IR 05000316/1978033
| ML17317A850 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/15/1978 |
| From: | Little W, Masse R, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17317A848 | List: |
| References | |
| 50-316-78-33, NUDOCS 7901080226 | |
| Download: ML17317A850 (5) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-316/78-33 Docket No. 50-316 License No.
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, Unit 2 Inspection At:
Donald C.
Cook Site, Bridgman, MI Inspection Conducted:
November 1-3, 1978 Inspectors:
.
E.
Masse
+.~M~%i~
J.
F. Streeter Nuclear Support Section
Ins ection Summar Ins ection on November 1-3 1978 (Report No. 50-316/78-33)
Areas Ins ected:
Routine, unannounced inspection of compliance with limiting conditions for operation; implementation of surveillance test program; and procedure change control.
The inspection involved 45.5 inspector-hours onsite by two NRC inspectors.
Results:
No items of noncompliance or deviations were identifie DETAILS 1.
Persons Contacted
- D. Shaller, Plant Manager
- B. Svensson, Assistant Plant Manager
- R. Keith, Operations Superintendent
- R. Dudding, Maintenance Superintendent
- E. Smarrella, Technical Superintendent
- C. Shay, Resident Advisor
- R. Lease, Production Supervisor (Operations)
- J. Stietzel, Quality Assurance Supervisor
+E. Abshagen, Quality Assurance Auditor H. Chadwell, Production Supervisor D. Vizner, Maintenance Quality Control Coordinator J. Rischling, Quality Control Coordinator T. Beilman, Qulaity Control Coordinator J. Colledge, Unit Supervisor R. Hall, Assistant Shift Operating Engineer
- Denotes those attending the exit interview.
2.
Com liance With Limitin Conditions For 0 eration The inspectors reviewed selected records and/or made independent observations to verify the licensee was complying with the below listed limiting conditions for operation.
(For those asterisked items, the inspectors independently verified compliance during a Control Room tour on November 3, 1978.)
3.1.1.1 3.1.1.2
- 3.1.3.1
~F 1.3.2
- 3.1.3.5
- 3.1.3.6
- 3.2.1 3.2.5 3.3.2.1
- 3.4.4
~3.4.9.2.c
- 3.5.1.b
- 3.5.l.d
- 3.5.4.1.c 0,
Shutdown Margin (RCS temperature 7 200 )
{RCS temperature
< 200 )
Rod Position (Indicated vs Demand)
Rod Position Indication Shutdown Rod Position Rod Insertion Limits Axial Flux Difference DNB Parameters ESFAS Instrumentation Pressurizer Level Pressure Spray Differential Temperature Accumulator Level Accumulator Pressure BIT Temperature
- 3.5.5 RWST Level
- 3.6.1.4 Containment Internal Pressure
- 3.7.1.3 Condensate Storage Tank Level No items of noncompliance or deviations were identified.
3.
Im lementation od Surveillance Test Pro ram The inspectors reviewed selected test job sheet records to verify the licensee was implementing the below listed surveillance requirements of the Technical Specifications and that discrepancies had been cor-rected and reported in accordance with the Technical Specifications:
4.7.5.1 4.3.1.1.1 4.4.6.2 4.5.2.a 4.6.5.2 4.6.1.5.1 4.6.5.4.a 4.6.5.1 4.7.7.1.a 4.5.4.2.b 4.6.5.3 4.6.2.1.a 4.6.1.3 4.7.4.1.a 4,1.2.l.a 4.1,2.1.b 4.7.3.1.a 4.6.4.2.a 4.5.4.1.b 4.5.l.b 4.5.2.8.a.l Control Room Air Temperature RCS Flow, Pressurizer Pressure and Level, Power Range Monitors, RCS T, Stem Flow, Steam Generator Levels, Radiation Monitoring Channels, and RCS Overpower and Overtemperature T.
RCS Operational Leakage ECCS Valve Position Ice Bed Temperature Containment Upper Compartment Air Temperature Ice Bed Inlet Door Monitoring System Ice Condenser Hydraulic Snubbers Heat Tracing Ice Condenser Doors Containment Spray System Valves Containment Air Lock Essential Service Water System Valves Boric Acid Flow Path Temperature Boric Acid Flow Path Valves Component Cooling Water System Valves Hydrogen Recombiner Boron Injection Tank Boran Concentration Accumulator Boron Concentration Boric Acid Storage Tank Boron Concentration No items of noncompliance or deviations were identified; however, the inspector had the following comments and unresolved item.
a
~
During the initial surveillance of hydraulic snubbers (con-ducted during the period July 23-August 8, 1978, as required by TS 4.7.7.1.a)
the nut on snubber S/N GRC-S624 had become loose causing the snubber to rotate such that the reservoir was below the cylinder.
The misoriented snubber was discovered while in Mode 5 and was not reported as Reportable Occurrenc The licensee reviewed the reportability of this item and informed the inspectors that it should have been and will be reported as a Reportable Occurrence.
The licensee also stated that when he discovers items to be inoperable when he is in a mode which does not require operability of the items and he can not reasonably establish that the items became inoperable after entering that mode, he evaluates the reportability of the items assuming the items were inoperable while in a mode for which their operability was required.
b.
The inspectors were unable to determine from the information available if TS 4.5.4.2.a was being implemented.
TS 4.5.4.2.a requires that each heat tracing channel for the boron injection flow path be energized each 31 days.
This matter is an unresolved item pending the licensee providing documentation to verify the implementation of TS 4.5.4.2.a.
c ~
There was no documentation in the test procedures that supervisory personnel were reviewing the results of the 24-hour surveillance of boron injection flow path temperatures.
The licensee stated the procedure would be revised to document the reviews.
d.
The inspectors noted that a inadvertent safety injection which occurred on August 4, 1978, had not yet been reported as required by TS 6.9.2.a.
The report was being prepared and was expected to be, submitted to RIII within a week, The licensee stated he would review the adequacy of his administrative controls in this area.
The inspectors had no other questions/comments concerning the implementation of the surveillance test program.
4.
Procedure Chan e Control The inspectors reviewed the below listed procedures, which were issued during the power ascension test program, to determine if they were reviewed and approved in accordance with the provision of TS 6.8.2 and if the licensee's document control procedures resulted in the most current revisions being available to operators in the Control Room:
II 2-OHP 4021.001.001,
"Plant Heatup From Cold Shutdown to Hot Standby, Revision 2, Dune 6, 1978.
ff 12-OHP 4021.001.012,
"Determination of Reactor Shutdown Margin, Revision 6, March 7, 197 OHP 4021.002.007,
"Pressurizer Pressure and Spray Control Systems Operation," Revision 1, August 1, 1978.
2-OHP 4022.001.001,
"Emergency Shutdown Including Reactor Trip,"
Revision 1,
May 3, 1978.
II 2-OHP 4 02 2. 008. 004, "Initiation of ECC Recirculation Phase with E
RHR Pump Out-of-S ervice, " Revision 1, July 1 1,
19 7 8.
2-OHP 4 024. 2 05. 00 1 through
. 050, "Annunciator No.
5 Response-Con-ta inmen t Spray, "
Revision 1, June 2 1, l9 7 8.
2-OHP 4 030. S TP. 002, "Boron Injection Flow Path and Boric Acid Trans fer Pump Operability Test, " Revision 1, June 5,
19 7 8.
2-OHP 4 030. S TP. 0 1 0, "Containment Isolation, " Revision 1, July 5,
1 9 7 8.
2-OHP 4 030. STP. 02 7, "Emergency D/G Operabil ity Test, " Revis ion 1,
June 2 1,
1 9 7 8.
2-OHP 4 0 30. STP. 1 20, "Fire Protection Water, " Revision 3,
June 2 1, l9 7 8.
No items of noncompliance or deviations were iden tified.
5.
Unresolved It ems Unresolved items are matters about which more information is required in order to ascer ta in whe ther they are acceptable items,
items of noncompliance, or deviations
.
An unresolved item disclosed dur ing the inspection is discussed in Paragraph 3, b.
6.
Exit Interv iew The inspectors me t with licensee repres en ta tives
{deno ted in P
h 1 ) at the conclusion of the inspection on November
'3,
aragrap of the 1978.
The inspectors summarized the purpose and the scope o
t e inspection and the findings.