IR 05000409/1980013
| ML20002D669 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/12/1980 |
| From: | Boyd D, Branch M, Forney W, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20002D667 | List: |
| References | |
| 50-409-80-13, NUDOCS 8101210643 | |
| Download: ML20002D669 (7) | |
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U.S. NL' CLEAR REGULATORY CONIISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-409/80-13 Docket No. '0-409 License No. DPR-45
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Licensee:
Dairyland Power Cooperative 2615 East Avenue, South
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La Crosse, Wisconsin 54601 Facility Name: La Crosse Boiling Water Reactor Inspection At:
La Crosse Site, Genoa, WI
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Inspection Conducted: October 1-31, 1980 Inspectors:
W. L.
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F. W.
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a K. R. Ridgway
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D. C. Boyd
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Approved By:
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Projects Section 4 Inspection Summary
Inspection on October 1-31, 1980 (Report No. 50-409/80-13)
Areas Inspected:
Routine unannounced inspection of the licensee's opera-tional safety, surveillance, maintenance; followup action to IE Bulletins, IE Circulars, Plant Trips, and outstanding inspection items.
The inspection involved a total of 254 inspector-hours onsite by four NRC inspectors including 30 inspector-hours during off-shift hours.
Results: Of the seven items inspected, no items of noncompliance or deviations were noted in six areas; two items of noncompliance were found
in one area -(Use of unqualified guard as armed responder; failure of Shif t Supervisor to make required tours.)
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DETAILS 1.
Persons Contacted
- J.
Taylor, Assistant General Manager for Power
- R. Shimshak, Plant Superintendent G. Boyd, Operations Supervisor L. Goodman, Operations Supervisor
- P.
Shafer, Radiological Engineer
- L.
Krajewski, Health and Safety Supervisor H. Towsky, Quality Assurance Supervisor S. Rafferty, Reactor Engineer W. Angle, Process Engineer M. Paulrean, Shift Supervisor P. Gall:gher, Shift Supervisor W. Nowicki, Instrument and Electrical Engineer R. Brimer, Electrical Engineer G. Joseph, Security and Fire Protection Supervisor L. Kelly, Assistant Operations Supervisor D. Rybarik, Mechanical Engineer
- Denotes those present at exit interview.
In addition, the inspector observed and held discussions with other engineers, plant equipment operators, reactor operators, assistants and plant attendants.
2.
General a.
Mr. David L. Rybarik joined the LACBWR staf f as the Mechanical Engineer effective October 1, 1980.
Mr. Rybarik holds Associate Degrees in Mechanical Technology and Manufacturing Technology from Racine School of Technology and a Mechanical Engineer Degree from Milwaukee School of Engineering.
Mr. Rybarik worked for General Electric Company as a Site Engineer and Project Supervisor on Boiling Water Reactor construction and maintenance programs from March,1972, until employment by Dairyland Power Cooperative.
b.
During the month of October the plant experienced a reactor trip on October 4, 1980, from 85% power due to a high reactor water level. The reactor was taken critical at 2230 on October 4, and remained at power for the duration of the month, c.
TMI ACTION PLAN REQUIREMENTS FOR OPERATING REACTORS - TASK II.E.4.3.C (CONTAINMENT PURGE)
The licensee has reviewed the requirements of Task II.E.4.3.C, the standard review plan and the interim position of October 23, 1980. This review has also been accomplished previously under tFe Systematic Evaluation Program (SEP) and the interim position.
The licensee's position and evaluations have been provided by i-2-
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LACBWR correspondence LAC-6104 of February 2, 1979, LAC-6681 of December 7,1979, LAC-6815 of March 6,1980, and LAC-6982 of June 12, 1980. The licensee plans to replace the existing d'amper valve operator solenoid operated valves with environmentally qualified solenoid operated valves. Additionally, the licensee intends to replace the elastomeric seals on the valve operating cylinders with environmentally and seismically qualified seals.
The solenoid operated valve and gasket replacement is currently in the planning and procurement phase with no specific commitment by the licensee for the installation phase.
The licensee is also committed to establish a preventative maintenance program for the containment isolation and solenoid valves.
This is considered unresolved item 80-13-01.
d.
The resident inspectors had a concern that the licensee had not adequately mounted an air-condit oner installed in the window of the chemistry analysis laboratory as required by paragraph 5.2.1. A of the Modified Approved Security Plan (MASP).
The concern was brought to the attention of the Security Director who initiated action to have the air-conditioner mounted as required by the MASP.
The required action was completed and the resident inspector's no longer have a concern.
The resident inspectors had a concern that radiological problems e.
discussed in Report No. 50-409/80-11 are still occuring and are not being corrected in a timely fashion. Examples of the problems
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are as follows:
(1) Cigarette butts in radiological controlled areas.
(2) Poor radiological control work practices (spread and possible spread of loose surface contamination).
(3) Portable radiation detector on 701 did not have calibration sticker.
(4) Personnel contamination.
These problems have been presented to plant management and the resident inspectors will assure a timely correction of problems.
3.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of October, 1980. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified
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proper return to service of affected components. Tours of the reactor building and turbine building were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks,
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and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance.
The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.
The inspector observed plant housekeeping / cleanliness conditions and
. verified implementation of radiation protection controls. During the month of October,1980, the inspector walked down the accessible r
portions of the high pressure core spray and boron injection systems to verify operability. The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.
These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedures.
The inspectors monitored records of personnel entry into containment area and noted that the tours of equipment areas are not being con-
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ducted at the required frequency. Of the records reviewed, it was
noted that the shift technical advisor had made no backshift tours as
required by ACP 2.4 and the shift supervisors had made no shift tours
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as required by ACP 2.3.
This item is considered an item of noncompliance.
After a discussion with Security Supervision, the inspectors noted that on the midnight shift of October 22, 1980, an individual was I
allowed to perform the duties of search officer, monitor and security base guard after he had demonstrated his inability to meet the mini-mum firearm scores listed in Regulatory Guide 5.20.
The positions described above required the use of personnel who had demonstrated their ability to meet the minimum firearm score listed in Regulatory
' Guide 5.20.
It should be noted that the individual failed this qualification on October 21, 1980, during a requalification exam given two months prior to present qualifications running out to take advantage of good weather.
This item is an iter of noncompliance.
4.
Monthly Maintenance Observation i
Station maintenance activities of safety related systems and com-ponents listed below were observed / reviewed to ascertain that they
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were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specifications.
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The following items were considered during this review:
the limiting
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conditions for operation were met while components or systems were
removed from service; approvals were obtained prior to initiating the i
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wc k; activities were accomplished using approved procedures and were in:pected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; act.ivities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and, fire prevention controls were implemented.
Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performance.
The following maintenance activities were observed / reviewed:
Nuclear Instrumentation - Source Range Channel 1 Power Supply Repairs IB Emergency Diesel Generator Start Battery Replacement IB Reactor Feed Pump - Auto Controller Repairs Control Rod Drive (CRD) #7 - Primary Position 'ndication Replacement Off-Gas arid Component Cooling Water Monitor (CCW) - Power Supply Repairs Following completion of maintenance on the CRD #7; Off-Gas and CCW monitor, the inspector verified that these systems had been returned to service properly.
No items of noncompliance were noted.
5.
Monthly Surveillance Observation
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The inspector observed technical specifications required surveillance testing on the N-5 through N-9 Nuclear Instrument System, Channel #2 safety system and Channel #3 water level and verified that testing was performed in accordance with adequate procedures, that test instru-mentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affe-te,d components were accomplished, that test results conformed wi echnical specifications and procedure requirements and were revieweo personnel other than y
the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
The inspector also witnessed portions of the following test activities:
1A and IB high pressure service water diesel test, IA and IB emergency diesel generator test, fire system flush, demineralizer water system and component cooling water system in service inspection.
No items of noncompliance were notet..
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A.
IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presentation in the bulle-tin and the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written response.
IEB 80-19 Failure of Mercury Wetted Matrix Relays IEB 80-20 Failure of Westinghouse Type W-2 Spring Switches No items of noncompliance were noted.
7.
IE Circular Followup For the IE Circulars listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and that if the circular were applic-able to the facility, appropriate corrective actions were taken or were scheduled to be taken.
IEC 80-03 Protection from Toxic Gas Hazards IEC 80-10 Failure to Maintain Environmental Qualifications of Equipment IEC 80-14 Radioactive Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel IEC 80-15 Loss of Reactor Cooling Pump Cooling and Natural Circulation IEC 80-18 10 CFR 50.59 Safety Evaluations for Changes to Radioactive Waste Treatment Systems IEC 80-21 Regulation of Refueling Crews No items of noncompliance were noted.
8.
Plant Trips J
Following the plant trip on October 4, 1980. the inspector ascertained
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the status of the reactor and safety systems Sy observation of control room indicators and discussions with licensee personnel concerning plant parameters, emergency system status and reactor coolant chemistry.
The inspector verified the establishment of proper communications and reviewed the corrective actions taken by the licensee.
All systems responded as expected, and the plant was returned to operation on October 4, 1980.
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No items of noncompliance were noted.
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9.
Followup on Open Inspection Items (OII)
(Closed) 011 79-071/: The licensee has provided revised quality assur-ance program description to Director of Nuclear Reactor Regulation for review and acceptance (reference LAC-7107).
10.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. Unresolved items disclosed during the t
inspection are discussed in Paragraphs 2 and 3.
11.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of the inspection. The inspectors sumaarized the scope and findings of the inspection activities.
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- IE Inspection Report No. 50-409/79-02, Paragraph 12.a.
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