IR 05000316/1981008
| ML17319A902 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/21/1981 |
| From: | Jackiw I, Ring M, Swanson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17319A901 | List: |
| References | |
| 50-316-81-08, 50-316-81-8, NUDOCS 8106020180 | |
| Download: ML17319A902 (5) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-316/81-08 Docket No. 50-316 License No. DPR-74 Licensee:
American Electric Power Service Corporation Indiana S Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:
D.
C.
Cook Site, Bridgman, MI Inspection Conducted:
March 16-18, and April 6-11, 1981 Inspectors; M. A.
ing Approved By:
I. Jackiw, Acting Chief, g~
Test Program Section Ins ection Summar Ins ection on March 16-18 and A ril 6-11 1981 (Re ort No. 50-316/81-08)
refueling activities, refueling surveillance and maintenance activities during the refueling outage on Unit 2.
The inspection involved a total of 76 inspector-hours onsite by one NRC inspector including 10 inspector-hours on offshifts.
Results:
In the four areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS Persons Contacted
- D. Shaller, Plant Manager
'E. Townley, Assistant Plant Manager B. Svensson, Assistant Plant Manager
- J. Stietzel, Quality Assurance Supervisor H. Chadwell, Outage Planning Coordinator C. Murphy, Production Supervisor J. Allard, Maintenance Supervisor A. Blind, Performance Engineering Supervisor D. Sudkamp, Performance Engineer C. Ross, Nuclear Engineering Supervisor H. Bolinger, In-Service Inspection Coordinator Additional plant technical and administrative personnel were contacted during the course of the inspection by the inspector.
-"Denotes those attending the exit interview.
Pre aration for Refuelin (Unit 2)
The inspector verified that technically adequate procedures for Unit 2 cycle II-IIIwere approved for fuel handling, transfers, core verification~
inspection of fuel to be reused and handling of other core internals.
These procedures were in a large part incorporated in the vendor Refueling Procedure FP-AMP-R2 which the inspector verified to have been reviewed and approved by the licensee in accordance with Technical Specifications.
The inspector verified that the licensee's
CFR 50.59 Safety Evaluation of the reload core showed that prior NRR review is not required.
The inspector also reviewed the licensee's program for overall outage control.
No items of noncompliance or deviations were identified.
Refuelin Ac'tivities The inspector verified that prior to the handling of fuel in the core, all surveillance testing required by the Technical Specifications and licensee's procedures had been completed.
The inspector verified that during the outage the periodic testing of refueling related equipment was being performed as required by Technical Specifications.
The inspector observed two shifts of fuel handling operations (removal, inspection, and insertion)
and verified the activities were performed in accordance with Technical Specifications and approved procedures.
In addition, the inspector observed activities within the upper contain-ment area while fuel handling operations were secured, and the reactor head was still removed in order to conduct sonic probe inspections of
" 2-
the vessel nozzles.
During this time, the inspector questioned the manner in which the precautions of Plant Manager's Instruction (PMSI)-068 section 8.0 and Refueling Procedure FP-AMP-R2 section 6.0E.1 on loose material control with an open reactor vessel were being observed.
is concern was discussed with licensee management who took prompt action in terms of internal memos and phone calls.
Subsequent observations on differing days and shifts showed that the precautions were being observed and that the licensee response appeared to be adequate.
No further action is required on this item.
The inspector also reviewed the qualifications of the refueling contractor personnel and verified that licensee staffing during refueling was in accordance with technical specifications and approved procedures.
No items of noncompliance or deviations were identified.
Surveillance - Refuelin The inspector observed the Diesel Generator Load Shedding and Performance (2THP 4030 STP 217A) surveillance testing on Unit 2 train A to verify that the tests were covered by properly approved procedures; that the procedures used were consistent with regulatory requirements, licensee commitments, and administrative controls; that test prerequisites were completed, special test equipment was calibrated and in service, and require d data was recorded for final review and analysis; that the d that qualifications of personnel conducting the test were adequate; an a
the test results were adequate.
No items of noncompliance or deviations were identified.
Maintenance Refuelin The inspector reviewed pressurizer safety valve replacement, reactor coolant pump seal inspections and main steam isolation valve disc guide replacement maintenance work items in order to ascertain whe her maintenance procedures included administrative approvals for removal and return of systems to service; hold points for inspection/audit and signo y
ff b QA or other licensee personnel; provisions for operationa'lities testing following maintenance; provisions for fire watch responsibi i ies (not required in items chosen);
review of material certifications; pro-visions for assuring LCO requirements were met during repair; provisions for housekeeping during and following maintenance; and responsibilities for reporting defects to management.
The inspector observed portions of the maintenance activities and verified the work was being accomplished in accordance with the following approved procedures.
a.
PMI-2090 Housekeeping/Plant Cleanliness b.
PMI-2220 Rework Clearance Permit System
"3"
'
c.
PMI-2110 Equipment Control - Clearance Permit System d.
PMI-2290 Job Orders e.
12MHP5021.002.003 Reactor Coolant Pump Seal Inspection
No items of noncompliance or deviations were identified.
6 " Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on April 10, 1981 and summarized the scope and findings of the inspection activities.
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