IR 05000409/1981014
| ML20010G591 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/10/1981 |
| From: | Branch M, Forney W, Mcgregor L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010G581 | List: |
| References | |
| 50-409-81-14, NUDOCS 8109220266 | |
| Download: ML20010G591 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/81-14
"ocket No. 50-409 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: July 1-31, 1981 Inspectors:
W. L. Forney
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M. W. Branch o
Approved By:
L. G. McGregor, Acting Chief cnad
.91de 9/N/i/
Projects Section 2B d
Inspection Summary Inspection on July 1-31, 1981 (he fort No. 50-409/81-a)
Areas Inspected: Routine resident inspection of Licer.see's Operational Safety, Surveillance Testing, Maint. nance Activities, Lspection and Enforce-ment Bulletin Followup, Inspection and Enforcement Circular Followup, Followup on Plant Scrams and Followup on Open Inspection Items. The inspection involved a total cf 250 inspector-hours onsite by two NRC inspectors including 16 in-spector-hours onsite during offshifts.
Results: Of tne seven items inspected, no items of noncompliance or deviation were noted in six of the areas. One item of noncompliance was noted in the area of Followup on Open Inspection Items (failure of plant personnel to follow written procedure).
8109220266 810910 PDR ADOCK 05000409 G
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DETAILS
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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. Rafferty, Reactor Engineer
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j W. Angle, Process Engineer M. Polsean, Shift Supervisor
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W. Nowicki, Supervisor, Instrument and Electric R. Wery, QA Specialist
- G. Joseph, Security and Fire Protection Supervisor l
- L. Kelley, Assistant Operations Supervisor l
- P. Shafer, Radiation Protection Engineer
- B. Zibung, Health and Safety Supervisor
- Denotes those present at exit interview.
i In addition, the inspector observed and held discussions with other engineers, plant equipment operators, reactor operators, assistants, and plant attendants.
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2.
General
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On July 28, 1981, Corporate Management from Dairyland Power Cooperative-(DPC) were in the U.S. Nuclear Regulatory Commission Region III Office
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for an enforcement conference. The meeting was called by NRC Region III for the purpose of discussing NRC's concerns regarding recent items of noncompliance and potential escalated enforcement actions. The meeting allowed for a healthy exchange of information between NRC management and attending DPC management in the areas of potential escalated. enforcement items and NRC's concerns with weaknesses in the management controls at
i LACBWR. USNRC Region III will issue a detailed report of the management meeting / enforcement conference in a separate Inspection Report.
3.
Operational Safety Verification The inspector observed control room operations, reviewed applicable
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logs and conducted discussions with control room operators during the month of July 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 maintenance requests had been initiated for equipment
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in need of maintenance. The inspector by observation and direct inter-view verified that the-physical. security plan was being implemented in.
accordance with the station security plan.
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The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the month of July 1981, the inspector walked down the accessible portiors of the Alternate Core Spray systems to verify operability.
The in-spector also witnessed portions of the radioactive waste system controls associated with radwaste shipments.
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 violations were identified.
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 calibrations were performed prior 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:
i Repairs to Turbine Initial Pressure Regulator (IPR) Controller.
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b.
Repairs to Control Rod Drive (CRD) Hydraulic Pump.
Following completion of maintenance on the CRD Hydraulic Pump and the IPR Controller, the inspector verified that these systems had been returned to service properly.
No violations were identified.
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Monthly Surveillance Observation The inspector observed Technical Specifications required surveillance testing on the No. I and No. 2 Safety Channels and the biweekly test of radi.ation monitoring equipment and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished,
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tcat test results conformed with Technical Specifications and procedure requirements were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the
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l testing were properly reviewed and resolved by appropriate management personnel.
The inspector also witnessed / reviewed portions of the following test i
activities: Nuclear Instrument Channels No. 5, 6, 7 and 8 monthly
test; Quarterly Inservice inspection of the following items: Shutdown l
Condenser, Steam and Condensate Valves, Containment Building Ventilation Dampers Valves and Purification System Stop Valves.
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No violations were identified.
6.
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 _ Bulletin and the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management j
representatives, that information discussed in the licensee's written
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response was accurate, and the correctP,e action taken by the licensee was as described in the written respanse.
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a.
81-02 (Failure of gate type valves to close against a differential pressure).
i b.
81-03 (Failure Flow blockage cooling water to safety system components by Asiatic Class and Mussels).
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No violations were identified.
7.
IE Circular Followup
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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 applicable
I to the facility, appropriate corrective actions were taken or were scheduled to be taken.
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a.
81-02 (Performance of NRC Licensed individuals while on duty).
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81-05 (Self aligning rod end bushings for pipe supports).
c.
81-08 (Foundation materials).
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No violations were identified.
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8.
Plant Scrams
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Following the plant scram on July 6, 1981 from 85% reactor power, l
caused by a spike on Nuclear Instrument Channel No. 7 or 8, the inspector ascertained the status of the reactor and safety systems-4-
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by observation of control room ir.dicators: and discussions with licensee
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t 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
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operation at 8:00 p.m. on July 6, 1981.
No violations were identified.
9.
Followup on Open Inspection Items (OII)
(Closed) '(Unresolved Item 81-10-02):1/
Possible problem with a.
compensatory measures taken during a security equipment malfunc-tion. USNRC Regien III Security Specialist reviewed this item
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during the August 3-5, 1981 security inspection and' concluded that compensatory measures taken by licensee were proper and
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adequate to provide equivalent security protection.
b.
(Closed) (Unresolved Item 81-06-01):M Statement of Policy for nonlicensed operators. The licensee has revised Administrative Control Procedure 21.1, to include a requirement that a candidate for a nonlicensed operator position must complete a training
program and possess a valid qualification card for the watch
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station he is being' assigned.
c.
(Closed) (Unresoivd Item 81-06-03):2_/ Proposed modification.
to containment buili.ing pressure setpoints, NUREG-0737, item (II-E.4.2.5).
NRR le tter from Crutchfield to Linder ' dated July 28,- 1981 stated chat licensee's setpoint for containment building pressure were acceptable as presently set.
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d.
(Open) (Unresolved Item 81-10-01):1I Failure to follow procedure.
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LACBWR Operating Manual, Volume X, Section 6.5.3 (7) stated in part: Each worker assigned to the Special Work Permit (SWP)
. will complete the required-information for-ea :h entry into the work area on the entry copy of the SWP.
Contrary to the above, on June 22, 1981 several plant management
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personnel failed to indicate on the job site copy of SWP (81-115)
their entry into and exit from the work site. This action by plant management personnel was in violation of the plant procedure
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as stated above. Plant management eliminated the procedure require-
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ment by simply changing the specific requirement after the procedure
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violation was,noted by the inspector. The frequency of plant per-
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sonnel failing to adhere to' approved plant procedures is noteworthy.
and has been addressed by the resident inspectors in their management
meetings with the licensee, in previous inspection reports and also 1/
IE Inspection Report No. 50-409/81-10.
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IE Inspection Report No. 50-409/81-06.
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discussed with the licensee at the enforcement conference held atLthe Region III office on July 28, 1981 (50-409/81-18).
'One violation was identified..
10.
Exit Interview The inspector met with. licensee representatives (denoted in Paragraph 1)
throughout the month and at the-conclusion of the inspection'and sum-marized the scope and findings of the inspection activities.
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