IR 05000409/1990001
| ML20059N634 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 10/05/1990 |
| From: | Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20059N629 | List: |
| References | |
| 50-409-90-01, 50-409-90-1, NUDOCS 9010170063 | |
| Download: ML20059N634 (8) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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REGION III
Report No. 50-409/90-01(DRP)
Docket No. 50-409 License No. DPR-45
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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, Wisconsin Inspection Conducted: September 17.and 18, 1990 Inspector:
D. Schrum
/0 kkO Approved By:
R.
e Reactor Projects Section 2B Date Inspection Summary inspection from Se)tember 17 through 18, 1990 (Report No. 50-409/90-01(DRP))
Ardas Inspected:
touTTHs7 announced inspection of operationiT sarety, maintenance, surveillance, nonlicensed staff training, audits, licensee review of Information Notices, and changes in the organizational structure and staffing.
l Results:
In summary, the licensee was found to be conducting audits, l-performing the PM program, reviewing ins and Bulletins,'and conducting routine surveillances in a satisfactory manner.
Housekeeping was very. good. The plant is clean and well maintained. There were minimal indications of leaks and rusting of plant equipment. The lights and fans are on in containment to maintain plant accessibility and environmental conditions. Some portions of the plant had been newly painted this year.
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9010170063 901005
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PDR ADDCK 05000409
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DETAILS
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1.
Persons Contacted L
- J. Parkyn, Plant Superintendent S. Raf fety, Reactor Engineer L. Nelson, Health and Safety Supervisor l
G. Boyd, Operations,180, Maintenance and Electrician Supervisor -
J. Tischer, Mechanical Maintenance Foreman
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R. Cota, Shift Supervisor l
T. Krueger, Plant Operator
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o The inspector also interviewed-other licensee personnel.during the course
of the inspection.
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- Denotes those attending exit interview during the inspection period.
2.
General f
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On April 24, 1987, the Dairyland Power Cooperative (DPC) Board authorized
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the permanent shutdown of LACBWR due to economic reasons.
The reactor is defueled with the core spray bundle and vessel lid in place and the primary coolant system filled with water.
On August 4,1987, the Commission issued license Amendment No. 56 to License No. DPR-45 changing it'from an operating license to a license
to possess - only.
On September 15, 1987, License Amendment No. 57.to the provisional
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license removed Inservice Inspection requirements for.high pressure primary system piping and equipment and deleted the requirements for
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nuclear instrumentation.
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On Decensber 21, 1987, DPC submitted its proposed Decommissioning Plan, the prelim b' y Decontamination Plan, and a supplement to the Environmental Report. The new TS for SAFSTOR was submitted separately
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on February 22, 1988.
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On January 4,1988, License Amendment No. 58 to the provisional license
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reduced the fire brigade from five members to three, reassigned fire -
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brigade training from the Mechanical. Engineer to a qualified Technical Support Engineer, deleted the position of Training Supervisor. and
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L reassigned training program responsibilities to a qualified Shift'
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Supervisor, changed the Operations Review Conunittee membership due to the reduction in staf f, and changed the Facility Organization Chart.
- J In an organizational change on January 4,1988, the Quality. Assurance Department, which formerly reported to-the LACBWR Plant Superintendent, now reports to the Assistant General Manager for Operations. The QA i
department, consisting of the Quality Assurance Director and four QA/QC Technicians, will devote approximately. fifty percent of their effort to
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the LACBWR programs.
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On February 10, 1988, the licensee requested that its application of
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October 9,1974, be amended by deleting its request for a' full-term
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operating license and requesting that LACBWR be placed in a SAFSTOR
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condition and be maintained as specified_ in the Decommissioning Plan.
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On March 14, 1988 Amendment No. 59 to the provisional license revising the Technical Specifications was issued. This' amendment removes the TS requirements for Containment Integrated Leak Rate Testing.
l MO, Amendment No. 60 to the provisional license revising :
On April 11,l Specifications was issued.
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the Technica 111s amendment changes the duty-shift requirements from three to two:
a Shift. Supervisor and a qualified Control Room Watchstander.
i On May 8, 1988, License Amendment No. 61 to the provisional license l
revising the LACBWR Physical Security Plan and Safeguards Contingency Plan was issued. This amendment changed the physical security requirements to
the.SAFSTOR mode with complete rearrangement of security equipment and a
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significant reduction in the security force.
On May 31, 1988, License Amendment No. 62 to the provisional possession - only i
license was issued. This amendment removed TS requirements for 0)erational Conditioas, i.e.,1 - Power Operations, 2 - Startup, 3 Hot
$1utdown, 5 - Refueling. Most of. the conditions for 4 - Cold Shutdown remain. This amendment also removed the safety limits, limited safety system settings, limiting conditions of operation for systems:used only for an operating reactor and other miscellaneous operational TS requirements.
On July 8,1988, the Commission notified the licensee that Revision 10 of the Emergency Plan had been approved.
Because of the significant reduction in the potential radiological hazards, the highest' emergency classification is now an Alert declaration and the previous five-mile
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emergency planning zone has been reduced to the DPC site boundary or:
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the owner-controlled area.
On August 18, 1988, License Amendment No. 63 revised the Provhional License No. DPR-45 to a full term possession
.only license that expires on March 29, 2003.
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On December 22, 1988, License Amendment No. 64-revised the Technical Specifications to-delete monitoring requirements ~ for a radionuclide.
(Iodine-131) which is no longer present at the La Crosse facility.
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On April 26, 1989, License Amendment No. 65 revised the-Technical
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Specificatiens because two new tanks of 265 gallon capacity were installed for the fire pump diesel engines to replace the older differently sized tanks. The TS change requires 150 gallons of fuel in both tanks which
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would allow each engine to operate for 15. hours without. refueling.-
As of this re) ort period, the-Decommissioning Plan had not yet been j
approved by t1e NRC.
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3.
Non-licensed Staf f Training (IP,41400)
The inspector. reviewed.the training program and records and determined
that the scope of the revised program was adequate for the plant status
and that the program was being implemented.
Records were maintained for
- all persons trained during the year. Two newly hired persons are in
training to become reactor operators.
Both have prior backgrounds which
included Navy nuclear power programs, so they.were a good addition to the
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plant staff. Both had recently passed exams to become qualified as Auxiliary Operators (A0s). The health physics technician that was hired
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and in training in 1989 was qualified during the.last year.
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The 1990 formal training' schedule was as listed below:
1990 TRAINING SCHECULE
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FEBRUARY:
General Employee Training (GET)'
HARCH:
System Training for A.0.'s..- Demineralized Water; high.
pressure service water (HPSW) and Fire Protection; i
low pressure service water (LPSW)
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r APRIL:
System Training for A.0.'s - Waste Water; Air;
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FuelElementStorageWell.(FESW)-
MAY:
System Training for A.O.'s - Component Cooling Water-(CCW);-
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Condensate; Well Water; Administer A.0. Requalification Exam
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l JUNE:
Reactor Theory (as applicable to the storage and handling -
of spent fuel).
JULY:
Emergency Procedures (including Emergency Plan)
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AUGUST:
System Training - Forced Circulation; SI; Heating
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VentilationandAirConditioning(HVA);-
Purification System
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SEPTEMBER:
Radiation Protection (including Portable Instruments and
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Backshift Health Physics Training)
'l OCTOBER:
Administrative Controls Fire Fighting and Procedures t
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Review /Make-up DECEMBER:
Annual Licensing Requalification Exam Those training commitments that were not completed on the designated month were finished the following month..
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Overall, the plant personnel appeared to be competent at performing
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their assigned tasks which indicates.their. expertise prior to the shutdown'
and that the current training is adequate.
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No violations or deviations were identified.
4.
Fire Protection and Prevention' program (IP 64704).
Back up fire prote'ction capability is available from the Genoa, Wisconsin, Fire Department. A fire brigade training program was being implemented for the brigade members. Fire fighting training was conducted onsite through a contract with a local technical school. 'The current requirement is to have three fire brigade members on shift at all times. The licensee also ensured that the three person requirement was met on the back shifts.
Tours of the plant and office spaces indicated that combustible materials
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were properly controlled. The housekeeping throughout the plant was good.
No violations or deviations were identified.
O erational Safety Verification (IP 71707)
5.
J Tours of the crib house, reactor building, and turbine building were conducted to observe plant equipment conditions and fluid leaks. The plant was well maintained and no leaks were observed. One.
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maintenance action resulted in rework due to an undersized bushing being-installed on a pump in the shield house.
The inspector verified that decay heat' calculations were made and were being tracked. The calculations and plotted curve were conservative and did not take into account the conductivity of the spent fuel.well walls. The licensee has more than adequate time to take corrective actions in the event of the loss of water from the spent ~ fuel well.
It was noted that minimal water spray would be adequate cooling at this time.
The water leakage from the spent fuel well is plotted on a-graph on a wall, readily observable by management. The-leakage rate is.
constant at about 50 gallons per day. There had been no increase in the trend over the past year. Although this leak has existed for the entire o
life of the plant, the inspector's concern is that the concrete may weaken from the constant leaching of minerals out of the concrete. The wet pool water quality was maintained. No detected problems had occurred'
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from algae growth. The licensee agreed to check on the possibility of'
l monitoring for bacteria growth which could result in bacterial corrosion of the fuel cladding.
I The licensee has been reviewing IN's for their applicability to the plant.
The licensee performed the necessary research to determine if the ins were applicable to LACBWR and had taken appropriate actions'in the plant when necessary. Due to the shutdown. status of LACBWR, many of the ins are no longer applicable.
The radiation exposure of the work force has continued to be reduced during the past year as a result of decreased activity in ~the plant and af reduction in the type of _ jobs that led to exposures. The licensee has
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built a tent on the refuel floor of the containment to minimize the
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spread 'of contamination during work activities.
Earlier in the year, 'one potential over-ex30sure occurred-when a radiation technician transferred a component that lad high activity through the plant without being aware -
of the exposure being received.
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The licensee has planned hot particle improvements to the facility.
Planned are the purchase of a new frisker and an improved laundry-l facility. A new air particle monitor was recently purchased for the
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containment. A new aluminum cover _ had ~ also been fabricated for the
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L wetwell to reduce the possibility of contamination from evaporation.
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No violations or deviations were observed.
6.
Surveillance Procedures and Reccrds (IP 61700)
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Due to the amount of equipment that is required to be operational,
the number of required surveillances is still substantial and were-being performed in a thorough and professional manner. The required surveillances were performed by the appropriate plant personnel, and surveillance procedures and records were maintained. Surveillances were performed on schedule.
No violations or deviations were observed.
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EvaluationofSelf-AssessmentCapability(IP40500]
The operations review committee has been meeting when required to approve
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procedure changes review applicable Bulletins, review delays in the
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preventative maintenance work items, etc. The required audits were'
s performed at the plant.
Review of meeting min' tes and audits indicated u
that the licensee T.S. commitments were being met.
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No violations or deviations were observed.
8.
Og anization and Administration
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See Attachment 1 (LACBWR Organization Chart) LACBWR staffing.
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Over the past year, the licensee has maintained the majority of its
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remaining staf f.
The following major changes occurred during the year.
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The mechanical maintenance supervicor retired and was not replaced.
Two individuals were hired to be trained as reactor operators. - A new electrician has been added to the staff. The licensee was_having difficulty finding a qualified realacement for the radiation protection engineer position whic1 has been vacant for one year, j
The site engineering staf f and the health and safety group were performing collateral duties for the coal fired plants.
During this inspection period, the mechanical maintenance staff wa's'
reduced by one member.
The mechanical maintenance supervisor retired in April of 1990, and as a result, the plant' transferred his' duties to the '
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operations supervisor (0S) who is al.so the supervisor of the I&C and.
electrical groups.
In addition, the OS is responsible for performing planned mechanical maintenance modifications to the plant for the fuel
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storage. The mechanics are performing PMs, corrective maintenance, yard I
work, building repairs, etc.
On a rotating basis,sthree of the maintenance crew members are used as auxiliary operators. With the p
continued use of the maintenance staff as A0's, the size of the
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maintenance'staffcis small. Many of the 'staf f members had reservations
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preventive maintenance' programs.c The: attrition ofJexperienced plant
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personnel willl present long term aroblems: for. the ' maintenance group'.
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five years, the majority of this lighly skilled group will be lost due to-retirements.
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The licensee's estimate of the portion of-the plant that:will need to.
g remain operational'for the.near future is'40-50. percent of the
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. operational systems, 'so the licensee will need to' retain'. highly: skilled
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a personnel who know the plant or adequate. resources to train new; personnel.:
During the previous year, the-licensee.had.in fact maintained this.
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committment.
1; 10. Exit Interview L
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a The inspector; met with licensee representatives (denoted in Paragraphi1)
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-on September'18,'1990. The insoector summarized.thesscope and findi.ngs~of;'
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'the-inspection' activities. The. licensee acknowledged the. findings =as
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fc reported herein~ and did not identify such. documents lor processes as'-
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proprietary.
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