ML17335A378

LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr

ML17335A378
Person / Time
Site:	Cook
Issue date:	12/07/1998
From:	Brassart G, Sampson J INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-007-01, LER-98-7-1, NUDOCS 9812110024
Download: ML17335A378 (4)

Text

~ CATEGORY, 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9812110024 DOC.DATE: 98/12/07 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME 'UTHOR AFFILIATION BRASSART,G. Indiana Michigan Power Co.

SAMPSON,J.R. Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-007-00:on 981106,high energy line break effects in auxiliary FW sys was noted. Cause of event is under investigation 6 will be completed by 990220.Updated LER will be submitted by 990310.With 981207 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR . ENCL SIZE:

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

NOTES:

'ECIPIENT COP1ES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG, J 1 1 INTERNAL: AEOD S RAB 2 2 AEOD/att. rat 491 06 616 466 6601 Z

INDIANA Il/IICHIetAN POWER December 7, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating License DPR-74 Docket No. 50-316 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event LER 316/98-007-00, "High Energy Line Break Effects On Auxiliary Feedwater System."

No commitments have been identified in the attached document.

Sincerely, J. R. Sampson Site Vice President

/mbd Attachment J. L. Caldwell (Acting), Region III R. P. Powers P. A. Barrett J. B. Kingseed R. Whale D. Hahn Records Center, INPO NRC Resident Inspector

'118i2ii0024 98i207 PDR ADOCK 050003i6 PDR

t NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVEO BY OMB Ho. 31504104 EXPIRES 05I3052001 I -1998) KSTSIATKO SVROKN PKR RESPONSE TO COMPLY WIM THIS MANDATORY INFORMATIONCOLLECTION RKGVKST: 50.0 HRS. RKPDRTKD LESSONS LEARNED ARK NCORPORATED Srro THE UCKNSING PROCESS ANO FKD BACK TO INOVSTRY.

LICENSEE EYENT REPORT (LER) FORWARD COMIIKNTS RKCARDSIG SVROKN KSTIIATK TO THK INFCRMATION ANO RKCDRDS MANAGKMKNT SRANCH (T+ F551. V S. NVCLKAR RfCIAATDRY COMMISSION, WASISNGTON. DC 2055$ 0001. ANO TO THK PAPERWORK RKOVCTION PROJECT D1500104), OFFICE OP MANACKMKNTAND SVOCKT. WASISNGTOIL DC (See reverse for required number of gogo digits/characters for each block)

FACIUTY NAME (1) DOCKET NUMBER(2) PAGE (5)

Cook Nuclear Plant Unit 2 05000-316 1 of 1 T(TLE (4I Interim LER - High Energy Line Break Effects On Auxiliary Feedwater System EVENT DATE (5) LER NUMBER (6) REPORT DATE P) OTHER FACII.ITIES INVOLVED(8)

A ILI NUM SEQUENTIAL REVISION MONTH . DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR A ILI NU 11 06 1998 1998 007 00 12 07 1998 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR li: (Check one or mo re) (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) 100 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)(u)

Ig-'~~.'lgal)i~Fl 20.2203(a)(2)(iv) 50.36(c)(2) . 50.73(a)(2)(vii)

Speafr SI Abeveol belorr eo <<I or n NRC Form SMA LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUMBER (Inobde Aree Cade)

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

REPORTABLE REPORTABLE TO CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX SYSTEM COMPONENT MANUFACTURER EPIX SUPPLEMENTAL REPORT EXPECTED (14 EXPECTED MONTH DAY YEAR X YES SUBMISSION 03 10 1999 (If Yes, complete EXPECTED SUBMISSION DATE NO DATE 15 Abstract (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) ln July 1995, the fire door/High Energy Line Break (HELB) door for the startup blowdown fiash tank room was blocked open for approximately 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> to allow draining of the Essential Service Water (ESW) header. At the time, the condition was evaluated and it was concluded that the condition was acceptable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This conclusion was based upon the assumption that the HELB would be detected and isolated within 10 minutes and that the line break would not result in automatic actions.

As part of the recent Auxiliary Feedwater (AFW) System Safety System Functional Inspection, the assumption that the break would be isolated within 10 minutes was revisited and determined not to be valid. A subsequent review of Westinghouse WCAP 10961 revealed that automatic action, a reactor trip, would occur at 12 minutes into the event.

Based on the new information, on November 6, 1998 it was determined that a HELB in the startup blowdown flash tank room would potentially expose the motor control centers (MCC) in the area to a steam environment and higher temperatures than they are qua}if(ed to withstand. Auxiliary Feedwater would potentially be lost because the valves which supply ESW to the AFW pumps are located on these MCCs. It was determined that this condition represented a condition outside the design bases, reportable under 10 CFR 50.?3 (a)(2)(ii)(B).

Investigation into this condition and potential effects of the increased temperature and steam environment on required equipment is ongoing, and is expected to be completed by February 20, 1999. An update to this interim LER will be submitted by March 10, 1999.

NRC F R 366 (6-1998)