05000316/LER-1997-003-01, :on 970826,determined That Unit Operated Outside Design Basis During Unit 2 1996 Refueling Outage. Investigation Into Event Continuing.Update to Interim LER Will Be Issued by 971117

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:on 970826,determined That Unit Operated Outside Design Basis During Unit 2 1996 Refueling Outage. Investigation Into Event Continuing.Update to Interim LER Will Be Issued by 971117
ML17333B097
Person / Time
Site: Cook 
Issue date: 10/21/1997
From: Kingseed J
INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17333B096 List:
References
LER-97-003-01, LER-97-3-1, NUDOCS 9710290121
Download: ML17333B097 (1)


LER-1997-003, on 970826,determined That Unit Operated Outside Design Basis During Unit 2 1996 Refueling Outage. Investigation Into Event Continuing.Update to Interim LER Will Be Issued by 971117
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(iii)

10 CFR 50.73(a)(2)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)(ii)

10 CFR 50.73(a)(2)(viii)(B)

10 CFR 50.73(a)(2)(x)
3161997003R01 - NRC Website

text

HRC fORR 366 (5.92)

U.ST HUCLEAR REGULATORY COMMISSION LXCENSEE EVENT REPORT (LER)

APPROVED BY OMB NO. 3150.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER

RESPONSE

TO COMPLY MITH THI IHFORMATION COLLECTION REQUEST: 50.0 HRS.

FORMAR COMMENTS REGARDING BURDEN ESTIMATE TO TH INFORMATION AND RECORDS HANAGEMENT BRANCH (HNB 7714),

U.S.

NUCLEAR REGULATORY COMMISSIONr MASHINGTON, DC 20555-0001, AND TO THE PAPERMOR REDUCTION PROJECT (3150-0104),

OFFICE 0

HANAGEMENT AND BUDGET MASHINGTON DC 20503.

FACILITY NAME (1)

Donald C. Cook Nuclear Plant - Unit 2 DOCKET NUMBER (2) 50-316 Page 1 of 1 TITLE (4)

Interim LER Revision-Dual Train Component Cooling Water Outage During Unit 2 Refueling Outage Results in Condition Outside the Desi n Basis MONTH OAY YEAR YEAR SEQUENTIAL NUMBER REVISION NUHBER HONTH OAY FACILITY NAME None DOCKET NUMBER 08 26 97 97 003 01 10 21 FACILITY NAME DOCKET HUMBER OPERATING MODE (9)

POMER LEVEI. (10) 100 20.2201(b) 20.2203(a)(2)(i) 20.2203(a)(3)(i) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(v) 73.71(b)

OTHER

~

~ ':<4

~

A a..ra 4 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 50.36(c)(2) 50.73(a)(2)(i)

X 50.73(a)(2)(ii) 50 73(a)(2)(v>> i)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x)

(Specify in Abstract'eloM and in Text,NAME Mr. Jeb Kingseed, Nuclear Safety and Analysis Manager TELEPHONE NUMBER (Include Area Code) 616/697-5106

CAUSE

SYSTEM COMPONENT MAHUFACTURER REPORTABLE TO HPROS

CAUSE

SYSTEH COMPONENT HANUFACTURER REPORTABLE TO HPRDS X YES NO EXPECTED SUBMISSION DATE 15 17 97 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On August 26, 1997, with Unit 2 at 100 percent Rated Thermal Power, it was determined that the unit had operated outside the design basis during the Unit 2 1996 refueling outage.

Itwas determined that this event was reportable under 10CFR50.72(b)(1)(ii)(B) as a condition outside the design basis, and an ENS notification was made at 1553 on August 26, 1997. This interim LER is being submitted under 10CFR50.73(a)(2)(ii).

A safety evaluation had been performed for the Unit 2 full core offload, assuming one train of Spent Fuel Pool (SFP)

Cooling available.

This safety evaluation covered the 1996 Unit 2 refueling outage schedule which included a dual train Component Cooling Water (CCWt outage.

The safety review addressed the FSAR Section 9.4 attributes of the SFP dealing with bulk pool temperature requirements, however, failed to address FSAR Section 9.5 attributes on associated CCW cooling requirements, such as the assumption that the CCW supply to the SFP heat exchanger is from the non-accident unit.

Investigation into this event is continuing.

In the interim, information concerning this condition has been made available to Engineering and Scheduling personnel.

Scheduling has reviewed the outage schedule for the upcoming Unit 2 refueling outage and verified that no dual train CCW outage is planned, and the appropriate procedure is being revised to require 1 train of CCW to be operable in support of Spent Fuel Pool Cooling during Modes 5, 6 and when defueled.

Evaluation of the safety consequences of this condition, and other similar conditions reported separately via ENS during the period August 8, 1997 to September 12, 1997, is ongoing. An update to this interim LER willbe issued by November 17, 1997.

97i02'giOi2i 97i023 PDR ADQCK.050003i6 S

PDR