IR 05000409/1981016
| ML20031F253 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/28/1981 |
| From: | Branch M, Forney W, Mcgregor L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20031F245 | List: |
| References | |
| 50-409-81-16, IEB-80-06, IEB-80-6, NUDOCS 8110190424 | |
| Download: ML20031F253 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/81-16 Docket No.30-409 License No. DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue, South La Crosse, WI 54601 Facility Name:
La Crosse Boiling Water Reactor Inspection At:
La Crosse Site, Genoa, WI Inspection Conducted: August 1-31, 1987.
Inspectors:
F6rney 9/.2 / //
W/dda
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M. W. Branch 9/'A 8/Fi
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W R/2W81 Approved By:
L. G. McGregor, Acting Chief Projects Section 2B l
Inspection Summary Inspectinn on August 1-31, 1981 (Repo t No. 50-409/81-16)
Areas Inspected: Routine resident inspection of Licensee's Operational Safety, Surveillance Testing, Maintenance Activities, Inspection and En-forcement Bulletin Followup, Licensee's Event Report Followup, Followup on Plant Scrams and Followup on Open Inspection Items. The int.pection involved a total of 304 inspector-hours onsite by two NRC inspectors in-cluding 23 inspector-hours during offshifts.
Results: Of the seven items inspected, no items of noncompliance or
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deviations were identified, l
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DETAILS 1.
Persons Contacted
- R. Shimshak, Plant Superintendent
- J. Parkyn, Assistant Plant Superintendent
- G. Boyd, Operations Supervisor
- L. Goodman, Operations Engineer
- H. Towsley, QA Supervisor
- S. Raffety, Reactor Engineer W. Angle, Process Engineer M. Polsean, Shift Supervisor W. Nowicki, Supervisor, Instrument and Electric R. Wery, QA Specialist
- G. Joseph, Security and Fire Protection Supervisor
- L. Kelly, Assistant Operations Supervisor
- P.
Shafer, Radiation Protection Engineer
- Bruce Zibung, Health and Safety Supervisor
- Denotes those present't exit interview.
a In addition, the inspector observed and held discussions with other engineers, plant equipment operators, reactor operators, assistants, and plant attendents.
2.
General The plant operated at 85% reactor power for most of the month of August with the exception of a one day outage starting with the reactor scram on August 3 and a three day outage starting on August 8, for necessary repairs to the Control Rod Drive Hydraulic System.
3.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the conth of August 1981. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified 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, and excessive vibrations and to verify that maintenante 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 August 1981, the inspector walked down the accessible portions of the Boron Injection system to verify operability. The inspector also witnessed portions of the radicactive waste system controls associated with radwaste shipments and barreling.
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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.
No items of noncompliance were noted.
4.
Monthly Maintenance Observation Station maintenance activities of safety related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specifications.
The following items were considered during this review:
the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibratiens were performed pricr to returning components or systems to service; quality control records were maintained; activities 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:
a.
Security Fence Modification as required by recent change to Physical Security Plan.
b.
Replacement of Initial Pressure R~gulator Controller.
Following completion of maintenance on the Security Fence and Initial Pressure Regulator Controller, the inspector verified that these systems had been returned to service properly.
No items of noncompliance were noted.
5.
Monthly Surveillance Observation The inspector observed Technical Specifications required surveillance testing on Reactor Protection Channel No. 2 "Safetys" and Reactor Portection Channel No. 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 affected components were accomplished, that test results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
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The inspector also witnessed / reviewed portions of the following test activities: Semi-annual Test of the No. 1 Emergency Service Water Supply System Pump; monthly test of Power Range Nuclear Instruments Channels No. 5, 6, 7 and 8; monthly test of the No. IB High Pressure Service Water Diesel Pump and the No. IB Emergency Diesel Generator.
No items of noncompliance were noted.
6.
IE Bulletin Followup For the IE Bulletin 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 or. information presented in the bulletin and the licensee's respence, 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.
a.
80-06 (Engincered Safety Feature Reset Controls).
Licensee response LAC 6987 indicated that facility modification was required and this action was accomplished as re-quired by Facility Change 64/38-80-2 and verified by the resident inspector.
7.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event report was reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with Technical Specifications.
a.
LER 81-08 (Main Steam Bypass Valce Controller not responding to pressure spikes properly). The licensee replaced the Initial Pressure Regulator (IPR) Controller and bench
'ested the Main Steam Bypass Valve Controller.
It appears that the Pressure Spikes caused by the malfunc-tioning IPR Ccntroller were of a magnitude and duration that was beyond the response capability of the Main Ste.' Bypass Valve Controller.
No items of noncomp..ance were noted.
8.
Plant Trips Following the plant scram at 3:22 p.m. on August 3, 1981 caused by a failure of the No. IA Reactor Feed Pump Speed Controller, the inspector ascertained the status of the reactor and safety systems by observation of control room indicators and discussions with licensee personnel con-cerning plant paraureters, emergency systeni status and reactor coolant chemistry. The inspector verified the establishment of proper communi-cations and reviewed the corrective actions taken by the licensee.
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All systems responded as expected, and the plant was returned to operation on August 4, 1981.
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i No items of noncompliance were noted.
l 9.
Followup on Open Inspection Items (OII)
a.
(Closed) Noncompliance No. 7:1 Record storage facility does not meet ANSI N45.2.9 requirements. This item was reinspected by USNRC
Region III Quality Assurance team and the only items remaining i
outstanding were (1).No index of contents, (2) Vault door is not fire rated and (3) No plant procedure specifying filing systems
to be used for QA records. These items were reissued as an item
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l of noncompliance in I/R 50-409/81-12.
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b.
(0 pen) Unresolved Item 80-09-01:2,/ Lack of calibration on stack
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and field air flow meters. The licensee has calibrated the field air flow meters, but has not developed a procedure to.nsure this correction data is utilized in the calculation of environmental
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data. The stack ;fr flow meters have not been calibrated due to
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a lack of traceable standards.
c.
(Closed) Unresolved Item 80-13-1:M
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Containment purge valves solenoids. Verified that licensee installed new solenoid. valves on the containment ventilation damper valves.n accordance with i
facility change FC-73-80-2jalso verified by acord review that valve operator seals were replaced and established in the pre-
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ventative maintenance program.
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(Closed) Unresolved Item 81-02-01:
Maintenance personnel not
. roperly observing radiological procedures. Licensee has changed p
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Operating Manual Volume X, Section 6.4 and. issued Health and Safety j-Memorandum dated August 8, 1981, re-emphasizing the need to adhere j
to all Plant Radiological Procedures.
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(Closed) Noncompliance 81-10-01:5I Failure to report all special
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tests performed in the 1979 and 1980 annual report. Licensee r
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issued LAC 7744 and 7745 to add tests that were not reported to
the annual reports of 1979 and 1980 and to establish a controlled ^
i distribution system to ensure that the person responsible for
issuing the annual report is made aware of all special tests and l
experiments conducted.
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10.
Exit Interview
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.The inspector met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of the inspection and summar-ized the scope and findings of the inspection activities.
V E Inspection Report-No. 50-409/78-01.
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IE Inspection Report No. 50-409/80-09.
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IE Inspection Report No. 50-409/81-13.
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IE Inspection Report No. 50-409/81-02.
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IE Inspection Report No. 50-409/81-10.
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