ML17326B468

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
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)

Text

k.C CELERY'Ig@DLR 2'9l DI RKQl%RA~N RIDgiYSTEM ACCESSION NBR:8810130119 DOC.DATE: 88/09/30 NOTARIZED: 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 SUB ECT: LER 88-007-00:on 880908,ice build-up in ice condense" flow p assa g es due to sublimation.

W/8 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ~ ENCL J SIZE:

TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

D'ECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME .LTTR ENCL ID CODE/NAME LTTR'ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANGPJ 1 1 D

INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 D'

ACRS WYLZE 1 .1 AEOD/DOA 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB *10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 1'0 1 1 NRR/DREP/RPB 10 2 2 NRR DRZS/SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 02 1 1 RES TELFORDPJ 1 1 RES/DSIR DEPY 1 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: EG&G WILLIAMSgS 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1- NSIC HARRZSgJ 1 1 NSIC MAYS,G 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR '46 ENCL 45

NRC Form 355 US. NUCLEAR REOULATORY COMMISSION (943)

APPROVED OMB NO. 3150010l EXPIAES: SISIISS LICENSEE EVENT REPORT {LER)

FACILITYNAME (I) DOCKET NUMBER (2) PA D. C. Cook Nuclear Plant Unit 1 0 5 0 0 03 151OF1 5 TITLE (Sl 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 YEAR YEAR SEQUENTIAL OAY YEAR FACILITYNAMES DOCKET NUMBER(S)

DAY NUMBER NUMBER MONTH 0 5 0 0 0 0 9088 8 88 0 0 7 00 0 9 30 8 8 THIS REPORT IS SUBMITTED PURSUANT T0 THE REDUIREMENTB oF 10 cFR (Il Icnecc one or more of the Ioriowinol (11 0 5 0 0 0 OPE RAT INC MODE (9) 20.402(bl 73.71DI) 20A05(cl 50.73(s)(2Hlv)

POWER 20A05( ~ l(1 )(l) 50.35(c) (Il 50.73(s H2 Hv) 73.71(c)

LEvEL 0 0 0 20.S05(s) (I IIII) 50.35(cl(2) 50.734) (2)(vS I OTHER ISpeclfy in Abrovct below end In Test, NIIC Form 20A05( ~ l(1 Hill) 50.73(e) (2)(ll 50.73(e) (2) (vill)IAI 366AI 20AOS (s I (I I (Iv) 50.73(e) (2)(5) 50.73(s) l2)(vI5I (5) 20AOS(el(1)(vl 50.734) (2) (III) 50.73(s)(2)(s)

LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER T. K. Postlewait- AREA CODE "Technical Engineering Superintendent COMPLETE ONE LIME FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 616465-5901 r I 4:

MANUFAC. EPORTABLE '3 MANUFAC.

CAUSE SYSTEM COMPONENT TURER TO NPADS;. 6y . N.

CAUSE SYSTEM COMPONENT TURER EPORTABLE TO NPRDS ke%m IRMA! XVPMa SUPPLEMENTAL REPORT EXPECTED (Icl MONTH OAY YEAR EXPECTED SUBMISSION OATS (15)

YES IIIyer, complere EXPECTED SUBMISSION DATE) NO AssTAAGT ILimlt to Ierx) rpecet, I.e., epprocimetely fifteen elnole specs typewrltren lined (1st 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.

8810130119 880'7)30 S

NRC Form 355 (903)

NRC FBOB 3BBA U.S. NUCLEAR REGULATORY COMMISSION (983)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3)50-OIBB EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER IB) PAGE (3)

YEAR Q5( SBOVENTIAL ,'gbP REVISION NUMBER NVMBBR D. C. Cook Nuclear Plant Unit 1 0 5 0 0 0 3 ] 5 8 8 0 0 7 0 0 020" 15 TEXT ///mate g>>CB /B nqakaf, BBB atCL5Wal HRC FBNR 388AS/ I Ill 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 by verifying, 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 *U.S.GPO:1985.0824 538/455 19'83)

NRC Form 368A U.S. NUCLEAR REGUI.ATORY COMMISSION (84)3)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEd OMS NO. 3I50-0(04 EXPIRES: 8/31/88 FACILITYNAME l) I OOCI(ET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION NUMBER NUMBER U 1 TEXT /$ /IRBB g>>CB 4I /BEN)BIS uW ~

D. C. Cook Nuclear Plant-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 amounts of 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 *U.S.GPO:1086.0.624 538/455 (94)3)

NRC Form 35EA U.S. NUCLEAR REGULATORY COMMISSION (983)

LICENSEE ENT REPORT (LER) TEXT CONTIN ION APPROVED OMS NO. 3150-0(94 EXPIRES: 8/31/88 ACIUTY NAME ul DOCKET NUMBER (3) I.ER NUMBER (5) PAGE (3)

YEAR SEOUENTIAI.

NUMBER 4'EV/SION Pc%<

NUMBER D. C. Cook Nuclear Plant Unit 1 0 5 0 0 0 3 ] 5 8 00 7-0 0 0 4 1 5 TEXT ///'/m//s g>>ce /4/q/o///w/, I/FEE///////dna/HRC Form 35543/ (17)

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 *U.S.GPO:)988.0-834 538/455

($ 83)

NRC Fono 388A U.S. NUCLEAR REGULATORY COMMISSION

($ 83)

LICENSE ENT REPORT ILER) TEXT CONTIN ION APPROVEO OMS NO. 3150-0104 EXPIRES: 8/31/(8 FACIUTY NAME (1) COCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION

.Njb'UMBER NUMBER D. C. Cook Nuclear Plant Unit 1 0 5 0 0 0 3 ] 5 8 8 0 0 70 0 0 5 OF 1 5 TEXT/PIIRBBRpoco /t Beta)BI/, Boo ////Ooo/ //RC Fontt 36843/ (17)

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 *U.S.GPO:1988.0.824 538/455 (94)31

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION (983) ~

LICENSEE ENT REPORT (LER) TEXT CONTIN ION APPROVEO OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITYNAME (1) COCKET NUMBER (1) LER NUMBER (8) PAGE (3)

YEAR SEQUENTIAL REVISION NUMBER NVM BR D. C. Cook Nuclear Plant Unit 1 0 5 0 0 0 3 1 5 8 0 0 7 0 0 0 6 OF 1 5 TEXT //P neo BPdcd b /IO/ror/ rrro dr/d/I/ooo/NRC Forrrr 3854'c/ (17)

ATTACHMENT 2 Representative Diagram of Ice/Frost Buildup in Two Flow Passages Lattice Framework Technical Specification nominal thickness (3/8 inch)

Scale:

1/2 inch equals 1 inch NRC FORM SBBA o U.S.GPO.'1986.0.624 538/455 (94)3)

NRC Form 366A US. NUCLEAR REOULATORY COMMISSION

($ 83),,

LICENSEE ENT REPORT (LER) TEXT CONTIN ION APPROVED OMS NO. 3150-0104 EXPIRES: 8/3)/88 FACILITYNAME (Il DOCKET NUMBER (2) LER NUMSER (6) PACE (3)

YEAR $ 8/~ SEOUENTIAL REVISION Ni<) NUMSER NUMBER Nuclear Plant D. C. Cook Unit 1 TEXT //P R>>m <<>>ce /8 mqUPEc/ II48 ~ HRC %%dmI 38543/ (17) o.s o o o 3 1 5 8 8 0 0 7 0 0 0 7 oF 1 5 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 *U 8 QPO 1988 0 824 538/455 (84)3) ~ . ~

NRC Form 3BSA U.S. NUCLEAR REGULATORY COMMISSION (943) i LICENSE ENT REPORT (LER) TEXT CONTIN ION APPROVEO OMB NO. 3150-OIOi EXPIRES: 9/31/SS FACIUTY NAME (1) OOCKET NUMBER (2) LER NUMBER (9) PAGE (3)

YEAR SEQUENTIAL 0?N'EVISION NUMBER NUMBER D. C. Cook Nuclear Plant-Unit 1 o s o o o 3 1 5 8 8 0 0 7 0 0 0 8 QF 1 5 TEXT//Frrxro<<>>co/F r)q/rorL I/ro////Or>>/NRC Forrn36//49/(17)

ATTACHMENT 4 Bay 2 (of 24 total)

Azimuthal Row (Basket) 6 7 D(8) 5.

Radial 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 .*U.S.GPO:19BB.O 624 BSJVABS (943)

NRC Form 3SSA U.S. NUCLEAR REGULATORY COMMISSION (94)3)

'ICENSEE EVENT REPORT (LER) TEXT. CONTINUATION APPROVED OMS NO. 3159WI04 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (5) PACE (3)

YEAR SEQUENTIAL QXj REVISION NVMBBR ".N NVMBBII D. C. Coo'k Nuclear Plant-Unit 1 0 5 0 0 0 3 ] 8 80 0 7 0 0 0 9 OF 1 5 TEXT //F moro <<Poco /4 /4//rkorL Ir<<B S/S/ooo/kRC Fomr 35843/ (17)

ATTACHMENT 5 Bay 3 (of 24 total)

Azimuthal Row (Basket)

C(2 and 3) 1 2'(2 5 and 3):

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 <<U.S.GPO:1988.0 824 538/455 (94)3)

NRC FFNR 388A U.S. NUCLEAR REGULATORY COMMISSION

($ 83)

LICENSEE EVENT REPORT (LER1 TEXT CONTINU ION APPROVED OMB NO. 3150-010S EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3)

YEAR, g@ SEOUENTIAL NUMSSR gp" REvrsloN Nuclear Plant D. C. Cook Unit TEXT ///mao <<>>co /s rsqo)orL l>>F 1

~ NRC Form 38843/ (17) o s o o o 31588 0 0 7 0 0 1 OoF 1 5 ATTACHMENT 6

'BAY 4 (OF 24 TOTAL)

Azimuthal Row (Basket) 5 6 D(3)

Radial '

Row (Row)

D(3 Note: The lattice frameworks affected are indicated in parenthsis after the category description number (see Attachment 1).

NRC FORM SSSA *U,B.GPO;1988 0 824 838/48$

(9<<3)

RC Form 366A" U.S. NUCLEAR REGULATORY COMMISSION

($ 4)3)

LICENSEE ENT REPORT (LER) TEXT CONTIN ON APPROVED OMS NO. 3150-0)04 EXPIRES: 8/3)/88 FACILITY NAME tl) DOCK ET NUM8 E R (2) LER NUMSER (6) PAGE (3)

YEAR SEOVSNTIAL kW'EVISION NUMBER 'VMSSR:IPS D. C. Cook Nuclear Plant Unit 1 0 5 0 0 0 3 1 5 8 8 0 0 7 0 0 1 1 OF 1 5 TEXT ///mac 4FSSF /4 F6I4)Sat, IIFF aSSSWone//YRC %%dmI 35549/ (17)

ATTACHMENT 7 Bay 6 (of 24 total)

Azimuthal Row (Basket) 5 Radial Row (Row)

D(3)

Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

NRC FORM 366A *U.S.GPO:I 986 0-624 538/455' (94)3)

NRC FONB 300A U.S. NUCLEAR REGULATORY COMMISSION (BB3) >

LICENSEE VENT REPORT ILER) TEXT CONTIN ION APPROVED OMB NO. 3180M)04 EXPIRES: 8/31/88 FACIUTY NAME (1) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3)

SEQUENTIAI REV IS ION YEAR gg NUMBER %Cr NUMBER D. C. Cook Nuclear Plant Unit 1 o s o o o3 15 8 8 0 0 7 0 0 1 2 QF I. 5 TACT/4/Ieee g>>ce /4 Ieqekaf, I>>e //8/0/>>/NRC Fo/In SSBAB/ ((7)

ATTACHMENT 8 Bay 8 (of 24 total)

Azimuthal Row (Basket)

\

I D(3)

Radial I Row (Row)

Note: The .1'attice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

NRC FORM 300A *U.S.GPO:1088.0.024 538/45S

($43)

NRC (94)3)

~ 388A 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) LER NUMBER (8) PAGE I3)

YEAR SEOVENT/AL REVIS lON NVMBER ').N0 NVMSER D. C. Cook Nuclear Plant Unit 1 o s o o o 3 1 5 8 8 0 0 7 0 0 1 3 OF TEXT /P//N/tu 4pecu /4/FEVEud, u44 //I/FR4/HRC Form 35543/ (IT)

ATTACHMENT 9 Bay 12 (of "24 total)

Azimuthal Row (Basket)

A 7)

I I

5 Radial I Row (Row) 7'ote:

The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

NRC FORM 388A *U,S.GPO:1988 0 624 538/455 (94)3)

RC Form 366A US. NUCLEAR REGULATORY COMMISSION (983)

LICENSEE ENT REPORT (LER) TEXT CONTINU ION APPROVEO OMS NO..'3)EO-0104 EXPIRES: 8/31/88 FACILITYNAME (Il DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SSOUSNTIAL REVOION

@P NUMSSR '>:55vr NUMSSR D. C. Cook Nuclear Plant Unit 1 o s o o o 3 1 5 8 8 0 0 7 0 0 1 4 OF 1 5 TEXT //F rrrors 4/roro/4 t/r//roo L oro 44I/one/NRC %%dnn 35549) (IT)

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 *U.S.GPO:1955.0 524 4638/455 (943)

NRC Form 368A US. NUCLEAR REGULATORY COMMISSION (943) ~

LICENSEE VENT REPORT (LER) TEXT CONTIN TION APPROVEO OMS NO. 3150-01(M EXPIRES: 8/31/85 FACIUTY NAME l1) OOCKET NUMBER 12) LER NUMBER (6) PAGE (3)

YEAR SBOUENTIAL REVISION NUMBBR NUMBBR 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 5

Radial Row (Row) 6 Note: The lattice frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

NRC FORM SBBA *U.S.GPO:(988 0 624 538/455 (943)

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.

M.

Davis, Region P. Alexich III 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