IR 05000409/1981007
| ML19352A925 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/12/1981 |
| From: | Branch M, Forney W, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19352A924 | List: |
| References | |
| 50-409-81-07, 50-409-81-7, NUDOCS 8106020355 | |
| Download: ML19352A925 (7) | |
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O U.S. NUCIJAR REULATORY COMMISSION OFFICE OF INSPETION AND ENFORCDENT
REGION III
Report No. 50-409/81-07 Docket 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 Cor4ucte 3 April 1-30, 1981 d
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Inspectors:
W. b.Forney
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h%Xmk M. W. Branch p.///
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Approved By:
R. F. Warnick, Chief M/M7/
Projects Section 2B
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Inscection Summary Inspection on Acril 1-30, 1981 (Recort No. 50-409/81-07)
Areas Inspected: Routine resident inspection of licensee's Operational Safety; Surveillance; Maintenance; Information Meeting with Local Officials; Followup Action on IE Circulars, Licensee Event Reports and Open Inspection Items. The inspection involved a total of 264 inspector-hours onsite by two NRC inspectors including 18 inspector-hours during offshifts.
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Results: Of the seven items inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
- B. Zibung, Health and Safety Supervisor
- R. 24m e=1<, Plant Superintendent
- J. Parkyn, Assistant Plant Superintendent
- G. Boyd, Operations Supervisor
- L. Goodman, Operations Engineer
- H. Towsley, Quality Assurance Supervisor
- S. Rafferty, Reactor Engineer W. Angle, Process Engineer M. Polsean, Shift Supervisor W. Nowicki, Supervisor, Instrument and Electric
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R. Wery, QA Specialist
- G. Joseph, Security and Fire Protection Supervisor
- L. Ke32,y, Assistant Operations Supervisor
- P. Sharer, Radiation Protection 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.
Information Meeting with Local Officials The Resident Inspectors met with the Township and Village Board of Genoa, WI at 8:00 PM on April 30, 1981. The inspectors informed the Public Officials of the following topics:
1.
Nuclear Regulatory Commission - Organization and Regulatory Responsibilities.
2.
Reason for the Resident Inspection Program was discussed -
more on-site time, better view of day to day activities, quicker response in the event of problems. The personal and professional background of the Resident Inspectors was also discussed with the officials.
The office telephone number (608) 689-2125 was given to the Boards and it was discussed that they should feel free to contact the The Inspectors Office for response to any questions or rumors.
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NRC Region III office telephone number (312) 932-2500 was also provided for information if the Resident Inspectors cannot be reached at their office.
The Public Document Room was discussed and the inspectors provided k.
the location and the types of material it contains.
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The inspectors infomed the Boards that Dairyland Power Cooperative was in the process of implementing their new emergency plan and that the people of Genoa should expect to see a Public Information Notice in their electric bills that will discuss actions to be taken in the event of an emergency.
The meeting was then opened to questions. The majority of the questions l
dealt with the topic of the emergency plan and how it will interact with the local people and deal with special cases. The inspectors infomed the Board that their concerns would be discussed with Dairyland manage-ment and that any concerns that are not resolved by DPC management in the Public Infomation Notice should be conveyed to DPC Public Affairs
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Operational Safety Verification The inspector observed _ control room operations, reviewed applicable logs and conducted discussions with control ro m operators during the month of April, 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 bn41 ding 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 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.
Theinspectorobservedplanthousekeeping/cleanlinessconditionsand i
f verified implementation of radiation protection controls. During the l
month of April,1981, the inspector walked down the accessible portions l
of the Alternate Core Spray system to verify operability. The in-spector also witnessed portions of the radioactive 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 confomance with the requirements established under technical specifications, 10 CFR, and administrative procedures.
The Resident Inspectors noted that during the month of February,1981, Nuclec.r Instmment Channel No. 8 read nonconservatively lower then calorimetric calibration data. This infomation was provided to the licensee and the Resident Inspectors posed the following questions:
1.
Because LACEWR's Technical Specifications does not address when a Nuclear Instmment is considered inoperable, does licensee consider t
NI Channel No. 8 operable?
2. Rrnlain why Channel No. 8 reads lower then calorimetric data? 3 What action does licensee plan to take to resolve the differences between Channel No.- 8 and calorimetric data?
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Since the Resident Inspectora expressed their concerns, licensee investigation has revealed that printed circuit boards in all four power range drawers and the spare was printed incorrectly, calibration data usec. to calibrate NI thnnah No. 7 and No. 8 were iacorrectly specified in procedure, data used to set Channels No. 1 and No. 2 powee-to-flow safety settings were incorrectly specified in procedure and the automatic gain settings for NI Channels No. 5, 6, 7 and 8 were t
l allowed to drift to a value that may be outside analyzed safety areas.
The licensee has corrected the printed circuit problem and the incorrectly specified data in procedures and 'has imposed operating
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limits on the Automatic Gain System. The licen4ee is presently conducting safety analysis to detemine if any unreviewed safety issues.are involved.
I The above item is considered unresolved item 81-4741.
j On March 16, 1981, while at 85% reactor power, tis plant experienced l
problems with the Initial Pressure Regulator (IPR) and decided to trip the turbine generator and bypass steam to the main condenser using the Main Steam Bypass Valve. Operation on the Bypass Valve caused a reduction in feed water heating due to a lack of extraction stese from the tripped turbine generator. This loss of feed water heating caused themal reactor power to increase to 101.83% while the Nuclear Instrument Channels No. 7 and No. 8 indicated only 87% power due to the features of the Automatic Gain System. Additionally the plant issued Operations Memorandum DPG % Rev.1 that'could have allowed o.perations on the Bynass Valve that may exceed Technical Specifications or allow operations outside presently analyzed safety areas. The Resident Inspectors expressed their concerns to plant management and the plant superintendent deci$ed to ' withdraw DPC % Rev.1. The Resident Inspectois have discussed the problems of operation on the Bypass Valve with NRR and the plant is presently e ng a safety
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evaluation of the problem experienced on March 16,1981 and operation l_
on the Bypass Valve in general.
The above item is considered unresolved item 81-07-02.
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Monthly Maintenance Observation l
Station maintenance activities of safety related systems and component 1 listedbelowwereobserved/reviewedtoascertainthattheywereconducted
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in accordance with approved procedures, regulatory guides and industry codes or standards and in confomance with technical specifications.
The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed frem service; approvals were obtained prior to initiating the
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work; activities were accomplished using appro sd procedures and were f
inspected as applicable; functional testing a:xi/or calibrations were perfomed 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 requeste were reviewed to detemine scatus of outstaMing jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system perfomance.
Thefollowingmaintenanceactivitieswereobserved/ reviewed:
1.
Replacement of pcwer supply for Intermediate Range Nuclear Instm-ment Channel Number 3 2.
Repairs to Power Range Nuclear Instmments Channels 5, 6, 7 and 8.
i Following completien of maintenance on the Compensating Voltage Power Supply for Intemediate Range Nuclear Instrument Channel Number 3, the inspector verified that thi.s system had been returned to service properly.
No items of noncompliance were identified.
Monthly Surveillance Observation Tne inspector observed technical specifications required surveillax e testing on the Ik:mber 1A Energency Diesel Generator and the Number IA High Pressure Service Water Diesel Pump and verified that testing was perfomed in accordance with adequate procedures, that test instrumen-tation was calibrated, that limiting conditions for operation were nt, that removal and restoration of the affected components were accomplished, that test results confomed with technical specifica-tions and procedure requirements and were reviewed by personnel other l
than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by
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appropriate management personnel.
The inspector also reviewed portions of the following test activities:
Bkn Alignment, N 5-9 Nuclear Instmment Checks, Reactor Water Level Probe Test wi the Bi-Weekly Safety Chacks.
No items of noncreliance were noted.
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6.
Licensee Event Reoorts Followuo
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Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to detemine that reportability requirements were fulfilled, immediate corrective action was accomplished, ani corrective action to prevent
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recurrence had been accomplished in accordance with technical spec-
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ifications.
I IJR 81-01 - Planned Loss 'of Off-Site Power for Maintenance l
IJR 81-03 - Gross Alpha Activity of Primary Coolant Sample Exceeded T.S.4.2.22.a.3 limits and caused Plant to Enter
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i Action of L.C.O.
IJR 81-04 - Improper Switching Caused Loss of 1B 480 V Bus Resulting i
i in Start of the Number 1B Bnergency Diesel Generator No items of nonc~an14=nes were noted.
IE Circular Followun i
For the IE Circular listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was perfomed, and that if the circular was applicable to the facility, appropriate corrective actions were taken or were l
scheduled to be taken.
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IEC 81-01 Design Problems Involving Indicating Pushbutton Switches Manufactured by Honeywell Incorporated No items of nonc~anliance were noted.
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Followup on Open Inspection Items (OII) and Previous Items of Non-compliance (Closed)
(Noncompliance item 8%13-2k-Failure of plant a.
management staff to make required plant tours. Plant has
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changed ACP's 2.3 and 2.4 to clearly define requirements for plant management tcurs.
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(Closed)
(Noncomplianceitem81-02-1Y-Operatorerrorcausing a total loss of off-site power. Plant management has established practical switchyard training for all LACBIE operators as in-
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dicated in LAC 7488 dated April 24, 1981.
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(Closed)
(Unresolved item'81-02-3 -Incomplete response to
'IMI task IM. Licensee has established in ACP L5 2the re-quirement for two party verific.ation of Lock and Tag procedure on safety related systems.
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_1/ IE Inspection Report No. 50-409/80-13 2/ IE Inspection Report No. 50-409/81-02 i-
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Unresolved Items Unresolved items are matters about which more inforination is required in order to ascertain whether they are acceptable items, itsas of noncompliance, or deviations. Unresolved items discicaM during the inspection are discussed in Paragraph 3 10. Exit Interview Theinspectormetwithlicenseerepresentatives(denotedin Paragraph 1) throughout the month and at the conclusion of the inspection and summarized the scope and findings of the inspection activities.
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