IR 05000315/1979004

IE Insp Repts 50-315/79-04 & 50-316/79-04 on 790205-09, 12-16,20-23,26-28 & 0301-02.Noncompliance Noted:Door to High Radiation Areas Unlocked

ML17317B124
Person / Time
Site:	Cook
Issue date:	03/19/1979
From:	Baker K, Masse R, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17317B121	List: IR 05000315/1979004 ML17317B120 ML17317B122
References
50-315-79-04, 50-315-79-4, 50-316-79-04, 50-316-79-4, NUDOCS 7904270219
Download: ML17317B124 (15)

Text

U.S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-315/79-04; 50-316/79-04 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:

February 5-9, 12-16, 20-23, 26-28 and March 1 and 2, 1979 Inspectors:

g FLU K.

R. Baker RF& ~

R.

E.

Masse Approved By:

R.

F. Marnick, Chief Reactor Projects Section

Ins ection Summar Ins ection on Februar 5-9, 12-16, 20-23, 26-28 and March 1 and

1979 (Re ort No. 50-315/79-04; 50-316/79-04)

Areas Ins ected:

Observations of surveillance, calibrations, maintenance>,

and security activities; review of operations and followup of events occuring during the inspection.

The inspection involved 159 inspector-hours onsite by two NRC inspectors.

Results:

No items of noncompliance were identified in five of the areas inspected.

In the sixth area,.one item of noncompliance was noted.

(Infraction door to high radiation areas unlocked Paragraph 2.c).

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DETAILS 1.

Persons Contacted

• D. Shaller, Plant Manager

• B. Svensson, Assistant Plant Manager

• R. Lease, Operations Superintendent

• R. Dudding, Maintenance Superintendent

• E. Smarella, Technical Superintendent

• V. Vandenburg, Nuclear Engineer

• J. Stietzel, Quality Assurance Supervisor

• F. Arsenault, Security Supervisor

• R. Begor, Staff Assistant The inspectors also contacted a number of operators, technicians and maintenance personnel during the course of the inspection.

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

2.

Review of 0 erations The inspectors conducted a review of operations.

This review consisted of direct observation of activities, verification of limiting conditions for operations, tours iof the facility and review of records.

The following is a summary of the inspectors activities.

a

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Observations Unit 1 Control Room operations February 5-9, 12-16, 20-23, 26-28 and March 1 and 2, 1979.

Unit 2 Control Room operations February 5-9, 12-16, 20-23, 26-28 and March 1 and 2, 1979.

b.

Records Unit 1 Control Room Log:

February 6 March 2, 1979.

Unit 2 Control Room Log:

February 6 March 2, 1979.

SOE Log:

February 20 March 2, 1979.

Clearance Permits Jumper Logs Data Sheets Radiation Control Logs Radwaste Logs Condition Reports

c.

Tours of the Facilit The facility was toured by the inspectors on February 5-9, 12-16, 20-23, 26-28 and March 1 and 2, 1979.

During a tour of the Auxiliary Building on February 9th, the inspectors found the Unit 2 lower containment access door unlocked.

This finding represents apparent noncompliance with Technical Specification 6.12.2 which requires doors to high radiation areas in excess of 1000 mrem/hr be locked.

Areas in the lower volume exceeded 1000 mrem/hr at the time the door was found unlocked.

d.

Related Activities The inspectors also observed maintenance activities on safety related equipment including ESW pumps, the diesel generator cooling system, APDMS system; calibration of various safety related instrumentation including the radiation monitoring system and the reactor protection system; surveillance testing including radiation monitors, diesel generator 1CD, and pres-surizer level; selected switch and valve positions; liquid release of No.

3 monitor tank; and modification in progress to the APDMS system.

e.

~Ueentit During tours and observation the inspectors observed that the licensee was complying with security requirements.

3.

Licensee Event Re ort (LER) Review The inspector reviewed the licensee's actions and records associated with the following LER's:

Unit 1 (Closed)

(Closed)

78-66/03L-0 78-67/03L-0 (Closed)

78-60/03L-0 (Closed)

78-63/03L-0 (Closed)

78-64/03L-0 (Closed)

78-65/03L-0 RCS leakage greater than 1 gpm.

Auxiliary feedwater valve inoperable.

Rod position indication drift.

Pressurizer level channel drift Rod position indication drift.

Reactor protection system logic test failur (Closed)

78-68/03L-0 Axial flux difference out of target band.

Unit 2 (Closed)

(Closed)'Closed)

78-78/03L-0 78-79/03L-0 78-89/03L-0 Degraded auxiliary feedwater system.

Diesel failed to start.

Axial flux difference out of target band.

(Closed)

78-92/03L-0 Operation with low coolant average temperature.

(Closed)

78-94/03L-0 Cable spreading area halon system inoperable.

(Closed)

78-95/03L-0 Operation with low reactor coolant temperature.

(Closed)

78-96/03L-0 Axial flux difference out of target band.

(Closed)

78-97/03L-0 Operation with low pressure.

(Closed)

78-99/03L-O Operation with low pressure.

(Closed)

78-101/01T-0 Control room pressurization fans inoperable.

(Closed)

79-01/03L-0 Quadrant tilt alarm and missed surveillance.

(Closed)

(Closed)

79-02/03L-0 79-03/03L-0 Inoperable auxiliary feedwater valve.

Reactor trip/safety injection due to steam line differential pressure instrument lines freezing.

During the review of records the inspector noted two job orders (06774 and 13982) were incorrectly filled out.

Both were checked as not being Technical Specification limited.

Both were when the equipment was removed from service.

The time and operability data was not recorded on the form as the result of checking the block

.

indicating it was not Technical Specification limited.

Other

records revealed Technical Specifications were complied with.

Correct use of the job order form was discussed with the licensee.

No items of noncompliance were identified by the inspector.

Unmonitored Release On February 24, 1979, a Unit 2 pilot actuated relief valve on a moisture separator reheater lifted for approximately 35 minutes due to a mechan-ical failure.

At the time of the failure, radioactive Sodium 24 was being circulated throughout the secondary system as part of a secondary system performance test to identify condenser tube leaks.

The licensee assumed that some of the Sodium 24 was discharged to the atmosphere at that time.

Their calculations indicated 1.15 E-11 microcuries per cubic centimeter of Sodium 24 in the steam being released and 6.99 microcuries total discharge.

Both calculations were below applicable Technical Specification and

CFR 20 limits.

At the time of the release the wind was 6 mph out of the east northeast, which resulted in the dispersion of the release over Lake Michigan.

Licensee surveys found no ground or building contamination.

The inspector reviewed actions and calculations associated with the release.

No regulatory limits were exceeded.

Unit 1 Diesel Generators On February 24, 1979, both emergency diesel generators were inoperable for approximately seven minutes.

The CD diesel generator had been removed from service earlier that day and the AB diesel had been test run to verify operability.

The AB diesel was being tested again to fulfillTechnical Specification requirements to demonstrate operability every eight hours when a diesel is out of service.

During this test, the generator field failed to flash. It was necessary to shut the diesel down, install the field flash fuses, and restart the diese3..

The licensee normally pulls the fuses just prior to surveillance test runs due to spurious reactor trips in the past from electrical noise spikes when the field flashed.

Technical Specifications permit continued reactor operation for up to two hours when both diesel generators are out of service, provided two sources of power are available from offsite and certain surveillance testing is accomplisged.

'I During, the initial test'un on the previous night, the AB diesel was started and paralleled wth buses T11A and TllB.

While the AB diesel was running, the CD diesel was removed from service.

However, during this run the AB diesel was operating in a degraded condition (for approximately one hour). " The Unit 1 diesel generators are normally tested using a load bank, but in this test the licensee paralleled the diesel to the buses to verify operability of the diesel generator

output breakers which had been racked out earlier for maintenance work.

To operate the diesel generator in parallel with the buses, load droop control must be switched into the governor circuitry.

This is accom-plished by opening a knife switch on the control room diesel generator control board.

Opening this same knife switch also removes load stripping capability.

The AB diesel was therefore incapable of shedding load and sequencing on blackout or SI loads.

The licensee is currently installing a design change on Unit 1 to alleviate the need to test in this manner.

Unit 2 circuitry does not need to be changed.

No items of noncompliance or deviations were identified.

6 ~

Exit Interviews The inspectors conducted exit interviews on February 9, 16, 23 and March 2, 1979, to discuss inspection findings.

Included in these discussions were:

a.

The apparent item of noncompliance with Technical Specification 6.12.2.

(Paragraph 2.c)

b.

Proper use of the job order form.

The licensee stated that actions would be taken to clear any misunderstanding on the proper methods for filling out a job order with respect to Technical Specification limits, Attachment:

Preliminary Inspection Findings

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