IR 05000285/1981013
| ML20009G608 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/12/1981 |
| From: | Hunnicutt D, Kelley D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20009G599 | List: |
| References | |
| 50-285-81-13, NUDOCS 8108040472 | |
| Download: ML20009G608 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report 50-285/81-13 Docket 50-285 License DPR-40 Licensee:
Omaha Public Power District 1623 Harney Street Omana, Nebraska 68102
Facility Name:
Fort Calhoun Station - Unit 1 Inspection at:
Fort Calhoun Station, Blair, Nebraska Inspection conducted:
May 1 - 31, 1981 Inspector:,1 hi' _
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D. L. Vellsy, Senior Resident Reactor Inspector
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Approved by:
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D. M. Hunnicutt, Chief, Reactor Project Section 2
' Date Inspection Summary Inspection conducted during period of May 1-31, 1981 (Report 50-285/81-13)
Areas Inspected:
Routine, announced inspection including (1) Operational safety verification; (2) Surveillance testing; (3) Follow-up on Coen Items; (4) Venting and Purging of Containment During Operation; (5) Radioactive Waste; and (6) Independent Measurement of Reactor Coolant System Leak Rate.
The inspec-tion involved 100 inspector-hours on site by one NRC inspector.
Results:
Within the six areas inspected, no violations or deviations were identified.
8108040472 810612 PDR ADOCK 05000285 G
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DETAILS 1.
Persons Contacted
- S. C. Stevens, Manager, Fort Calhoun Station
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W. G. Gates, Supervisor, Operations G. R. Peterson, Supervisor, Maintenance
- R. L. Andrews, Section Manager, Operations
- W. C. Jones, Division Manager, Products Operations
- 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.
0 erational Safety Verification 2.
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 OperaH ons (LC0'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.
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(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 deter-mina as a result of these discussions tnat for the plant status these alarms were normal and the operating staff is cognizant of the cause for the alarms.
b.
Inspection Activities Performed on a Weekly Basis (1) The operability ci selected Emergency Safeguards Features (ESF)
systems was ykrified by noting valve positions, breaker positions, instrumentation and the general condition of major systems com-ponents.
In addition, the NRC inspector performed a complete wa R down of the following systems using the licensee's approved valve line up sheets:
Auxiliary Feedwater System Containment Spray System (2) The licensee's equipment control was reviewed for proper imple-mentation by performing the following inspection activities:
(a) Review of maintenance order log and tag-out log to deter-mine the licensee's compliance with LCO's and Technical Specifications action statements.
(b) Verification of " return to operable status of selected 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, plcnt conditions, security, safety housekeeping.
Observations included the following:
(a) General plant and equipment condition.
(b) Fire hazards.
(c) Control of combustible material.
(d) Fire watch postings and presence of fire watches when required.
(e) Physical security.
The inspettor verified thet the security plan is being impie-mented by observing thct:
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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 Barrit :; 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 identifice-
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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.
3.
Surveillance Observations a.
The inspector observed portions of the following surveillance tests:
SI-ISI-CVCV-3, F.1, " Chemical and Volume Control Pump
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Inservice Testing, F.1 CVCS Pump Test," R2, February 5, 1981.
ST-FW-3, F.2, " Auto Initiation of Auxiliary Feed Water,"
R2, April 20, 1981.
b.
The inspector determined through personal observation and records where appropriate that:
(1) Approved procedures were used.
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L (2) Test instrumentation was calibrated.
(3) Limiting Conditions for Operation were met when the system being tested was removed from service.
(4) The test data was recorded accurately and completely.
Selected test results were independently verified by the inspector.
(5) The surveillance test documentation was properly reviewed and test discrepancies were rectifie.
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(6) Test results met Technical Specification requirements.
(7) The test was done by qualified personnel.
No violations or deviations were identified.
4.
Venting and Purging of Conteinment During Operation The inspector reviewed the licensee's method of compliance with Action Plan Item Number II.E.4.2.6, of the Preliminary Clarification of TMI Action Plan Requirements. This item deals with venting and purging of the containment during power operation.
The specific concern is the closing of the large butterfly valves in these systems under LOCA con-ditions.
To meet the requirement for these valves, the licensee has elected to close the valves, with the power disconnected, and tag them with "Do Not Operate" tags that state the valves are not to bt operated when the Primary System Temperature is above 210 degrees Fahrenheit.
The position is verified once each eight hours using the shift turnover sheet.
The containment is normally vented using a 2-inch containment pressure relief line.
These provisions were verified by the inspector.
No violations or deviations were identified.
5.
Radioactive Waste During this inspection period radioactive waste shipment No. 81-08, was made by the licensee to Barnwell, South Carolina.
This shipment consisted of 126 cubic feet of dewatered resin, 20 reactor coolant pump studs and 400 pounds of dry insulation.
Total activity of the shipment was 76 curies.
The inspector reviewed the complete records, which included procedures, radiation and contamination surveys and bills of lading to verify that:
Department of Transportation Regulation 49 CFR 173 was followed.
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Procedures were followed and release approvals were cbtained.
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Required samples and analysis were performed.
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Personnel protection was applicable to the tasks performed.
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Proper barriers and shielding were errected and maintained.
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Proper labeling, surveys and records for shipment were accomplished.
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No violations or deviations were identified.
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6.
Followup on Open Items (8003-02, 8003-03)
During inspection 80-03, the inspectors identified open items 8003-02 and 8003-03.
These two items are related and deel with review of surveillance
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licensee has revised Procedure G-23, Surveillance Test Prograr tests.
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to clarib and specify the method and responsibility for surveillance test review.
The inspector has no further questions regarding these items.
These items are considered closed.
No violations or deviations were identified.
7.
Independent Measurement of Reactor Coolant System Leak Rate (RCSLR)
The inspector independently verified that the RCSLR for the Reactor Coolant System (RCS) was within the Limiting Conditions for Operation (LCO) and that the licensee's calculation technique for determining the RCSLR was adequate.
The licensee's calculation technique and the inspector's independent results were compared.
The licensee's identified and unidentified RCSLRs were:
(1) Total Leakage = 0.175 gallons per minute (gpm); (2) Known Leakage = 0.073 gpm; and (3) Unknown Leakage = 0.102 gpm.
The results of the inspector's independent measurements were:
(1) Total Leakage =
0.206 gpm; (2) Known Leakage = 0.073 gpm; and (3) Unknown Leakage = 0.133 gpm.
The RCSLR difference between the licensee's calculated total leakage and the inseector's independent calculations was 0.031 gpm.
This difference is.<itnin the difference in values normally expected and was less than 0.2
gpm; therefore, the inspector determined that the RCSLR was within the
Technical Specification limits and the difference between the licensee's and the inspector's results was acceptable.
No violations or deviations were identified.
8.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
on June 2, 1981, to discuss the scope and findings of this inspection.
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