IR 05000313/1978036

IE Insp Repts 50-313/78-36 & 50-316/78-37 on 781107-09, 12-17,20-22,27-30 & 1201,04-08.No Noncompliance Noted.Major Areas Inspected:Observation of Surveillance Calibrations, Maint Activities & Review of Operations

ML17317A976
Person / Time
Site:	Cook, Arkansas Nuclear
Issue date:	01/08/1979
From:	Baker K, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17317A975	List: IR 05000313/1978036 IR 05000315/1978036
References
50-315-78-36, 50-316-78-37, NUDOCS 7903080491
Download: ML17317A976 (17)

Text

U.S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-315/78-36; 50-316/78-37 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 Plant, Units 1 and

Inspection At:

Donald C.

Cook Site, Bridgman, MI Inspection Conducted:

November 7-9, 13-17, 20-22, 27-30; December 1,

and 4-8, 1978 A %4cP Inspector:

K. R.

Baker Approved By:

R. F. Warnick, Chief Reactor Projects Section

Ins ection Summar Ins ection on November 7-9 13-17 20-22 27-30'ecember

and 4-8 1978 (Re orts No. 50-315/78-36'0-316/78-37)

Areas Ins ected:

Observations of surveillance, calibrations, and maintenance activities, review of operations, observations of security activities, review of licensee event reports, followup of IE Bulletins and Circulars, and followup of events occurring during the inspection.

The inspection consisted of 107 inspector-hours onsite by one NRC resident inspector.

Results:

No items of noncompliance or deviations were identified in the areas inspected.

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DETAELS 1.

Persons Contacted

• D. Shaller, Plant Manager

• B. Svensson, Assistant Plant Manager C. Shay, Resident Management Advisor R. Dudding, Maintenance Superintendent

• E. Smarrella, Technical Supervisor R. Lease, Production Supervisor H. Chadwell, Production Supervisor

• J. Stietzel, QA Supervisor L. Matthias, Administrative Supervisor

• R. Keith, Operations Superintendent J. Dolan, Senior Executive Vice President Engineering, AEPSC R. Jurgensen, Chief Nuclear Engineer, AEPSC The inspector also contacted a number of operators, technicians, and maintenance personnel during the course of the inspection.

2.

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

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

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

The following is a summary of the inspector's activities:

a.

Observations Unit 1 Control Room operations November 8, 13, 14, 20, 21, 27; December 1, 5, 6, and 7.

Unit 2 Control Room operations November 8, 9, 13, 14, 20, 21, 27; December 1, 5, 6, and 7.

b.

Records Unit 1 Control Room Log November 4 30; December 1-8 Unit 2 Control Room Log November 4 30; December 1-8 SOE Log - November 13 30; December 1-8 Clearance Permits

Jumper Logs Data Sheets Radiation Control Logs Radwaste Logs Condition Reports c.

Tours of the Facilit The facility was toured by the inspector on November 8, 9,

13, 17, 20-22, and 27; December 1,

and 4-8.

d.

The inspector also observed maintenance activities on safety related equipment, calibration of nuclear instru-ments, surveillance testing of Unit 2 diesels, and verified selected valve positions.

e.

During tours and observation the inspector observed that the licensee was co~lying with security 'requirements.

No items of noncompliance were, noted.

3.

~Meetin On November 29, 1978 the inspector met with the Senior Executive Vice President and the Chief Nuclear Engineer of AEPSC.

Operating trends and performance were discussed.

4.

Fire On November 13, 1978 the inspector observed the licensee's repsonse to a fire under the Unit 2 Electrical Generator.

The fire was caused by maintenance activities igniting hydrogen gas leaking from the generator.

The potentially damaging fire was controlled and extinguished by the use of plant equipment and personnel with minimal damage occurring.

Two maintenance men working in the area received burns which were treated at a local hospital.

They returned to work the same day.

No reactor safety related equipment was involved in the fire and there was no radioactive material involved in the fire.

No items of noncompliance were identified by the inspector.

5.

Licensee Event Re orts (LER)

The inspector reviewed the following LER's and the licensee's actions and records associated with them:

Unit 1 (Closed)

78-042/03L-0 (Closed)

78-047/03L-0 Failure to complete surveillance within required time.

Low temperature on heat traced line.

(Closed)

78-050/03L-0 (Closed)

78-053/03L-0 Boron Injection throttle valves incorrectly adjusted.

Containment atmosphere radiation monitor failure.

(Closed)

78-054/03L-0 Ice condenser inlet door monitoring system inoperable.

(Closed)

78-057/03L-0 Auxifliary feedwater pump governor failure.

(Closed)

78-058/03L-0 Nonconservative calculation F

by APDHS.

z (Closed)

78-059/03L-0 Pressurizer level channel drift.

Unit 2 (Closed)

78-034/03L-0 78-034/03L-l Containment recirculation fan timer drift.

(Closed)

78-046/03L-0 Diesel lube-oil cooler leak.

(Closed) '8-065/03L-0 Diesel inoperable due to lube oil problem.

(Closed)

78-066/03L-0 Failure of airlock interlock.

(Closed)

78-069/03L-0 Reactor protection system bistable failure.

(Closed)

78-070/03L-0 Diesel generator declared inoperable.

(Closed)

78-071/03L-0 Ice condenser doors opened by damper failure.

(Closed)

78-075/03L-0 Rod position indication failure.

(Closed)

78-076/03L-0 Solid state protection system logic card failure.

(Closed)

78-077/03L-0 Turbine stop valve limit switch failur.

Unit 2 Containment S ra S stem Check Valves-1/

II On November 21, 1978 the licensee noted water leaking from the upper containment spray nozzles in Unit 2.

No leakage was noted from the lower containment nozzles.

This indicated that there might be an obstruction in the supply to the lower header.

Investigation revealed that the check valves in the supply lines to the lower containment headers were installed backwards.

This removed the capability to provide spray to the lower containment.

The valves were removed and rein-stalled correctly.

The licensee verified correct instal-lation of the other check valves in the containment spray system of both units.

The inspector verified the correct installation of the Unit 2 check valves.

Investigation indicated the valves were incorrectly installed by construction personnel following system testing and flushing.

The licensee is initiating a design change to eliminate the need to remove these valves during future testing.

The licensee reviewed his QA program for operations and determined that requirements do now exist which would reduce the likelihood of similar events occurring during operation even if done by construction personnel.

A review of facility drawings and procedures indicates that these check valves are unique in that they are the only ones that are,not flow tested on a frequent basis.

No additional items of noncompliance were identified by the inspector.

7.

Locked Valves On November 27, 1978 the inspector noted that Unit 2 valves RH113E and RH113W were not locked.

These valves are RHR pump discharge valves.

Similar valves in Unit 1 are locked.

A review of the valve lineup procedure

OHP 4021.008.002 did not reveal a requirement to lock these valves.

Plow diagram 1-2-5143 did indicate these valves should be locked.

This was brought to the attention of the licensee.

The valves were locked and included in procedure 2-OHP-4030 STP 035 Locked or Sealed Valve Position Logging.

1/

LER 78-090/01T-No items of noncompliance were noted.

8.

IE Bulletins and Circulars (Closed)

The inspector reviewed the licensee's actions regarding IE Circulars No. 78-09 and No. 78-13.

The licensee has reviewed the circulars and is taking actions where required.

(Open)

IE Circular No. 78-05:

Licensee has not completed his action associated with this circular dated Hay 26, 1978.

Review action was requested by AEPSC of the plant by June 22, 1978.

This was assigned to the Operations Department.

Several reminder memos were noted in the file.

Operations had not completed this item by the time of inspection.

(Open)

IE Circular No. 78-O6:

Licensee has not completed his review and actions associated with this circular dated May 31, 1978.

A target date of June 21, 1978 had been established for th'is circular review.

AEPSC documented its review in October 25, 1978.

The plant has questions regarding the review conducted so the review has not been completed.

9.

Exit Interviews The inspector conducted exit interviews on November 9, 17, 22; December 1 and 8, 1978 to discu'ss inspection findings.

Included in these were discussions of:

a.

Locking and sealing of valves.

b.

Apparent slow response in the review and resolution of IE Circulars.

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