IR 05000315/1979024
| ML17318A604 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/02/1980 |
| From: | Boyd D, Masse R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17318A602 | List: |
| References | |
| 50-315-79-24, 50-316-79-21, NUDOCS 8002110079 | |
| Download: ML17318A604 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
=Report No.:
50-315/79-24; 50-316/79-21 Socket 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
$
Inspection At:
Donald C.
Cook Site, Bridgman, MI I
Inspection Conducted:
October 6 - November 30, 1979 Inspector:
R. E. Masse
/-8 -80 Approved By:
D.
C. Boy
, Chief Reactor Projects, Section
/ -3 -gO Ins ection Summar Ins ection on October 6-November
1979 (Re ort No. 50-315/79-24; 50-316/79-21)
Areas Ins ected:
Review of Operations, Security, Thermal Power Evalua-tions, Refueling Activities, Procurement, Radiation Protection and I,icensee Event Reports (LER's).
The inspection involved 134 inspector-hours onsite by the NRC Resident Inspector.
Results:
Of the seven areas inspected, no items of noncompliance were identified in six.
In the Operations area, two items of noncompliance were identified as follows:
Control of "High Radiation Area" doors-Infraction (Paragraph 2) and control of ignition sources - Infraction (Paragraph 2).
DETAILS Persons Contacted-D. Shaller, Plant Manager-B. Svensson, Assistant Plant Manager
- E. Townley, Assistant Plant Manager
+R. Iease, Operations Superintendent-R. Dudding, Maintenance 'Superintendent-J. Stietzel, Quality Assurance Supervisor-T. Beilman, Quality Assurance Auditor D. Engle, Performance Engineer R. Keith, Outage Coordinator D. Duncan, Instrument Engineer The inspector also contacted a number of operators, technicians, and maintenance personnel.
-Denotes those present at one or more of the exit interviews.
Plant 0 erations The inspector reviewed plant operations including examinations of Control Room Log Books, Auxiliary Logs, Shift Operating Engineer Log Book, Operating Orders, Jumper Iogs and Equipment Clearance Logs for the reporting period.
The inspector made visual observations of routine surveillance and functional tests in progress, and observed offshift activities at various times during the period, This review was conducted to verify that facility operations were in conformance with requirements established under Technical Specifications, 10 CFR, and approved procedures.
A review of the Licensee's Condition Reports was conducted'o verify that violations of Technical Specifications were correctly identified and reported.
The inspector conducted random tours throughout the period and noted that instrumentation was functioning properly, radiation controls were adequate, fluid leaks and piping vibrations were minimal, plant housekeeping/cleanliness were.adequate, and that fire hazards were minimal.
The inspector observed shift turnovers to verify that plant and component status and problem areas were being turned over to relieving shift personnel.
On one of the aforementioned tours on November 7, 1979, the inspector noted that door jj370 (entrance to Unit 2 containment vestibule area)
was propped open by an Argon purge hose being used for a welding job in that area.
This area is posted as a "High Radiation Area" and is required to be locked pursuant to PMP 6010 RAD.002.
The door was un-guarded.
This finding represents an apparent item of noncompliance with respect to Technical Specification 6.8.1 requiring procedure adherence.
- 2 "
The inspector also noted that the welding taking place in the Unit 2 vestibule area did not appear to be covered by an active welding permit.
A permit was not in evidence at or near the job site.
PMI 2275 requires one copy of a "Welding, Burning, or Grinding Permit" be posted in the work area.
This finding also represents apparent item of noncompliance with respect to Technical Specification 6.8.1 requiring procedure adherence.
Both of these concerns were brought to the attention of the licensee who took immediate and appropriate corrective actions.
The inspector discussed these issues with members of the plant staff and accepted the corrective actions which were verified by a tour later the same day.
These items of noncompliance are considered closed and no response is necessary.
3.
~Securit During tours and periods of observation, the inspector verified licensee compliance with security requirements.
Observations in-cluded the following:
a.
Vital area doors, protected area doors, and isolation zones.
b.
Security organization.
c.
Identification, Badging and Authorization.
d.
Search.
e.
Escort.
f.
Communications.
No items of noncompliance or deviations were identified.
4.
Thermal Power Evaluation The inspector reviewed the results of the licensee's Core Thermal Power Evaluation for Unit 1 which were obtained on July 31, 1979, while at 96/ power and verified the technical adequacy of the evaluations and results and that the frequency of evaluations was as prescribed 'by the Technical Specifications.
No items of noncompliance or deviations were identified.
5.
Refuelin Activities.
Unit 2 was shutdown October 19, 1979, for a refueling and maintenance outage.
The inspector verified that prior to the handling&f fuel in
- 7
the core, all surveillance testing required by Technical Specifications and procedures had been completed; that during the refueling the per-iodic testing of related equipment was performed as required; observed several hours of fuel handling operations (removal, inspection and insertion)
and verified the activities were in accordance ~h require-ments.
The inspector also verified that containment integrity was maintained; that good housekeeping was maintained in the refueling area; and that staffing during core alterations was in accordance with Technical Specifications and approved procedures.
6.
No items of noncompliance or deviations were identified.
Radiation Protection-0 erations During tours and observation periods, the inspector randomly examined many of the radiation protection instruments in use and verified operability and currency of calibration.
The inspector verified that current RWP's were issued in accordance with licensee procedures and that work conducted under the RWP's was as required; and that high radiation. area posting and control and
CFR 19 posting requirements were met.
No items of noncompliance or deviations were identified.
7.
Procurement The inspector conducted a tour of the licensee's storage areas and verified that safety related material and spare parts received onsite had been inspected by qualified personnel, that storage and packaging requirements had been defined and met, that identification and trace-ability were adequate, and that related activities were in accordance with procedures.
The inspector reviewed the findings and recommenda-tions of a recent internal QA audit of procurement activities and procedures.
No items of noncompliance or deviations were identified.
8.
Review and Followu on Iicensee Event Re orts (LER's)
Through direct observations, discussions with licensee personnel, and review of records, the following Licensee Event Reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Specificatioions.
These items are considered closed:
Unit
79"04/03L-0 79-07/03L-0 79-28/03L-0 79-28/03L-0
79-16/03L-0 79-17/031-0 79-18/03L"0 79-19/03L-0 79-20/03L-0 79-21/031-0 79-22/03I,-O 79-22/03X-0 79-23/031-0 79"24/03L-0 79-25/031-0 79-26/03L-0 79-27/03L-0 79-06/03L-0 79-09/03L-0 79-10/031-0 79-11/03L-0 79-12/03L-0 79-20/031-0 79-21/03L-0 79-22/03L-0 79"23/03L-0 79-24/03L-0 79-25/03L-0 Local Officials Meetin Unit 2 79-30/03L-0 79-30/03X-0 79-31/03L-0 79-3R/03L-0 79-3P/03L-0 79-35/03L-0 79-43/031-0 79-44/03L-0 79-45/03L-0 79-46/03L-0 79-47/03L-0 79-48/03L-0 79-49/03I,-O 79-14/03L-0 79-16/03L-0 79-17/03L-0 79-18/03L-0 79-19/01T-0 79-27/03L-0 79-28/03L-0 79-29/03L-0 79-30/03L-0 79-33/03L-0 79-35/03L-0 A meeting was conducted by NRC in the Berrien County Courthouse Board Room on November 29, 1979, to introduce local officials to the D. C.
Cook Plant Resident Inspector, Mr. Robert Masse, and to acquaint these officials with the mission of NRC and the Resident Inspection Program, discuss lines of communication, status of the D. C.
Cook Plant and related community concerns.
Mr. Duane Boyd, Section Chief of Reactor ProjectsSection III of the Region III Office presided over the meeting.
Local officials included representatives from Berrien County, Bridgman, Stevensville, Lake Township and Lincoln Township.
The meeting received token media attention.
Exit Inter'views The inspector met with licensee representatives (denoted in Para-graph 1) at various times during the reporting period.
The scope and findings of the inspection were discusse ~