IR 05000315/1979011

IE Insp Repts 50-315/79-11 & 50-316/79-08 on 790407-0504. Noncompliance Noted:Failure to Implement Procedure from LER & Failure to Review Mod of Containment Structure

ML17317B371
Person / Time
Site:	Cook
Issue date:	06/11/1979
From:	Masse R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17317B369	List: IR 05000315/1979011 ML17317B368 ML17317B370
References
50-315-79-11, 50-316-79-08, 50-316-79-8, NUDOCS 7907300092
Download: ML17317B371 (13)

Text

U.S.BINUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-315/79-11; 50-316/79-08 Docket No. 50-315; 50-316 License No. DPR-58; DPR-74 Licensee:

American Electric Power Service Corporation Indiana and Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:

Donald C.

Cook Nuclear Power Plant, Units 1 and

Inspection At:

Donald C.

Cook Site, Bridgman, MI Inspection Conducted:

April 7-May 4, 1979

'7 Q Approved By:

D.

C'. Boyd, Acting Chief Reactor Projects Section

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Ins ection Summa Ins ection on A ril 7-Ma

1979 (Re ort No. 50-315/79-11 50-316/79-08)

Areas Ins ected:

Review of Plant Operations, Refueling Activities, Security, Emergency Drill and Licensee Event Reports.

The inspec-tion involved 96 inspector-hours onsite by two NRC inspectors.

Results:

Of the five areas inspected, no items of noncompliance were found in three areas.

One item of noncompliance was noted in each of the two remaining areas.

(Infraction - Failure to implement procedure - Paragraph 7; and Infraction - Failure of PNSRC to review modification - Paragraph 6).

DETAILS 1.

Persons Contacted

• D. Shaller, Plant Manager

• B. Svensson, Assistant Plant Manager

• R. Lease, Operations Superintendent

+R. Dudding, Maintenance Superintendent

• E. Smarrella, Technical Superintendent

• H. Chadwell, Production Supervisor - Unit

C. Murphy,'roduction Supervisor - Unit 2

• J. Stietzel, QA Supervisor W. Cornell, Maintenance Engineer A. Papai, ISI Supervisor The inspectors also contacted a number of operators, tech-nicians and maintenance personnel during the course of the inspection.

"Denotes those present at one or more of the exit interviews.

2.

Review of Plant erations (Unit 2)

The inspector maintained a continuous cognizance of Unit 2 operations including review'f logs and operating records, data sheets, chart recorders, and records of malfunctioning equipment.

The review included checks of:

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Control Room Logs SOE Logs Auxiliary I,ogs'peratingOrders Standing Orders Jumper/Lifted Lead/Blocked Alarm Log Condition Reports The inspector made several tours of Unit 2 checking general housekeeping, radiation controls, instrumentation, fire controls, etc.

No items of noncompliance or deviations were identified.

-2-

3.

Refuelin Activities (Unit 1)

Unit 1 was shutdown for refueling on April 6th.

The outage is scheduled to last approximately 50 days.

Prior to the fuel handling, the inspector verified that all surveillance testing required by procedures and Technical Specifications was com-pleted.

The inspector observed fuel handling operations and verified that all activities were in accordance with Technical Specifications and approved procedures.

The inspector also verified that containment integrity was maintained as required; that refueling crews were properly manned; and that general housekeeping around the refueling areas was adequate.

No items of noncompliance or deviations were identified, 4,

Securit Activities The inspector randomly observed that security activities were in accordance with the Plant Security Plan and implementing procedures.

The observations included Protected Area and Vital Area doors and gates, isolation zones, badging, identification, escorting, search, and communications.

No items of noncompliance or deviations were identified.

On April 18, 1979, the inspector observed an emergency plan drill with the scenario of a heavy object having been dropped onto spent fuel in the spent fuel pit.

All aspects of the drill were reviewed including personnel accountability, evacu-ation, alarms, operator and supervisor actions, communications, and overall coordination.

The inspector attended the drill critique which followed.

No items of noncompliance or deviations were identified, 6.

Containment Structure During a tour of the facility the inspector noted that licensee had made some temporary and permanent attachments to the exterior of the Unit 1 containment.

The temporary attachment was to place a temporary roof over the facade that encloses the steam and feedwater piping that runs to the east steam enclosure.

A series of 2 x 4's were attached to the containment using 1/2

inch bolts bolted:into concrete anchors on 3 to 4 foot centers.

The permanent attachment was a sheet metal ice deflector also attached by 1/2 inch bolts and concrete anchors.

The ice deflector had been installed as RFC 12-2254.

A review of the RFC showed the licensee had classified it as non-safety related.

This appears to be incorrect as it is a modification to pressure vessel which is also seismic class 1.

The modifi-cation is safety related and should have been reviewed by the Plant Nuclear Safety Committee (PNSRC)

as required by Technical Specification 6.5.1.6.d.

The licensee could not provide documentation of approval of the temporary attachment or repair procedure to be used when removed.

The plant personnel were unaware that Construction Department had made the temporary attachment to the containment hence the PNSRC had not reviewed the temporary modification and procedures used as required by Technical Specification 6.5.1.6.d.

7.

Licensee Event Re orts (LER's)

The following LER's were reviewed by the inspector.

Included in the review were selected facility records regarding the events.

The inspector found the events were as described and actions were being taken to prevent recurrence as described in the licensee's report except as noted below.

V Unit

(Closed)

78-69/03L-0 (Closed)

79-01/03L-0 (Closed)

79-03/03L-0 (Closed)

79-05/03L-0 AFD alarm point set above Technical Specification limits, Rod position indication drift.

Surveillance test require longer to perform than allowed by Technical Specification.

Unit operated with position moder-ator temperature coefficient.

(Closed)

79-06/03L-0 Ice Condenser inlet doors open due to PRT rupture disc blowin (Open)

79-07/09L-0 Suction valve for centrifugal charging pump found closed.

The licensee's corrective action to prevent a recur-rence was to review the event with operating shift personnel.

The inspector's review of applicable pro-cedures and administrative controls reveals that if they had been imple-mented the event would not have occurred.

The surveillance test that resulted in the valve being shut was 1-OHP 4030 STP.

005.

The pro-cedure is designated by the licensee as being required in hand while per-forming the steps.

Specific steps were provided to return the pump to the proper lineup.

The operator who did the steps did not have the pro-cedure in hand.

The operator who directed that the steps be performed had the procedure and is the one who initialed the steps as being completed.

It does not appear that the requirement of PMI 2010 to have the procedure in hand and of 1-OHP 4030 STP.

005 were implemented in this case.

This appears to be in noncompliance with Technical Specification 6.8.1.

(Closed)

79-08/03L-0 R-11 and 12 sample pump inoperable.

(Closed)

79-10/03L-0 Diesel essential service water check valve.

The event date on the LER contained a typographical error.

The data should have been February 23, 1979.

The licensee will correct the date.

(Closed)

79-11/03L-0 (Closed)

79-12/03L-0 (Closed)

79-13/03L-0 Auxiliary feedwater valve would not close.

R-ll and 12 sample pump failure.

Auxiliary feedwater valve would not clos (Closed)

79-14/03L-0 Rod position indication drift.

(Closed)

79-15/03L-0 Ice Condenser inlet doors opened due to pressurizer relief tank rupture disk blowing.

Unit 2 (Closed)

79-04/01T-0 (Closed)

79-05/03L-0 (Closed)

79-07/03L-0 Iow fluid oil pressure switches not set within Technical Specifications.

Logic test failure.

Containment high pressure bistable drift.

(Closed)

79-08/03L-0 Turbine stop valve limit switch failure.

8.

Exit Interviews The inspectors met with licensee representatives (denoted in Paragraph 1) at the conclusion of weekly inspection on April 13, 20, 27 and May 4, 1979.

The inspectors summarized the scope and findings of the inspection.

Attachment:

Preliminary Inspection Findings

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DOCKET NUiKERS 50-315 50-316 4.

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DhTE OP XNSPECTXON DPR-58:DPR j4'RIE. 7-13 (97 f

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These preliminary'inspection findings villbe'xeviewe'd by'NRC Supervision/'fanagement at the Region XXX Office and they VQ.1 correspond with you concerning any enforcement action.

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