ML17335A131

LER 98-020-01:on 980408,noted Failure to Include Sodium Hydroxide in W Border Computer Program Used to Determine Ph in Containment Sump.Cause Indeterminate.Updated LER Will Be Submitted by 981001.W/980728 Ltr

ML17335A131
Person / Time
Site:	Cook
Issue date:	07/28/1998
From:	Kingseed J, Sampson J AMERICAN ELECTRIC POWER CO., INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-020, LER-98-20, NUDOCS 9808040167
Download: ML17335A131 (6)

Text

CATEGORY 1 REGULA' INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCESSION NBR:9808040167 DOC.DATE: 98/07/28 NOTARIZED: NO 'OCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315

.AUTH. NAME AUTHOR AFFILIATION KINGSEED,J. 'ndiana Michigan Power Co.

SAMPSON,J;R. Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-020-01:on 980408,noted failure to include sodium hydroxide in W BORDER computer program used to determined', pH in containment sump. Cause indeterminate. Updated LER will be submitted by 981001.

DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. E NOTES:

RECIPIENT COPIES 'ECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3. PD 1 1 STANG, J 1 1 R INTERNAL: RAB 2 2 AEOD/SPD/RRAB 1 1 ILE CENTER 1 ~

1 NRR/DE/ECGB 1 1 NR D B 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

'1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE, J H 1

~

NOAC POORE, W. 1 1 NOAC QUEENER,DS 1 1 0 NRC PDR 1 1 NUDOCS FULL TXT 1 1 E

N NOTE TO ALL "RIDS" RECIPIENTS:

PIEASE 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

~ %

American Electric Po r Cook Nuclear Plant One Cook Place Brktgman, MI 49106 6164655901 AMERICAN ELECTRiC POWER

'uly 28, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:

~tttftt tt tttt In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event t

tttt.'8-020-01 Sincerely, J. R. Sampson Site Vice President lmbd Attachment C. J. Paperiello (Acting), Region III J. R. Sampson P. A. Barrett S. J. Brewer R. Whale D. Hahn Records Center, INPO NRC Resident Inspector 9808040%67 980728 "SPDR ADOCK 050003i5 PDR

c' NR(; Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROYED BY OMB NO. 51504104 (4-95) EKPIRES OV50/55 ESTIMATED BVRDEN PER RESPONSE TO COMPLY WITH T)00 MANDATORY LICENSEE EVENT REPORT (LER) INFORMATIONCOLLECTION REGVEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE SICORPORATED RITO THE LICENSNO PROCESS AND FEO BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BVRDEN ESTNATE TO THE VIFORMATIONAND RECORDS MANAGEMENT BRANCH (T4 F55). V.S. NUCLEAR REGVIATORY COMLVSSION, WASHINGTON, DC 205554001,'AND TO THE (See reverse for required number of PAPERWORK REDUCTION PROJECT (51500105). OFFICE OF MANAGEMENT AND BIJDGET. WASHINGTON. DC 2051M digits/characters for each block)

FACILITYNAME (I) DOCKET NUMBER (2) PAGE (0)

Cook Nuclear Plant Unit 1 50-315 1 of 1 TITLE (4)

Interim LER - Containment Recirculation Sump pH Upper Limit Potentially Exceeded Due to Analysis Input Omission EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR A ILI NAM D NUMB R NUMBER NUMBER Cook Unit 2 50-316 A ILITYHAM KE NUMB R 04 08 98 98 020 01 07 28 98 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (): (Check one or more) (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) 00 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) SI Ab5Vacl be)0Nr Or 50.36(c)(1) 50.73(a)(2)(v) eI NRC Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12)

TELEPMONE NUMBER (InoNde Area Code)

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

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MON H YES .NO SUBMISSION X DATE (15) 10 01 98 (If Yes, complete EXPECTED SUBMISSION DATE)

Abstract (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On April 8, 1998, with Units 1 and 2 in Cold Shutdown, as a result of questions raised by personnel performing a safety system functional inspection of the Containment Spray system, it was determined that the Westinghouse BORDER computer program used to determined the pH in the containment sump had not included the sodium hydroxide contained within the ice condenser ice bed. Failure to include the sodium hydroxide in the calculation could potentially result in the containment sump pH value exceeding the maximum pH limit following a Loss of Coolant Accident. An ENS notification was made at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> EDT in accordance with 10CFR50.72(b)(2)(i), for an unanalyzed condition discovered while the plant was shutdown. This interim LER is therefore submitted in accordance with 10CFR50.72(a)(2)(i).

The Technical Specification limit for pH in the containment sump is 9.5. Preliminary calculations including the from the ice bed indicated a potential value of 9.7, in excess of the Technical Specification limit. Subsequent sodium'ydroxide calculations are showing, however, a maximum pH value of 9.5. Investigation is still ongoing to determine the root cause of why the sodium hydroxide was not included in the original calculation. The result of this investigation will be provided in an update to this LER, which will be provided by October 1, 1998. "

NRC FORM 366 (4-95)