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{{#Wiki_filter:k.C CELERY'Ig@DLR 2'9l DI RKQl%RA~N RIDgiYSTEM ACCESSION NBR:8810130119 DOC.DATE: 88/09/30 NOTARIZED:
{{#Wiki_filter:}}
NO DOCKET'ACIL:50-315 Donald C.Co'ok Nuclear Power Plant, Unit 1, Indiana&05000315 AUTH.NAME AUTHOR AFFILIATION POSTLEWAIT,T.K.
Indiana Michigan Power'Co.(formerly Indiana&Michigan Ele SMITH,W.G.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION p g W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR
~ENCL J SIZE: TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.NOTES: SUB ECT: LER 88-007-00:on 880908,ice build-up in ice condense" flow assa es due to sublimation.
ltr.D'ECIPIENT ID CODE/NAME PD3-1 LA STANGPJ INTERNAL: ACRS MICHELSON ACRS WYLZE AEOD/DSP/NAS AEOD/DSP/TPAB DEDRO NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES TELFORDPJ RES/DSIR/EIB EXTERNAL: EG&G WILLIAMSgS H ST LOBBY WARD NRC PDR NSIC MAYS,G COPIES.LTTR ENCL 1 1 1 1 1 1 1.1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 4 4 1 1 1 1-1 1 RECIPIENT ID CODE/NAME PD3-1 PD ACRS MOELLER AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB
*10 NRR/DREP/RAB 1'0 NRR DRZS/SIB 9A 02 RES/DSIR DEPY RGN3 FILE 01 FORD BLDG HOY,A LPDR NSIC HARRZSgJ COPIES LTTR'ENCL 1 1 2 2 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D D'TOTAL NUMBER OF COPIES REQUIRED: LTTR'46 ENCL 45 NRC Form 355 (943)LICENSEE EVENT REPORT{LER)US.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3150010l EXPIAES: SISIISS FACILITY NAME (I)D.C.Cook Nuclear Plant-Unit 1 TITLE (Sl DOCKET NUMBER (2)PA 0 5 0 0 03 151OF1 5 Ice Build-Up in Ice Condenser Flow Passages Due to Sublimation EVENT DATE (5)LFR NUMBER (5)REPORT DATE It)OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR SEQUENTIAL NUMBER MONTH OAY NUMBER YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 0 9088 8 88 0 0 7 00 0 9 30 8 8 0 5 0 0 0 OPE RAT INC MODE (9)POWER LEvEL 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 50.73(s)(2Hlv) 50.73(s H2 Hv)50.734)(2)(vS I 50.73(e)(2)(vill)IAI 50.73(s)l2)(vI5 I (5)50.73(s)(2)(s) 20A05(cl 50.35(c)(Il 50.35(cl(2) 50.73(e)(2)(ll 50.73(e)(2)(5)50.734)(2)(III)20.402(bl 20A05(~l(1)(l)20.S05(s)(I IIII)20A05(~l(1 Hill)20AOS (s I (I I (I v)20AOS(el(1)(vl LICENSEE CONTACT FOR THIS LER (12I 0 THE REDUIREMENTB oF 10 cFR (Il Icnecc one or more of the Ioriowinol (11 73.71DI)73.71(c)OTHER ISpeclfy in Abrovct below end In Test, NIIC Form 366AI NAME T.K.Postlewait-"Technical Engineering Superintendent TELEPHONE NUMBER AREA CODE 616465-5901 COMPLETE ONE LIME FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER r I EPORTABLE'3 4: TO NPADS;.6y.N.IRMA!CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTABLE TO NPRDS XVPMa ke%m SUPPLEMENTAL REPORT EXPECTED (Icl YES III yer, complere EXPECTED SUBMISSION DATE)NO AssTAAGT ILimlt to Ierx)rpecet, I.e., epprocimetely fifteen elnole specs typewrltren lined (1st MONTH OAY EXPECTED SUBMISSION OATS (15)YEAR On September 8, 1988, with Unit 1 in Mode 4 (Hot Shutdown), flow passage inspections of the ice condenser revealed frost and ice buildup on the lattice frames of greater than 3/8 inch in a total of thirty-six flow passages in nine of the twenty-four ice condenser bays.Technical Specification (T/S)4.6.5.1.b.3 limits frost or ice buildup in flow passages to a nominal thickness of'3/8 inch.According to this T/S, buildup exceeding this limit in two or more flow passages per bay is evidence of abnormal degradation.
Though our evaluation has concluded that the degradation is not serious, we believe issuance of this voluntary LER is appropriate'since some degradation has been.identified.
Actions taken to correct the abnormal degradation included manual cleaning of the flow passages.In addition an internal investigation of the event was conducted.
The results of T/S Surveillances regarding frost and ice that forms in the flow passages is being monitored to ensure that any adverse trends in the amount of ice and frost buildup between surveillances will be identified.
The impact of frost and ice buildup in the flow passages is also being studied in conjunction with the other utilities with ice condenser containments.
NRC Form (903)8810130119 880'7)30 S 355 NRC FBOB 3BBA (983)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3)50-OIBB EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER IB)Q5(SBOVENTIAL NUMBER ,'gbP REVISION NVMBBR PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///mate g>>CB/B nqakaf, BBB atCL5Wal HRC FBNR 388AS/I Ill 0 5 0 0 0 3]5 8 8 0 0 7 0 0 020" 15 Conditions Prior to Occurrence Unit 1 in Mode 4 (Hot Shutdown)Descri tion of Event The as-found visual inspection of ice condenser (EIIS/COND) flow passages conducted on September 8, 1988, identified frost and ice accumulation greater than 3/8 inch in two flow passages in Bay 1, two flow passages in Bay 2, four flow passages in Bay 3, two flow passages in Bay 4, four flow passages in Bay 6, two flow passages in Bay 8, two flow passages in Bay 12, two flow passages in Bay'14 and two flow passages in Bay 15.Subsequently, the inspection was expanded to include at least twenty additional flow passages in each affected bay.This inspection revealed an additional two flow passages in Bay 2, six flow passages in Bay 3 and six flow passages in Bay 4 with more than 3/8 inch frost and ice buildup.A total of thirty-six flow passages were affected.There are a total of 3072 flow passages in the Ice Condenser.
Attachments 1 through 11 graphically describe the geometry of the flow passages and the location of the ice/frost accumulation.
Technical Specification (T/S)4.6.5.l.b.3 requires that the ice condenser be determined operable at least once per 9 months byverifying, via visual inspection of at least two flow passages per ice condenser bay, that accumulation of frost or.ice on flow passages between ice baskets (EIIS/COND-BSKT), past lattice frames (EIIS/COND-FRM), through the intermediate and top deck floor grating, or past the lower inlet plenums support structures (EIIS/COND-SPT) and turning yanes is restricted to a nominal thickness of 3/8 inch.If one flow passage per bay-is found to have an accumulation of frost or ice greater than this thickness, a representative sample of twenty additional flow passages from the same bay shall be visually inspected.
If these additional flow passages are found acceptable, the surveillance, program may proceed considering the single deficiency as unique and acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation-of the ice condenser.
The affected flow passages were manually cleaned to remove the accessible frost and ice buildup.NRC FORM 3BBA 19'83)*U.S.GPO:1985.0824 538/455 NRC Form 368A (84)3)LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.S.NUCLEAR REGUI.ATORY COMMISSION APPROVEd OMS NO.3I50-0(04 EXPIRES: 8/31/88 FACILITY NAME l)I OOCI(ET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL NUMBER REVISION NUMBER PAGE (3)D.C.Cook Nuclear Plant-U 1 TEXT/$/IRBB g>>CB 4I/BEN)BIS uW~NRC%%drm 38543/(17)3 1 5 8 8 0 0 7 0 0 0 3 5 Additional factors considered as possible contributors to the frost and ice accumulation included: 1)during the surveillance interval prior to the September 8, 1988 test, several of the 60 air handling units (AHU)(EIIS/AHU)(used to maintain ice condenser temperature) were intermittently inoperable for maintenance and/or repair.In addition, as the result of a personnel error, most of the AHU's were inoperable for a period of about four days at the end of July;however, it has been concluded that the inoperability of the AHU's did not significantly contribute to the frost and ice formation experienced; 2)during the Unit shutdown immediately preceding this surveillance, it was discovered that a secondary side steam leak had occurred inside containment, possibly'affecting the humidity in the ice condenser; however, it has been concluded that the steam leakage did not significantly contribute to the frost and ice formation experienced, as the formation was very similar to that experienced in the past (the only apparent effect of the steam leak on the ice condenser was minor amountsof frost/ice formation on the intermediate deck doors).With the exception of the AHU's, there were no inoperable structures, components or systems that contributed to this event.Cause of Event It is believed that sublimation of ice or high humidity in the containment air could have contributed to this problem.Further investigation of this event.is ongoing.Anal sis of Event The Westinghouse evaluation indicated that latti'ce frost/ice formation of up to 20 percent of the total flow passage area could be present without the peak Ice Condenser Compartment Pressure exceeding the design limit.Since the frost/ice buildup identified in Bays 1, 2, 3, 4, 6, 8, 12, 14 and 15 constitute a total flow blockage area which is less than 20 percent limit, this situation is bounded by the Westinghouse evaluation.
Our evaluation indicates that the amount of flow blockage due to frost and ice buildup noted in the Iee Condenser can be tolerated without adversely affecting the Ice Condenser function during a Loss of Coolant Accident.Based on the above information and the Westinghouse evaluation, it is concluded that the abnormal degradation event does not constitute an unreviewed safety question as defined in 10CFR50.59(a)(2), nor does it adversely impact health and safety.Though-our evaluation has concluded that the degradation is not serious, we believe issuance of this voluntary LER is appropriate since some degradation has been identified.
NRC FORM SSBA (94)3)*U.S.GPO:1086.0.624 538/455 NRC Form 35EA (983)LICENSEE ENT REPORT (LER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150-0(94 EXPIRES: 8/31/88 ACIUTY NAME ul DOCKET NUMBER (3)YEAR I.ER NUMBER (5)SEOUENTIAI.
Pc%<NUMBER 4'EV/SION NUMBER PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///'/m//s g>>ce/4/q/o///w/, I/FEE///////dna/HRC Form 35543/(17)0 5 0 0 0 3]5 8 00 7--0 0 0 4 1 5 Corrective Actions The corrective action was to manually clean the flow passages to remove the accessible frost and ice buildup.The results of Technical Specification Surveillances regarding frost and ice that forms in the flow passages is being monitored to ensure that any adverse trends in the amount of ice and frost buildup between surveillances will be identified.
The impact of frost and ice buildup in the flow passages is also being studied in conjunction with the other utilities with ice condenser containments.
Failed Com onent Identification No component failures were identified during this event.Previous Similar Events LER 50-316/85-013 LER 50-316/87-002 LER 50-315/87-013 LER 50-316/87-010 LER 50-315/88-002 LER 50-316/88-005 NRC FOAM SSEA ($83)*U.S.GPO:)988.0-834 538/455 NRC Fono 388A ($83)LICENSE ENT REPORT ILER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3150-0104 EXPIRES: 8/31/(8 FACIUTY NAME (1)COCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL.Njb'UMBER REVISION NUMBER PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT/PIIRBB Rpoco/t Beta)BI/, Boo////Ooo///RC Fontt 36843/(17)0 5 0 0 0 3]5 8 8 0 0 7-0 0 0 5 OF 1 5 ATTACHMENT 1 Description of Flow Passage Blockage by Category (affected Flow Passages are indicated by the boxed areas on the following attachments).
~Cate or A Maximum Flow Passage Ice/Frost Blockage greater than 75 percent.Maximum Flow Passage Ice/Frost Blockage between 50 and 75 percent.Maximum Flow Passage Ice/Frost Blockage between 25 and 50 percent.D Maximum Flow Passage Ice/Frost Blockage less than 25 percent (but greater than 3/8" buildup).*NOTE: These are generalized categories which reflect the maximum.ice/frost blockage found in a particular flow passage and in general was limited to one or two lattic'e frameworks in the flow passage.This does not indicate that the flow passage was blocked its entire length.Lattice Framework is located at the positions'of cruciforms in the ice basket.Cruciforms are installed every six feet within the 48 foot ice basket (for convention the"top" lattice framework is referred to as number 1, etc.).The specific lattice frameworks affected are indicated on the individual Bay drawings (Attachments 3-11).NRC FORM BBBA (94)31*U.S.GPO:1988.0.824 538/455 NRC Form 388A (983)~LICENSEE ENT REPORT (LER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1)COCKET NUMBER (1)YEAR LER NUMBER (8)SEQUENTIAL NUMBER REVISION NVM BR PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//P neo BPdcd b/IO/ror/rrro dr/d/I/ooo/NRC Forrrr 3854'c/(17)0 5 0 0 0 3 1 5 8 0 0 7 0 0 0 6 OF 1 5 ATTACHMENT 2 Representative Diagram of Ice/Frost Buildup in Two Flow Passages Technical Specification nominal thickness (3/8 inch)Lattice Framework Scale: 1/2 inch equals 1 inch NRC FORM SBBA (94)3)o U.S.GPO.'1986.0.624 538/455 NRC Form 366A ($83),, LICENSEE ENT REPORT (LER)TEXT CONTIN ION US.NUCLEAR REOULATORY COMMISSION APPROVED OMS NO.3150-0104 EXPIRES: 8/3)/88 FACILITY NAME (Il D.C.Cook Nuclear Plant-Unit 1 DOCKET NUMBER (2)o.s o o o 3 1 5 YEAR 8 8 LER NUMSER (6)$8/~SEOUENTIAL Ni<)NUMSER 0 0 7 REVISION NUMBER 0 0 PACE (3)0 7 oF 1 5 TEXT//P R>>m<<>>ce/8 mqUPEc/II48~HRC%%dmI 38543/(17)ATTACHMENT 3 Bay 1 (of 24 total)Azimuthal Row (Basket)C(7)Radial 5 Row (Row)Note: The lattice frameworks affected are indicated in parenthesis after the catepory description number (see Attachment 1).NRC FORM 366A (84)3)~.~*U 8 QPO 1988 0 824 538/455 NRC Form 3BSA (943)i LICENSE ENT REPORT (LER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3150-OIOi EXPIRES: 9/31/SS FACIUTY NAME (1)OOCKET NUMBER (2)YEAR LER NUMBER (9)SEQUENTIAL NUMBER 0?N'EVISION NUMBER PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//Frrxro<<>>co/F r)q/rorL I/ro////Or>>/NRC Forrn36//49/(17) o s o o o 3 1 5 8 8 0 0 7 0 0 0 8 QF 1 5 ATTACHMENT 4 Bay 2 (of 24 total)Azimuthal Row (Basket)6 7 D(8)Radial 5.Row (Row)D(3)8 Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 3OOA (943).*U.S.GPO:19BB.O 624 BSJVABS NRC Form 3SSA (94)3)'ICENSEE EVENT REPORT (LER)TEXT.CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3159WI04 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (5)SEQUENTIAL QXj NVMBBR".N REVISION NVMBBII PACE (3)D.C.Coo'k Nuclear Plant-Unit 1 TEXT//F moro<<Poco/4/4//rkorL Ir<<B S/S/ooo/kRC Fomr 35843/(17)0 5 0 0 0 3]8 8-0 0 7 0 0 0 9 OF 1 5 ATTACHMENT 5 Bay 3 (of 24 total)Azimuthal Row (Basket)C(2 and 3)1 2'(2 and 3): 5 6 2 Radial Row (Row)D(3)Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FOAM SBBA (94)3)<<U.S.GPO:1988.0 824 538/455 NRC FFNR 388A ($83)LICENSEE EVENT REPORT (LER1 TEXT CONTINU ION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-010S EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (8)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///mao<<>>co/s rsqo)orL l>>F~NRC Form 38843/(17)YEAR, g@o s o o o 31588 SEOUENTIAL NUMSSR 0 0 7 gp" REvrsloN-0 0 1 OoF 1 5 ATTACHMENT 6'BAY 4 (OF 24 TOTAL)Azimuthal Row (Basket)5 6 Radial'Row (Row)D(3)D(3 Note: The lattice frameworks affected are indicated in parenthsis after the category description number (see Attachment 1).NRC FORM SSSA (9<<3)*U,B.GPO;1988 0 824 838/48$
 
RC Form 366A" ($4)3)LICENSEE ENT REPORT (LER)TEXT CONTIN ON U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150-0)04 EXPIRES: 8/3)/88 FACILITY NAME tl)DOCK ET NUM 8 E R (2)LER NUMSER (6)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT///mac 4FSSF/4 F6I4)Sat, IIFF aSSSWone//YRC
%%dmI 35549/(17)0 5 0 0 0 3 1 5 YEAR 8 8 SEOVSNTIAL kW'EVISION
'VMSSR:IPS NUMBER 0 0 7-0 0 1 1 OF 1 5 ATTACHMENT 7 Bay 6 (of 24 total)Azimuthal Row (Basket)Radial 5 Row (Row)D(3)Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 366A (94)3)*U.S.GPO:I 986 0-624 538/455' NRC FONB 300A (BB3)>LICENSEE VENT REPORT ILER)TEXT CONTIN ION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3180M)04 EXPIRES: 8/31/88 FACIUTY NAME (1)DOCKET NUMBER (2)LER NUMBER (8)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TACT/4/Ieee g>>ce/4 Ieqekaf, I>>e//8/0/>>/NRC Fo/In SSBAB/((7)o s o o o3 15 YEAR gg 8 8 SEQUENTIAI NUMBER%Cr 0 0 7 REV IS ION NUMBER 0 0 1 2 QF I.5 ATTACHMENT 8 Bay 8 (of 24 total)Azimuthal Row (Basket)Radial Row (Row)\I I D(3)Note: The.1'attice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 300A ($43)*U.S.GPO:1088.0.024 538/45S NRC~388A (94)3)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3150-OI04 EXPIRES: 8/31/BS FACILITY NAME (1)OOCKET NUMBER (2)YEAR LER NUMBER (8)SEOVENT/AL NVMBER').N0 REVIS lON NVMSER PAGE I3)D.C.Cook Nuclear Plant-Unit 1 TEXT/P//N/tu 4pecu/4/FEVEud, u44//I/FR4/HRC Form 35543/(IT)o s o o o 3 1 5 8 8 0 0 7 0 0 1 3 OF ATTACHMENT 9 Bay 12 (of"24 total)Azimuthal Row (Basket)A 7)Radial 5 Row (Row)I I I 7'ote: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 388A (94)3)*U,S.GPO:1988 0 624 538/455 RC Form 366A (983)LICENSEE ENT REPORT (LER)TEXT CONTINU ION US.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO..'3)EO-0104 EXPIRES: 8/31/88 FACILITY NAME (Il DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//F rrrors 4/roro/4 t/r//roo L oro 44I/one/NRC
%%dnn 35549)(IT)o s o o o 3 1 5 YEAR@P 8 8 SSOUSNTIAL NUMSSR 0 0 7 REVOION'>:55vr NUMSSR 0 0 1 4 OF 1 5 ATTACHMENT 10 Bay 14 (of 24 total)Azimuthal Row (Basket)4 5 Radial 5 Row (Row)8 D(2)Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM 366A (943)*U.S.GPO:1955.0 524 4638/455 NRC Form 368A (943)~LICENSEE VENT REPORT (LER)TEXT CONTIN TION US.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3150-01(M EXPIRES: 8/31/85 FACIUTY NAME l1)OOCKET NUMBER 12)YEAR LER NUMBER (6)SBOUENTIAL NUMBBR REVISION NUMBBR PAGE (3)D.C.Cook Nuclear Plant-Unit 1 TEXT//FmBm BPBBB lI BqIA)BI/, IIFF 9//dBBB/HRC
%%dmI 35549/l)T)os000315 8 8 0 0 7 0 0 1 5 QF 1 5 ATTACHMENT ll Bay 15 (of 24 total)Azimuthal Row (Basket)D(2)1 Radial 5 Row (Row)6 Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).NRC FORM SBBA (943)*U.S.GPO:(988 0 624 538/455 Indiana Michlga Power Company Cook Nuclear Plant P.O.Box 458 Bridgman.Ml 49106 616 465 5901 Z MAMBA MCHJGQH PQ'uV22 September 30, 1988 United States Nuclear Regulatory'ommission Document Control Desk Washington, D.C.20555 Operating 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:
88-007-00 Sincerely, W.G.Smith, Jr.Plant Manager WGS:clw Attachment cc: D.H.Williams, Jr.A.B.Davis, Region III M.P.Alexich P.A.Barrett J.E.Borggren R.F.Eroeger NRC Resident Inspector J.F.Stang, NRC.R.C.Callen G.Charnoff, Esp.-Dottie Sherman, ANI Library D.Hahn INPO PNSRC A.A.Blind S.J..Brewer/B.P.Lauzau}}

Revision as of 07:34, 23 October 2019

LER 88-007-00:on 880908,flow Passage Insp of Ice Condenser Revealed Frost & Ice Buildup.Caused by Sublimation of Ice or High Humidity in Containment Air.Flow Passages Manually Cleaned to Remove Accessible frost.W/880930 Ltr
ML17326B468
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 09/30/1988
From: Postlewait T, Will Smith
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-007-01, LER-88-7-1, NUDOCS 8810130119
Download: ML17326B468 (18)
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