ML17335A495

LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr

ML17335A495
Person / Time
Site:	Cook
Issue date:	01/29/1999
From:	Brassart G, Sampson J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-059, LER-98-59, NUDOCS 9902030311
Download: ML17335A495 (5)

Text

CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDE)ACCESSION NBR:9902030311 DOC.DATE: 99/01/29 NOTARIZED:

NO DOCKET¹FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFILIATION BRASSART, G.Indiana Michigan Power Co.(formerly Indiana&Michigan Ele SAMPSON,J.R.

Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-059-00:on 981230,interim LER-single failure in containment spray sys could result in containment spray pH outside design occurred.Investigation into condition continuing.

Update will be submitted by 990514 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL I SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD3-3 PD COPIES LTTR ENCL 1 1 RECIPIENT ID CODE/NAME STANG,J COPIES LTTR ENCL 1 1 0 INTERNAL: AEOD/SPD RAB NRR/DE/EELB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN3 FILE 01 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1'1 1 1 1 AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB LITCO BRYCE,J H NOAC QUEENER,DS NUDOCS FULL TXT 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D U N NOTE TO ALL MRIDSM RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22 0

Indiana Michigan~Power Company Gxk Buaer~>as xe xr,-a i Bridyncn.ha 491 06 ele-'ea~s Z INDIANA MICHIGAN IaOM%R January 29, 1999 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 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 LER 315/98-059-00,"Single Failure In Containment Spray System Could Result ln Containment Spray pH Outside Design" No commitments were identified in this submittal.

Sincerely,i.k4~J.R.Sampson Site Vice President/mbd Attachment c: J.L.Caldwell (Acting), Region III R.P.Powers P.A.Barrett D.F.Kunsemiller R.Whale D.Hahn Records Center, INPO NRC Resident Inspector+f1 lrr 99020303ii 990i29 PDR ADQCK 050003i5 S PDR

a NRC Form 366 U.S.NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED BY OMB No.3160.0104 EXPIRES 06/30/2001 ESTIMATED SVRDEN PER RESPONSE TO COMPLY WITH TIOS MANDATORY INFORMATION COLLECTION REOVEST 500 HRS REPORTED LESSONS LEARNED ARE WCORPORATED INTO THE UCENSING PROCESS ANO FED SACK TO INDVSTRY.FORWARD COMMENTS REGARDING SVRDEN ESTasATE TO THE INFORMATION AND RECORDS MANACEMENT SRANCH IT%F55).V.S.NUCLEAR REGIAATORY COMMISSlON, WASHINGTON.

DC 20555400I.

AND TO THE PAPERWORK REDVCTION PRO)ECT ts)50o)0I)

OFFICE OF MANAGEMENT ANO BVDCET.WASICNGTON.

DC 20505 FACIUTY NAME tl)Cook Nuclear Plant Unit 1 DOCKET NUMBER I2)05000-315 PAGE IS)1 of 1 TITLE 14)Interim LER-Single Failure In Containment Spray System Could Result In Containment Spray pH Outside Design EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY 12 30 YEAR YEAR 1998 1998 SEQUENTIAL NUMBER 059 00 01 29 1999 REVISION NUMBER MONTH DAY YEAR A ILI NAM DC Cook-Unit 2 ACILI NAM D NUMB 05000-316 K NUM OPERATING MODE (9)POWER LEVEL(10)000 e)(11)20.2201 (b)20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR g: (Check one or mor 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)

LICENSEE CONTACT FOR THIS LER (12)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)

OTHER Speci/r Ir)Abstract Deicer or n NRC Form 366A NAME Mr.Gary Brassart, Nuclear Safety Analysis Supervisor TELEPHONE NUMBER (Incsvde Area Code)616/697-5106 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX sl Mu N SUPPLEMENTAL REPORT EXPECTED (14)X YES (If Yes, complete EXPECTED SUBMISSION DATE)NO EXPECTED SUBMISSION DATE (15)MONTH 05 DAY 14 1999 Abstract (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)(16)In December 1998, plant personnel identified an issue regarding a single failure in the Containment Spray (CTS)System which could result in loss of sodium hydroxide chemical addition to a single train of CTS during injection phase.On December 30, 1998, it was determined that this represented a condition outside the design bases.Therefore, this interim report is being submitted in accordance with 10 CFR 50.73 (a)(2)(ii)(B) as a condition outside the design bases of the plant.The Containment Spray System operates in response to a Loss of Coolant Accident (LOCA)or MSLB inside containment.

Sodium hydroxide solution from the spray additive tank is added to the spray using an eductor, and ensures that the pH of the spray and sump are maintained within the established limits.If a single valve supplying CTS flow through the eductor for one train of CTS fails closed, chemical addition to that train would be stopped.Lack of sodium hydroxide addition results in borated water from the RWST, with a pH of 4.5, being sprayed on components inside containment from the affected train ofCTS.Theequipmentincontainmentisqualified fora pHrangeof6.8to12.9.

Therefore, spraying RWST water without sodium hydroxide additive results in spray pH outside the range used for equipment qualification.

This condition appears to be part of the original design of the plant.Investigation into this condition is continuing, and is expected to be complete April 30.An update to this interim LER will be submitted by May 14, 1999.NRC FORM 366 (6-1998)