IR 05000285/1981023
| ML20031C925 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/16/1981 |
| From: | Hunnicutt D, Kelley D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20031C910 | List: |
| References | |
| 50-285-81-23, NUDOCS 8110090133 | |
| Download: ML20031C925 (5) | |
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m U. S. NUCLEAR REGULATORY COMISSION
0FFICE OF INSPECTION AND ENFORCEMENT
REGION IV
i Report 50-285/81-23 Docket 50-285 License DPR-40 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
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Inspection conducted:
August 1-31, 1981
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Inspector:
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D. L. Kelley, Senior Resident ~ Reactor Inspector Date Approved by:
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D. M. Hunnicutt, Chief, Reactor Project Section 2 Date
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Inspection Summary Inspection Conducted Dur_ing Period of August 1-31, 1981 (Report 50-285/81-23
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Areas Inspected:
Routine, announced inspection including (1) Operational Safety Inspection; (2) Surveillance Testing; (3) Maintenance; (4) Plant modifications; (5)
Generic Letter Follow-up; and (6) Plant Status.
The inspection involved 80 inspection hours by one NRC inspector.
Results: Within the six areas inspected no violations or deviations were i
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DETAILS 1.
Persons Contacted
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- S. C. Stevens, Manager, Fort Calhoun Station l
W. G. Gates, Supervisor, Operations
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l G.' R. Peterson, Supervisor, Maintenance J. Fleuhr, Reactor Engineer l
L. R. Kloke, Construction QA The inspector also talked with and interviewed other licensee employees
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during the inspection.
These employees included licensed and unlicensed operators, craftsmen, engineers and office personnel.
2.
Operational Safety Verification
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The inspector performed certain activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements and that the licensee's management control system is effectively dis-charging its responsibilities for continued safe operation.
The inspec-tor's activities and findings in this regard are described in the following paragraphs:
a.
Inspection Activities Performed Several Times Per Week (1) ' Control room observations were made which included the following items:
(a) Licensee adherence to selected Limiting Conditions for Operations (LCO's).
(b) Observation of instrument and recorded traces for abnor-malities.
(c) Verification of operator adherence to approved procedures.
(d) Verification of control room and shift manning.
(2) Review of selected logs and records to obtain information on plant operations, trends, compliance with regulatory require-ments, and assess the effectiveness of communication provided by these logs and records.
(3) During the course of control room observations the inspector noted the alarm status of the control room annunciators.
The alarm status was discussed with several licensed operators to l
determine as a result of these discussions that for the plant status these alarms were normal and the operating staff is cognizant of the cause for the alarms.
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b.
Inspection Activities Performed on a Weekly Basis
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l (1) 'The operability of selected Emergency Safeguards Features (ESF)
systems was verified by noting valve positions, breaker positions, instrumentation and the general condition of major systems com-ponents.
In addition, the NRC inspector performed a complete walk down of the Containment Spray System using the licensee's approved valve line up sheets.
(2) The licensee's equipment control was reviewed for proper imple-mentation by performing the following inspection activities:
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(a) Review of maintenance order log and tag-out log to deter-mine the licensee's compliance with LCO's and Technical LS Specifications action statements.
(b) Verification of " return to operable status of selected i
safety-related components and systems."
(3) The inspector toured accessible areas of the plant at various times during the inspection to determine and/or verify equip-ment conditions, plant conditions, security, safety housekeeping.
Observations included the following:
(a) General plant and equipment condition.
(b) Fire hazards.
l (c) Control of combustible material.
(d) Fire watch postings and presence of fire watches when required.
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l (e) Physical security.
The inspector verified that the security plan is being imple-
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mented by observing that:
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The Security organization is properly manned and security
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personnel are capable of performing their assigned tasks.
Protected Area Barriers are not degraded.
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Isolation Zones are clear.
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Vehicles are properly authorized, searched, and escorted
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or controlled within the protected area.
Persons'within the protected area display photo identifica-
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tion badges and persons requiring escort are properly escorted.
Persons and packages are checked prior to entry into the
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protected area.
The inspector observed several shift turnovers and reviewed several shift turnover sheets.
No violations or deviations were identified.
The inspector reviewed outstanding job orders to determine that the licensee is giving priority to safety-related maintenance and that a backlog is not developing on a given system which might affect its operability.
The inspector also determined that the proper approvals were obtained for job orders,'hich appear to constitute design changes.
No violations or deviations were identified.
4.
Plant Modification The licensee has been installing a Steam Generator Blowdown Processing System.
Part of the modification included constructing concrete shield walls and overheads around the tanks and pumps.
The walls and overheads required tie-in to two existing Category I walls.
The new walls are defined as " Limited Critical Quality Element (CQE)." By this definition it is meant that even though the new walls were not required to be Category I, their construction (especiaMy at the +ie in points) would not degrade the existing structure.
The inspector has periodically observed the construction during the building process.
In addition, the inspector reviewed the concrete testing done by tbraska Testing Laboratory, Inc.
These tests included:
Grout tests
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Pull out tests on grouted rebar
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Proof load tests
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Concrete Cylinder break tests (wall and slab - 14 day and 28 day)
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Rebar specifications.
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No violations or deviations were identifie. _ _ _ _
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5.
Follow-p on Generic Letter Actions The inspector reviewed the licensee's response to Generic Letter (81-01),
" Qualification of Inspection, Examination, and Testing and Audit Personnel,"
and Generic Letter (81-04), " Emergency Procedures and Training for Station Blackout Events."
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The inspector reviewed the licensee's response to determine that:
The time requirements for the responses had been met.
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The response addressed the specific item requested.
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That procedures and training programs were revised where
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required.
No violations or deviations were identified.
6.
Plant Status Fort Calhoun Station is scheduled to be shut down on September 18, 1981, for the 1981 refueling outage.
The plant boron concentration had been reduced to 10-15 ppm during the first part of the week of August 13, 1981. On August 15, 1981, the reactor power was reduced to 90%.
On August 18, 1981, with the reactor power at 90% and Tc at 5410 F, the licensee began lowering Tc while holding reactor power at 90%.
This program will remain in effect until Tc reaches 5200F.
When the temperature reaches 5200F, the reactor power will be allowed to decrease while holding Tc at 5200F.
7.
Exit Interview The inspector met with S. C. Stevens, Manager, Fort Calhoun Station on August 27, 1981, to discuss the scope and findings of this inspection period.
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