ML17325B161

LER 89-002-00:on 880817,seismic Restraint Identified to Have Significant Deformation & on 890116 Subsequent Evaluation Determined That Suction Line Stresses Would Have Exceeded FSAR Criteria.Cause Unknown.Design revised.W/890215 Ltr

ML17325B161
Person / Time
Site:	Cook
Issue date:	02/15/1989
From:	Postlewait T, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-002, LER-89-2, NUDOCS 8903030264
Download: ML17325B161 (7)

Text

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ACCESSION NBR:8903030264 DOC.DATE: 89/02/15 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 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 R

SUBJECT:

LER 89-002-00:on 890116,non-svc induced deformation of ECCS suction line seismic restraint.

W/8 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR L TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

ENCL X SIZE:

NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANG,J 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADE 8H 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 10 1 1 NRR/DREP/RPB 10 2 2 NRR D SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 1 1 RES/DSIR/EIB 1 1 RES/DSR/PRAB 1 1 RGN3 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 S

NOTE 'IO ALL "RZDS" RZCZPZZNrS PLEASE HELP US K) RGOUCE HASTE! CONZACT 'IHE DOCUMENT'r CXNZR)L DESK, RCCYi Pl-37 (EXT. 20079) IO ELIIGZATE YOUR NAME FRY DISTRIBVZIGN LISTS FOR DOCUMENTS YOU DGNIT NEED}

TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44 ~

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NRC Form 388 US. NUCLEAR REOULATORY COMMISSION (04)3)

APPROVEO OMS NO. 31604104 LICENSEE EVENT REPORT (LER) EXPIRES: SI31IBS FACILITY NAME (II DOCKET NUMBER 12) PACE 3 D. C. Cook Nuclear Plant - Unit 2 0 5 0 0 0 3 1 6 1 OFO 5 Non-Service Induced Deformation o mergency ore oo ~ng ystem uct3.on Line Seismic Restraint EVENT DATE (5) LER NUMBER (8) AE'PORT DATE (7) OTHER FACILITIES INVOLVED ISI MONTH DAY YEAR YEAR P~y'rC BEDUBNTrAL RcvrBroN DAY FACILITYNAMES DOCKET NUMBER(SI

&% NUMBER 8%: NUMBER MONTH YEAR 0 5 0 0 0 0 1 168989 0 0 2 0 0 0 2 1 5 8 9 0 5 0 0 0 OPEAAT INC THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CFR ((: (Check One Or more Of the follovflnP) Ill)

MODE (8) 20.402 (b I 20.405(cl 60.73( ~ ) (2) livl 73.71(b)

POWER 20A06 (~ ) (I I (i) 60.38(cl(1) 60.73( ~ ) (2)(vl 73.71(c)

LEVEL p p p 20.405 ( ~ I (I I (8 I 50.38(cl(2) 60.73(el(2) IvQ) OTHER ISpeclfy In Abstrect below end In Tees, NRC Form 20.405( ~ I (I) (ill) d0.73( ~ ) (2) (I) 60,73(e)(2)(vill)IA) 38EA) 20AOd (e) (I ) (lv) 60.73(el(2)(ill 50.73(el(2)(vill) (6) 20A05(el(1) (v) 50.73(el(2) I ill) 60.73( ~ )12) (el LICENSEE CONTACT FOR THIS LER (12I NAME T. K. Postlewait- AREA CODE TELEPHONE NUMBER Technical Engineering Superintendent COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPORT (13) 616465-5901 CAUSE SYSTEM COMPONENT MANUFAC.

TUAER REPORTABLE TO NPRDS Coll) ~ SYSTEM COMPONENT MANVFAC TURER EPORTABLE TO NPRDS

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NX '. C:yrps'rckesNk P@g'<Ãih%Ã m~E~ NaSIFkk

'RP¹)IL SUPPLEMENTAL REPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SUBMISSION DATE 05)

YES Ilfyes, complete EXPECTED SUBMISSION OATEI NO 0 4 0 7 8 9 ABSTRACT (Limit to IC(X) sprees, I e., epproelmetely filreen slnpleepece typewritten lintel (18)

On August 17, 1988 with Unit 2 in Mode 6 (Refueling) during a walkdown of Inservice Inspection pipe supports, a seismic restraint was identified to have significant deformation. The restraint is located on the 24 inch Emergency Core Cooling System suction line from the Unit 2 Refueling Water Storage Tank. Subsequent evaluation on January 16, 1989, determined that the suction line stresses would have exceeded the FSAR criteria under design basis seismic conditions. The investigation determined that it was highly unlikely that the damage was service related. Modifications had been made to the piping to allow the pipe to be replaced with a spool piece to facilitate flushing and ocher startup activities. The deformaeion most likely occurred during the removal and reinstallation of the piping during or following startup activities. The restraint has been repaired and returned eo an acceptable design condition.

Subsequent walkdown of the subject piping system revealed additional as-built/design inconsistencies on two adjacent supports. A detailed engineering analysis is being performed to determine what the effects of a Design Basis Earthquake would have been on the subject piping system, had it occurred based on the subsequent inconsistencies identified on the two adjacent supports. A supplemental report will be submitted by Apri.l 7, 1989.

Pi 7(,)i~L,). <t,),"rr cr r.t. I, NRC Form 388 IB 83l

NRC Form 3SSA U.S. NUCLEAR REGULATORY COMMISSION 19@3)

LICENSEE ENT REPORT (LER) TEXT CONTINUA ION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

D. C. Cook Nuclear Plant- YEAR .j~

~9 SEQUENTIAL NVMSSR 4',

ISr( REVISION NVMSSR Unit 2 0 5 0 0 0 3 ] 8 9 0 0 2 0 0 0 20F TEXT /Krooro 4Poco /4 r(O/ror/ voo //I/O/M/HRC Forrrr 3884'4/ I IT)

Conditions Prior to Occurrence Unit 2 in Mode 6 (Refueling no fuel in the core).

Descri tion of Event On August 17, 1988, at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, during a walkdown of Inservice Inspection (ISI) pipe supports (EIIS/SPT) on Unit 2, it was identified that restraint 2-GSI-L102 was deformed. The restraint is located on the twenty-four inch Emergency Core Cooling System (ECCS) suction line (EIIS/Bg-PSP) gust downstream of the Unit 2 Refueling Water Storage Tank (RWST) (EIIS/CB-TK).

Subsequent evaluation of the restraint's condition on January 16, 1989, determined that the Unit 2 ECCS suction line stresses would have exceeded the FSAR Criteria under design basis seismic conditions.

The deformation of the restraint was identified as deformation of the I-beam attached to the wall, along with deformation of two stanchions attached to the suction pipe (see ATTACHMENT 1). The deformation caused significant increases in the gap between the I-beam and the stanchions. Examination of.

the ECCS piping itself revealed no damage. The original seismic design required a one-sixteenth inch gap on each side. The gaps found from the deformation ranged from one-half to one and one-quarter inches. The design of the restraint is for seismic considerations and by definition is exempt from ISI visual examination per- ASME Section XI. The restraint carries no load during normal plant operation in any plane. The purpose of the restraint is to limit horizontal movement of the suction line during a seismic event.

The ECCS suction line piping was walked down and adjacent hangers and supports were inspected. Two supports, 2GSI-L106 and 2GSI-104, were identified as possibly not being installed in accordance with plant design.

The walkdown, however, did not reveal any noticeable deformation, damage, significant pipe movement or other evidence of service induced abnormalities.

On November 1, 1988 and February 10, 1989, respectively, it was determined that the as-built condition of the subject additional hangers were not in accordance with plant design.

Cause of Event The investigation concluded that it is highly unlikely that the deformation of 2GSI-L102 was service induced as there have been no recorded unusual operating conditions, including a Design Basis Earthquake, which could have resulted in such significant deformation. The location of the restraint, on the suction side of the ECCS pumps, supports the likelihood that this type of deformation did not occur during service.

NRC FORM SSSA o U S GPO 1985 0 824 538/455 194LI)

NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (M3l LICENSEE ENT REPORT ILER) TEXT CONTINU ION APPROVED OMB NO. 3150M)04 EXPIRES'/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

D. C. Cook Nuclear Plant- YEAR SEOUENTIAL jest: REV/SION NUME8R 8??1 NUMSER Unit 2 0 5 0 0 0 3 8 9 0 0 2 0 0 0 3 OF 0 5 TEXT //F'moro 8//ocF /8 te////k/8/L r/>> /r/or/8/NRC %%dr/r/36//A'4/ 07)

Cause of Event (continued)

A review of modifications made to the system identified one potential cause for the deformation of 2GSI-L102. In order to facilitate flushing and other startup activities prior to initial unit startup a modification was made to the system, (changing this section of piping to a spool piece) to allow this portion of piping to be removed and replaced with a "jumper" spool piece.

The modification, performed in 1976, was completed with one minor change to the original design; ie, the subject restraint was moved to prevent interference with newly installed flanges. No other problems were noted.

A Quali'ty Control inspection report from August 1977 noted no problems with the restraint. The startup activities removed the modified pipe section and replaced it with a spool piece connecting the ECCS pump suction to the Condensate Storage Tank (CST) (see ATTACHIIENT 1). Upon completion of the startup activities, the piping was restored. It is believed that the deformation of the restraint occurred during this evolution; however, no documentation of such deformation could be located. The corresponding restraint for Unit 1 was examined. There was no simi1ar modification performed on Unit 1 and no deformation of the restraint was seen.

The investigation of 2GSI-L104 and 2GSI-L106 concluded that the inconsistencies with plant design were not service induced, but rather, the as-installed configuration.

Anal sis of Event This event is being reported per 10CFR50.73(a)(2)(ii) as an event that resulted in the plant being in a condition that was outside the design basis of the plant. (Suction line stresses would have exceeded FSAR criteria under design basis seismic conditions) ~

The Donald C. Cook Nuclear Plant is located in a low seismicity area, and historically earthquakes have been of low intensity. To date, a seismic event of Design Basis Earthquake magnitude has not occurred at the Cook Nuclear Plant. Thus, the subject piping system has not been subjected to the Design Basis Earthquake loading. Review of the normal operating system loading indicated that the system was capable of supporting normal operating loads.

A detailed engineering analysis is being performed to determine what the effects of a Design Basis Earthquake would have been on the subject piping system, had it occurred based on the subsequent inconsistencies identified on 2GSl-L104 and 2GSI-L106.

A supplemental report will be submitted by April 7, 1989.

NRC FORM 8664 *U,S GPO;1986 0.624 538/455 (94)3)

NRC Form 366A U.S, NUCLEAR REGULATORY COMMISSION (9431 LICENSEE ENT REPORT (LER) TEXT CONTINUA ION APPROVED OMB NO. 3150-0)04 EXPIRES: 8/3'I/88 FACILITY NAME ill DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQVENTIAL REVISION NVMBER NUMBER D. C. Cook Nuclear Plant-Unit 2 0 5 0 0 0 3 1 6 8 9 0 0 2 0 0 0 4 oF0 5 TEXT //moro FPoco 1I /oEM)oIL Irro////OIM/ NRC Form 3684'4) (17)

Corrective Actions Due to the extent of the deformation of 2GSI-L102, it was not possible to return the restraint to its original design configuration. A revised design was developed to reinforce the restraint and reestablish the gap clearances specified by the original seismic design. A modification was initiated along with an ASME Section XI repair plan to repair the restraint. Repairs

.have been completed and the restraint visually inspected for final acceptance.

Regarding 2GSI-L104 and 2GSI-L106, corrective design has been issued and the supports will be returned to an acceptable configuration prior to return to service of the unit from the current outage.

Failed Com onent Identification None Previous Similar Events None NRC FORM 366A o U,S GPO 1986 0 624.538/455 (94)3)

NRC Form 3$ 6A U.S. NUCLEAR REGULATORY COMMISSION

($ 83)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) yEAR SEOVENTIAL IQ<'EVISION IP> '.% NVMBSR D. C. Cook Nuclear Plant- NUMBER Unit 2 0 6 0 0 0 3 8 9 0 0 2 0 0 0 5 OF TEXT l/Fmore <<>>ce /4/e//rerL I/roe/R/or>>/HRC Form 35543/ (17)

ATTACHMENT 1 NORMAL PIPING CONFIGURATION TQ From ECCS RMST Pumps Support 2-GSI-L102 (Detailed Below)

From TQ CST Aux Feed Pumps PIPING CONFIGURATION USED FOR FLUSHING AND TESTING TQ From ECCS RWST Pumps To From Aux Feed CST Pumps SUPPORT 2-GSI-L102 DETAIL Original As-Found Design Condition

+- Gaps Ranged 1/16" Tvp. from J" to 1" I-Beam Deformation NRC FORM SSBA o U S,GPO.'I 986.0.624 538/455 (983)

Indiana Michigan~

Power Company

~

Cook Nuclear Plant P.O. Box 458 Bridgman. Mi 49106 616 465 5901 INDIANA MICHIGAN PQVlkR February 15, 1989 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-316 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:

89-002-00 Sincerely, C>)i !i,~~~ n....

Y,. G. Smith,/ Jr.

&Plant Manager WGS:clw Attachment CC D. H. Williams, Jr.

A. B. Davis, Region M. P. Alexich III P. A. Barrett J. E. Borggren R. F.. Kroeger NRC Resident Inspector Wayne Scott, NRC R. C. Callen G. Charnoff, Esa.

Dottie Sherman,.ANI Library D. Hahn INPO PNSRC A. A. Blind S. J. Brewer/B. P. Lauzau