IR 05000285/1982001
| ML20042A326 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/24/1982 |
| From: | Hunnicutt D, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20042A319 | List: |
| References | |
| 50-285-82-01, 50-285-82-1, IEB-80-11, NUDOCS 8203230328 | |
| Download: ML20042A326 (5) | |
Text
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ __-_____
'
.
APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report:
50-285/82-01 License: DPR-40 Docket:
50-285 Licensee: Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Facility Name:
Fort Calhoun Station, Unit 1 Inspection At:
Fort Calhoun Station, Blair, Nebraska Inspection Conducted: January 1-31, 1982 Inspector:
b (lmrdN d/16/PA I
L. A. Yandell, Senior Resident Reactor Inspector Dhte '
Approved By:
h/ ) toi<S o2If9/8f2L D. M. Hunnicutt, Chief, Reactor Projects IIate 7
~
Section 2 Inspection Summary Inspection conducted during period of January 1-31, 1982 (Report 50-285/82-01)
Areas Inspected:
Routine, announced inspection including (1) Operational Safety Verification; (2) Surveillance Testing; (3) Maintenance; (4) Plant Status; and (5) Follow up on IE Bulletins. The inspection involved 96 inspector-hours by one NRC in-spector.
Results:
Within the five areas inspected, no violations or deviations were identified.
i
,
9203230328 B20305 PDRADOCK05000g
,
G
-
-
- - - -
-
.,
.
j-2-DETAILS
,
1.
Persons Contacted
- W. C. Jones, Division Manager, Production Operations
- R. L. Andrews, Section Manager, Operations
- T. L. Patterson, Licensing Administrator
- J. K. Gasper, Manager, Reactor and Computer Technical Services
- S. C. Stevens, Manager, Fort Calhoun Station W. G. Gates, Supervisor, Operations G. R. Peterson, Supervisor, Maintenance B. J. Hickle, Supervisor, Chemistry and Radiation Protection
- Denotes those attending exit interview.
The inspector also talked with and interviewed other licensee employees during the inspection. These employees included licensed and unlicensed operators, craftsmen, engineers, and office personnel.
2.
Operational Safety Verification
The inspector performed certain activities as described below to ascer-tain that the facility is being maintained safely and in conformance with regulatory requirements, and that the licensee's management control system is effective.
a.
The inspector made several control room observations to verify:
(1) licensee adherence to selected LCOs, (2) operator adherence to approved procedures, and (3) proper control room and shift manning.
The inspector reviewed selected logs and records to verify compliance with regulatory requirements. The licensee's equipment control was reviewed for proper implementation by:
(1) reviewing the maintenance order and tag-out logs, and (2) verification of " return to operable status of selected safety-related components and systems." The inspector observed several shift turnovers and reviewed several shift turnover sheets.
!
b.
The inspector toured the plant at various times during the inspection to determine and/or verify equipment conditions, plant conditions,
'
security, safety and general housekeeping.
These observations in-cluded the following:
(1) General plant and equipment condition, (2) Fire hazards, (3) Control of combustible material, (4) Presence of fire watches when required, and (5) Physical security.
)
,
-
- -,
,,.
,
-_ _ ___-
_
.-_r
'
.
-3-During the plant tour of January 24, 1982, the inspector reviewed the Auxiliary Building RWP log and noted that two men had failed to sign out under RWP 14 for January 22, 1982. The inspector considered this an isolated instance and discussed with the licensee their follow-up system for closing out this record.
The inspector reviewed this item with the licensee at the exit interview, and indicated that this would be a matter of special attention in the coming months to determine if a weakness exists in the program, c.
The inspector verified the operability of the Containment Spray System
-
by performing a walk-down of the accessible portions of the system in accordance with checklist 01-CS-1-CL-A.
No violations or deviations were identified.
3.
Maintenance Observations a.
The inspector observed work being performed on FC-79-190C, Installation of Steam Line Radiation Monitor.
Personnel were welding brackets for tubing runs, and the inspector verified that the workers had an approved Flame Cutting and Welding Permit (FC-18), with a fire watch properly posted.
i b.
MO 13662, Determine If The Vent Header Is Leaking. This and other re-lated maintenance orders were written to investigate the cause for high activity in the Auxiliary Building. On January 14, 1982, about 11:40 a.m., an alarm on RM 061 caused VIAS to o: cur. The plant staff went
,
l to their emergency procedures, verified that it was a valid reading, l
and commenced drawing local air samples in and around the plant. As a
'
precaution, the Auxiliary Building was evacuated except for those in full face masks.
Valve WD 108 was closed, isolating the Waste Holdup Tanks from the Vent Header (refer to drawing M-98, Section IB). This caused activity levels to stop increasing, and once local sampling was completed, ventilation was restored to reduce levels in the Auxiliary Building in a controlled manner.
During the next week, the licensee systematically tested the vent header with Nitrogen Gas, Freon, and finally a water leak check to determine the source of leakage. The inspector attended some of the planning sessions for these evolutions, and witnessed portions of the various leak checks. A leak was identified at the relief on the top of the Component Cooling Water Surge Tank (AC-341), where a plug was missing.
The plug was replaced, and the vent header was restored to normal line-up with no additional activity problems. The plant staff is continuing their investigation of the matter, as a question still remains of I
whether this was the source of the activity. The licensee intands to issue a complete report on the matter in the near future.
'
,
!
!
-
--
.
.
-4-Apart from the investigation pertaining to the missing plug and the activity release, the inspector expressed concern that this valve had been worked on in the past and left in the situation just described.
The inspector considers this a potential violation because of a possi-ble breakdown in the licensee's program in the maintenance or QC area.
The licensee had already initiated an investigation of this issue, and this will be carried as an unresolved item pending further infor-mation from the licensee.
(8201-01)
c.
M0 13624, HCV 1040 Leaks Through. The inspector witnessed the re-adjustment of the valve stroke, and verified that tagging was properly done. This was followed up a week later with MO 13689 with the vendor technical representative on site. The inspector witnessed disassembly of the valve, where it was determined by the technical representative that a missing bushing was preventing the valve operator from genera-ting full power. Spare parts were available and the valve was re-assembled that afternoon.
No violations or deviations were identified.
4.
Surveillance Observations a.
ST-ICI-CC-3, Component Cooling Water Pump Inservice Testing, Section F.1, for pump AC-3A. The inspector witnessed the taking of data in the control room and the flow calculations being performed. The in-spector verified that the current test procedure was used and that it was performed by qualified personnel.
b.
ST-RA-1, Reactivity Anomalies, Section F.1.
The inspector witnessed the performance of this weekly reactivity balance determination. The current test procedure was used, and the work was performed by a trainee under the direct supervision of a qualified person.
c.
ST-CEA-1, Control Element Assemblies, Section F.5.
The inspector wit-nessed the recording of data and verified that a Computer Programmer was present as required by the procedure. The current test procedure was used, and the work was performed by qualified personnel.
d.
The inspector also reviewed ST-CONT-2, Containment Local Leak Detection Test, Type B, Section F.5, with regard to the leak check of the elec-trical penetrations.
No violations or deviations were identified.
5.
Plant Operations
The plant has been operating at full power during this reporting period.
An amendment to the Fort Calhoun Station Environmental Technical Speci-fications was issued to delete pages 1.1-1 and 1.1-2, and give them re-lief from the limit of 35 degrees temperature rise across the condenser.
t
- -
,
-
..
-5-The inspector attended a portion of the Reactor Effluent Technical Speci-fication meeting on January 26 and 27,1982, with OPPD, EG&G, and NRC representatives.
6.
Follow-up on IE Bulletins The licensee informed the inspector that the seven masonry walls identified in their letter of January 4,1982, have been completed in accordance with their response to IE Bulletin 80-11.
7.
Exit Interview The inspector met periodically with plant personnel to discuss the scope and findings of the inspection, and on January 29, 1982, held a formal exit interview with licensee representatives.