ML17334B745

LER 98-020-00:on 980408,interim LER - Determined That Containment Recirculation Sump Ph Upper Limit Exceeded. Caused by Analysis Input Omission.Condition Remains Under Evaluation to Determine Appropriate action.W/980423 Ltr

ML17334B745
Person / Time
Site:	Cook
Issue date:	04/23/1998
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 9804280038
Download: ML17334B745 (3)

Text

e CATEGORY REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9804280038 DOC.DATE: 98/04/23 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTK.NAME AUTHOR AFFILIATION KZAGSEED,J. Indiana Michigan Power Co.

SAMPSON,J.R. Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-020-00:on 980408, interim LER - determined that containment recirculation sump pH upper limit exceeded.

Caused by analysis input omission. Condition remains under evaluation to determine appropriate action.W/980423 ltr.

DISTRIBUT10N CODE: ZE22T COPIES RECEIVED:LTR ENCL SIZE:

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

RECIPIENT COPIES RECIPXENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG,J 1 1 INTERNAL: . 8 2 2 AEOD/SPD/RRAB 1 1 FILE CENT 1 1 NRR/DE/ECGB 1 1' EELB 1 1 NRR/DE/EMEB 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRZB 1 1 RES/DET/EIB 1 1 RGN3 'ILE 01 1 1 D

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

E N

NOTE TO ALL "RIDS" 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 24 ENCL 24

Indiana Michigan Power Company aeC'ac<=ace

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a IMDIAbfA NICHIGAM POSER April 23, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled the following report is being submitted:

98-020-00 Sincerely, J. R. Sampson.

$ Q Site Vice President lmbd Attachment A. B. Beach, Region III E. E. Fitzpatrick P. A. Barrett S. J. Brewer R. Whale D. Hahn Records Center, INPO NRC Resident Inspector yV'804280038 980423 PDR ADOCK 050003i5 8 PDR

HRC FORH 366 U.S. HUCLEAR REGULATORY COMMISSIOH , PPROVEO BY OMB HO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY NITH THI IHFDRHATIDH coLLEGTIDN REGUEsT: 50.0 HRs. FDRNAR LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIHATE To TH IHFORHATIOH AND RECORDS MANAGEMENT BRANCH (HNB 7714), U.S. NUCLEAR REGULATORY COMMISSIONg IIASMINGTOH, DC 20555-0001, AND TO THE PAPERNOR REDUCTION PROJECT (3150-0104), OFFICE 0 MANAGEHENT AND BUDGET IIASHINGTOH DC 20503.

FACILITY NAHE (1) (2)

Donald C. Cook Nuclear Plant - Unit 1 DOCKET NUHBER Page1 of1 50.315 TITLE (4)

Interim LER -Containment Recirculation Sump pH Upper Limit Exceeded Due to Analysis Input Omission EVENT DATE 5 LER HUMBER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 SEQUENTIAL REVISION FACILITY NAME DOCKET HUHBER MONTH DAY YEAR YEAR MON'IH NUMBER NUMBER OAY Cook - Unit 2 50-316 FACILITY HAME DOCKET NUMBER 04 08 98 98 020 00 04 23 OPERAT IHG TH S REPORT IS SUBHITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR  : Check one or mo e 11 MODE (9) 20.2201(b) 20.2203(a)(3)(I) 50.73(a)(2)(iii) 73.71(b)

PONER 0

20.2203 a 1 20.2203 a 3 ii 50.73 a 2 iv 73.71o LEVEL (10) 20.2203(a)(2)(I) 20.2203(a)(4) 50.73(a)(2)(v) OTHER 20.2203 a 2 ii 50.36 c 1 50.73 a 2 vii (Specify in 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(viii)(A) Abstract below 20.2203(a)(2)(iv) 50.73(a)(2)(I) 50.73(a)(2)(viii)(B) and in Text, HRC Form 366A) 20.2203(a)(2)(v) 50 73(a)(2)(il) 50'73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER 12 NAHE TELEPHOHE NUMBER (Include Area Code)

Mr. Jeb Kingseed, Nuclear Safety Analysis Manager 616 697-5106 COMPLETE ONE LINE FOR EACH COMPOHENT FAILURE DESCRIBED IN THIS REPORT REPORTABLE REPORTABLE CAUSE SYSTEH COMPOHEHT MANUFACTURER CAUSE SYSTEM COMPONENT MAHUFACTURER TO HPRDS TO HPRDS gyes:;;4):

SUPPLEHENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR YES SUBMISSION X (If yes, complete NO 07 31 98 EXPECTED SUBMISSION DATE). DATE (15)

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

On April 9, 1998, an ENS notification was made in accordance with 10 CFR 50.72(b)(2)(i), for a condition which was found while both units were shutdown, which had it been found while the reactor was in operation, could have resulted in the nuclear plant being in an unanalyzed condition. This notiTication is a result of an issue discovered during a safety system functional inspection of the containment spray system.

It has been determined that the Westinghouse method for calculating the maximum pH in the containment sump after an accident might result in a pH that is too basic. While responding to an AEP audit question, Westinghouse discovered that the sodium hydroxide contained within the ice condenser ice beds had not been included in any of the BORDER analysis performed for Cook Plant. BORDER is a computer program used to determine the pH in the containment sump. The impact of this is that the actual containment sump pH value following a toss of coolant accident exceeds the maximum pH limit in the Bases for Technical Specification (T/S) 9.5. Preliminary calculations indicate a pH value of approximately 9.7 is possible. The T/S is based on Branch Technical Position MTEB 6-1 on the pH for emergency cooling water for PWRs. The reference states that the pH should be in the high end of the range of 7.0 to 9.5 for greater assurance that stress corrosion cracking will not occur. The reference does not give any guidance on what the affects would be if 9.5 is exceeded, thus the unanalyzed condition. The significance of the impact of the pH above the range in the T/S requires further evaluation.

This condition remains under evaluation to determine appropriate action to rectify this issue. Additionally, this issue is being evaluated for potential 10CFR Part 21 reportability. An update to this interim LER will be submitted by July 31, 1998.