IR 05000285/1980020
| ML19353A134 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/17/1980 |
| From: | Hunnicutt D, Kelley D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19353A132 | List: |
| References | |
| 50-285-80-20, NUDOCS 8101070244 | |
| Download: ML19353A134 (7) | |
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U. S. NUCLEAR REGULATORY CLMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-285/80-20 Docket No. 50-285 License No. 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 Inspection Conducted:
October 1-31, 1980 Inspector i 3 'hl' j w d u W llfl7f$O
' v0. L. Kelley, Senior Resident Inspector Date/
l Approved by:
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////7/80 u av D. M. Hunnicutt, Chief, Reactor Projects Section No. 2 0' ate '
Inspection Summary Inspection Conducted During Period of October 1-31, 1980 (Report No. 50-285/80-20)
Areas Inspected:
Routine, announced inspection including operational safety verification, radioactive waste shipment, and followup on IE Headquarters Requests.
The inspection involved 96 inspector-hours on-site by one NRC inspector.
Results:
Within the three (3) areas inspected no items of noncompliance or deviations were identified.
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2 DETAILS 1.
- S. C. Stevens, Manager, Fort Calhoun Station W. G. Gates, Supervisor, Operations L. T. Kusek, Supervisor, Technical L. J. Dugger, Reactor Engineer B. Hickle, Plant Health Physicist J. L. Connolley, Supervisor, I&C and Electrical Field Maintenance
- W. C. Jones, Division Manager, Production Operations
- J. M. Gloshen, QA Engineer
- T. Patterson, Licensing Administrator
- 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.
Ooerational Safety Verification 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 discharging its responsibilities for continued safe operation.
The inspector's activities and findings in this regard are described in the following paragraphs:
a.
Inspection Activities Performad Several Times Per Week (1) Control room observations were made which included the following items:
(a)
Licensee Adherence to Selected Limiting Conditions for Operations (LC0's).
(b) Observation of Instrument and Recorder Traces for Abnormalities.
(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 requirements, and assess the effectiveness of communication provided by these logs and records.
b.
Inspection Activities Performed on a Weekly Basis (1) The operability of selected Emergency Safeguards Features (ESF)
systems was verified by noting valve positions, breaker positions,
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instrumentation and the general condition of major system components.
The systems selected for review during this inspection were:
(a) Auxiliary Feedwater System (b) Emergency Power - Diesel Generator Systems OG-1 (2) The licensee's equipment control was reviewed for proper implementa-tion by performing the following inspection activities:
(a) Review of maintenance order log and tag-out log to deter-mine the licensee's compliance with LC0'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, plant conditions, security, safety and house-keeping.
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 inspector verified that the security plan is being implemented by observing that:
The Security organization is properly manned and security personnel are capable of performing their assigned tasks.
l 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 or
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controlled within the protected area.
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l Persons within the protected area display photo identification
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I badges and persons requiring escort are properly escorted.
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Vital Area physical barriers are not degraded.
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Persons and packages are checked prior to entry into the
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protected area.
The inspector reviewed several shift turnover sheets and observed several shift changes.
(4) The inspector reviewed the Area Radiation Surveys for the period of October 1-20 1980.
In addition, the inspector made several tours of the Auxiliary Building to assess the general condition of equipment, contamination control measures, and take independent radiation readings of selected areas.
Also during these tours selected areas were inspected to verify the following:
Postings are as required by 10 CFR 20 and 19.
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RWP requirements are being followed and the requirements
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appear appropriate for the job or activity.
Licensee's procedures are being followed.
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Step-off pads are being properly maintained and contaminated
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clothing or debris are being properly collected and disposed of.
(5) Plant Review Committee The inspector observed the licensee's Plant Review Committee (PRC)
meeting on October 22, 1980.
The observation was made to ascer-tain the general method in which the licensee conducts these meetings and to specifically verify the following:
(a) The meeting had the required number of members to satisfy the requirement for a quorum.
(b) The necessary expertise for technical reviews was present.
l (c) l'ew and revised procedures were reviewed in accordance with l
Tichnical Specifications.
i (d) Other reports, incidents, and nonconformances were reviewed and acted upon in accordance with Technical Specifications.
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3.
Radioactive Waste l
Ouring this inspection period, radioactive waste shipment No. 80-45 yas made by the licensee to Barnwell, S.C.
This shipment consisted of 100ft of dewatered spent resin.
The inspector observed licensee activities in the i
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preparation and filling and dewatering of the resin line.
The inspector reviewed the completed records, which included procedures, radiation and contamination surveys and bills of lading to verify that:
Department of Transportation regulation 49 CFR 173 were followed.
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Procedures were followed and release approvals were obtained.
Require samples and analysis were performed.
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Personnel protection was applicable to the tasks performed.
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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4.
Followuo on IE Headquarter Inquiries a.
Inspection of TMI Task Action Plan Category "A" Reauirements At the request of IE Headquarters by memorandum dated October 24, 1980, the inspector was requested to confirm the items listed below.
The confirmation was accomplished by review of previous inspection reports, review of licensee records and procedures, discussion with licensee representatives and visual observations.
Inspected (Previot Inspection Rpt. No.,
TAP No.
Paragraph) or Confirmed Date Remarks I. A.1.1 1/1/80 Confirmed I. A.1. 2 1/1/80 Confirmed I.C.1 1/1/80 Confirmed I.C.2 1/1/80 Confirmed In use prior to 1/1/80
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I.C.3 1/1/80 Confirmed I.C.4 1/1/80 Confirmed II.B.1 Submitted 12/31/79 II.B.2 Submitted 12/31/79 In rev. due
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to change in source terms
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II.B.3 Minor mod. in place refueling outage.
Procedure OI-PAP-1 thru 9 II.D.1 Submitted 12/29/79; part of EPRI II.D.3 Installed 1980 Refueling outage Acoustical type II.E.1.2 Mod. & Control grade 1980 Refueling outage II.E.3.1 Mod. & Procedure EP-3 1980 Refueling outage II.E.4.1 Present design adequate-no licensee action Response 12/31/79 No recombiners at FCS - Licensee
action N/A II.E.4.2 Verified in followup IEB 79-068 (Report 79-07) also during 1980 Refuciing outage II.F.2 Installed 1980 refueling outage l
II.G.1 Modifications complete 1980 refueling i
outage III.A.1.2 Located prior to 1/1/80 Computer Operational 1980 Refueling outage III.A.1.2 Space provided prior to 1/1/80 III.D.1.1 Sent to NRR - June 1980 II.F.1 Monitor Delivered January 1980 l
III.D.3.3 Procedure OI-PAP-9 in effect Prior j
to 1/1/80 b.
Information on Solenoid Valve Failures At the request of IE Headquarters, the inspector obtained data on installation of Valcor solenoid valves and subsequent failures ex-perienced at Fort Calhoun St'.. ion.
The data gathered showed that as a result of corrective act',
required by IEB 79-01, the non-certified safety-related solenoid va...a were removed and replaced with Valcor solenoid valves.
Since installation of these Valcor solenoid valves,
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there have been four failures of the eleven Valcor solenoid valves that were installed.
This information has been transmitted to IE Headquarters.
c.
Waste Storage Modification At the Request of IE Headquarters, information on proposed modification of the licensee's waste storage capability was obtained by the inspector.
This information was transmitted to the Region IV c*fice cor information and transmission to IE Headquarters.
5.
Exit Interview Weekly mini exit interviews were held with S. C. Stevens, Manager, Fort Calhoun Station.
On October 24, 1980, a concluding exit interview for the month of October was held with licensee representatives (denoted in para-graph 1) to review the scope and findings of this inspection period.
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