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 DOCKET ¹ FACIL: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 COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG,J 1 1 INTERNAL: AEOD/SPD RAB 2 2 AEOD/SPD/RRAB 1 1 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOHB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 RES/DET/EIB 1 1 RGN3 FILE 01 1 1 D

LITCO BRYCE,J H EXTERNAL: L ST LOBBY WARD 1 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 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

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ele -'ea 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

+rr f1 l 99020303ii 990i29 PDR ADQCK 050003i5 S PDR

a NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 3160.0104 EXPIRES 06/30/2001 (6-1998) ESTIMATED SVRDEN PER RESPONSE TO COMPLY WITH TIOS MANDATORY INFORMATIONCOLLECTION REOVEST 500 HRS REPORTED LESSONS LEARNED ARE WCORPORATED INTO THE UCENSING PROCESS ANO FED SACK TO INDVSTRY.

LICENSEE EVENT REPORT (LER) FORWARD COMMENTS REGARDING SVRDEN ESTasATE TO THE INFORMATIONAND 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 (See reverse for required number of 20505 digits/characters for each block)

FACIUTY NAME tl) DOCKET NUMBER I2) PAGE IS)

Cook Nuclear Plant Unit 1 05000-315 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)

A ILI NAM D NUMB SEQUENTIAL REVISION DC Cook - Unit 2 05000-316 MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR ACILI NAM K NUM 12 30 1998 1998 059 00 01 29 1999 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR g: (Check one or mor e) (11)

MODE (9) 20.2201 (b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50.73(a)(2)(viii)

POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)

LEVEL(10) 000 73.71 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v)

Speci/r Ir) Abstract Deicer 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) or n NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Incsvde Area Code)

Mr. Gary Brassart, Nuclear Safety Analysis Supervisor 616/697-5106 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE TO CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER EPIX sl Mu N

SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY X YES SUBMISSION 05 14 1999 (If Yes, complete EXPECTED SUBMISSION DATE) NO DATE (15)

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)