOCKET N FACIL: 50-315 Donald C. Cook Nuclear Power Planti Unit iI Indiana 5 05000315 AUTH. NAME AUTHOR AFFILIATION ALLARDIJ. D. Indiana u~ Michigan Electric Co.

SMITHS W. G. Indiana 8< Michigan Electric Co.

RECIP. NAME RECIPIENT AFFILIATION

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 TITLE: 50. 73 Licensee Event Report (LER)I Incident j

Rpti .

SIZE:

etc.

5 NOTES:

REC IP IFNT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 PD3-3 PD 1 1 WIGGINGTQNI D 1 1 INl ERNAL: ACRS MICHELSON ACRS MOELLER 2 2 AEOD/DQ* AEOD/DSP INAS 1 AEOD/DSP/ROAB 2 2 AEOD/DSP /TPAB 1 1 DEDRO 1 1 NRR/DEST/ADE 1 0 NRR/DEBT/ADS 1 0 NRR/DEST/CEB ~ 1 1 NRR/DEBT/ELB 1 1 NRR/DESTI ICBB 1 1 NRR/DEBT/MEB 1 1 I NRR DEBT/MTB 1 1 NRR/DEBT/PBB 1 NRR/DEST/RSB 1 NRR/DEBT/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DQEA/EAB 1 1 NRR /DR EP /R AB 1 NRR/DREP /RPB 2 2 N NA LRB 1 NRR/PMAS/PTSB 1 1 G - 02 1 1 RES DEPY GI 1 1 RES TELFQRDI J 1 RES/DE/EIB 1 1 RQN3 F ILE 01 1 EXTERNAL: EGD<<G GROH> 5 5 5 H BT LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRISI J 1 1 NSIC MAYBI Q 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 43

NRC Form 355 US. NUCLEAR REOULATORY COMMISSION (943)

APPROVED OMB NO. 3)600101 EXPIRES: 5/31/SS LICENSEE EVENT REPORT (LER)

FAClLITY NAME (Il DOCKET NUMBER (2) PA E 3 D. C. Cook Nuclear Plant, Unit 1 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) LER NUMBER (5) REPORT DATE (7) OTHER FACILITIES INVOLVED (5)

MONTH DAY YEAR YEAR NI SEQUENTIAL CNS NUMBER RB~

NUMBER MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S)

D. C. Cook Unit 1 o s o o o3 16 0 5 2 8 585 0 2 3 010 714 87 0 s 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR ()t (Chock ons or mors ol Ills Iollortlnp) (11)

MODE (9) 20.C02(B) 20.405(c) 50.73(x)(2) (Ir) 73.71(B)

POWER 20.COS( ~ ) (I )(B SOW(c)(I) 50.734) (2) (vl 73.71(cl LEVEL II0) p p 0 20A05(s) (1)(Bl 50.35(cl(2) 50.73(s) (2) (rB) OTHER (Spsclly ln Aors'sct arty "3 (Nlotrsnd In TsxL HRC Form Sr'jc 20.sos(s) (1)(III) 50.73(s) (2)(I) 9),73(s) (2) (rIB)(A) 3SSAJ 20AOS(s) (1)(lv) 50.73(s)(2)(B) 50.73(s) (2) (rIII)(5)

,I).. 0, .ks~~'t:: Sc 20.405(v)(1) (v) 50.73(s) (2) BII) 50,73( ~ )12)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE J. D. Allard, Maintenance Superintendent 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:

I xos

, cL x x

'.,...,.

SUPPLEMENTAL REPORT EXPECTED (IC) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)

YES (II yct, complctt EXPECTED SUBMISSIDIY DATEI NO ABSTRACT (Limit to lc00 tpscst, Is., spproxlmstsly 5!tscn tlnplscpscs typsrrrlttsn linctl HB)

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 US. NUCLEAR REOULATORY COMMISSION (94)3)

LICENSEE E ENT REPORT (LER) TEXT CONTINUAT ON APPROVED OMS NO. 3180-0104 EXPIRES: 8/31/88 FACILITYNAME ll) OOCKET NUMBER (3) LER NUMSER (8) PACE (3)

YEAR +~i SEQVSNTIAL '~j'EVISION

'..:

'I)xI/ NVMSSR NVM SR D. C. Cook Nuclear Plant, Unit 1 0 S 0 0 0 3 15 85 0 2 3 0 1 0 2OF0 TEXT /$ 44>>>> <<>>c>> SI /4)MS'>>o aSSM>>o/NRC F>>RII 38M 3/ (17)

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 was 2, 1985 during a review of NUREG 0612 requirements, determined that on occasion, between June 1982 and April 1985, the it 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 ~USOPO:IOS(LO83A.S38/SSSIN

"(883)

NRC Form 388A US. NUCLEAR REOULATORY COMMISSION

)883)

LICENSEE E NT REPORT (LER) TEXT CONTINUAT N APPROVED OM8 NO. 3160&104 EXPIRES: 8/31/88 FACILITYNAME 11) DOCKET NUMBER I2) LER NUMBER )8) PACE 13)

YEAR .'san 8EOUENTIAL 'Nr IIEVISION

~

%%1 NUM SII N U M 8 8 II D. C. Cook Nuclear Plant, Unit 1 o s o o o 31 58 5 023 0 1 0 30F 04 TEXT 13//Noro deco 8 ro0rkord Iso akN5wo/H/IC %%drIII 38/A8/ OT)

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 *U.S.OPOII 0880824438/1 66 .

1883)

hRC Form 3BBA US. NUCLEAR REOULATORY COMMISSION (083)

LICENSEE E NT REPORT (LER) TEXT CONTINUATI N APPROVED OMB NO. 3150-0104 EXPIRES: 8/31 I(6 FACIU NAME (1) DOCKET NUMBER (3) LER NUMBER (B) PACE (3)

YEAR SEOVENTIAL REVISION rIVM ER  %Ã NVM ER D. C. Cook Nuclear Plant, Unit 1 0 5 0 0 0 3 l 5 8 5 023 0 1 0 4 OF 0 4 TEXT (PIRoro N>>co Jr roBMBad oro aki5ans'NRC ForIII 3(ELBE) ((7)

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 m ().SOP(3I198()4() SI.S38/add, .

BALI)

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~ye/ INDIANA I& MICIIIGAN 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 R. C. Callen, MPSC III 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