IR 05000409/1998004

Insp Rept 50-409/98-04 on 980921-22.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Sf Safety & Radiological Safety

ML20154K031
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	10/13/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20154K023	List: IR 05000409/1998004 ML20154K019
References
50-409-98-04, 50-409-98-4, NUDOCS 9810160081
Download: ML20154K031 (10)

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l U.S. NUCLEAR REGULATORY COMMISSION l

REGION 111 l

. Docket N License No: DPR-45 i

Report No: 50-409/98004(DNMS)

Licensee: Dairyland Power Cooperative 2615 East Avenue South La Crosse, WI 54601

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Facility: La Crosse Boiling Water Reactor <

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Location: La Crosse Site, Genoa, Wisconsin Dates: Septembe ^1-22,1998 Inspectors: D. Nelson, M.S., Radiation Specialist P. Lee, Ph.D., Radiation Specialist

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Approved By: Bruce L.Jorgensen, Chief '

Decommissioning Branch Division of Nuclear Materials Safety

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981'0160001 981013 PDR ADOCK 05000409 G PDR i

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l EXECUTIVE SUMMARY La Crosse Boiling Water Reactor NRC Inspection Report 50-409/98004(DNMS)

, This routine decommissioning inspection covered aspects of licensee management and

control, spent fuel safety, and radiological safety.

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. Overall, the licensee's perforrr.ance during decommissioning activities was good. All activiths inspected were conducted in compHwce with the Decommissioning Plan, the Quality Assurance Program (QAP) and the Technical Specifications Facility Manaoement and Control

. .' The licensee performed appropriate safety reviews prior to conducting limited  ;

I dismantling of reactor components and systems.

l * A Quality Assurance audit of the licensee's Corrective Actions Programs identified i minor weaknesses in the programs.

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Soent Fuel Safety ,

• Fuel Element Storage Well water level, chemistry and cleanliness control programs appeared adequate to ensure the safe wet storage of the spent fue Radioloaical Safety

. The Radiation Protection Program was effective in implementing the requirements of the Decommissioning Plan, the QAP and the license. Contamination and personnel exposure were well controlle . Housekeeping throughout the facility was excellen >

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Report Details l

Summary of Plant Activities ]

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Activities during the inspection period were limited to routine ongoing safe storage (SAFSTOR)

activities and very limited dismantlement of selected plant system .0 Facility Management and Control General The inspectors conducted reviews of ongoing activities in order to assess overall management and controls. Specific events and findings are detailed in the sections belo !

' (Closed) LER 50-409/97-01(DRP)

On January 2,1997, the licensee reported that both Emergency Diesel Generators (EDGs) 1 A and 1B were out of service contrary to tha Technical Specification (TS)

requirement that at least one EDG be available to provide A.C. power. During service for repair on EDG 1B, EDG 1A was found to be inoperable contrary to the TS requirement that at least one EDG be operable. Upon discovery, the licensee immediately reported the finding to NRC Region Il '

Subsequent to the incident, the licensee amended its possession-only license by deleting TS 4.3, "Electncal Power Systems," from the TS. The deletion removed the requirement that the EDGs be available to provide A.C. powe This LER is close .3 Oraanization. Manaaement and Cost Controls at Permanentiv Shut Down Reactors Inspection Scope (36801)

l The inspection evaluated whether the licensee's SAFSTOR organization, staffing and qualifications met the requirements of the Quality Assurance Program (QAP) and the Decommissioning Pla ;

1 Observations and Findinas j

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There have been no changes in the licensee's SAFSTOR organization since the last inspection. The plant manager, the technical staff, members of the Operations Review Committee and the Safety Review Committee remain unchanged from that inspectio Conclusions l The licensee's SAFSTOR organization, staffing and qualifications continued to meet the requirements of the QAP and the Decommissioning Plan Eraffin !

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- Safety Reviews. Desion Chances. and Modifications at Permanentiv Shutdown Reactors Inspection Scope (37801)

The inspection evaluated whether the licensee had e stablished an adequate program to identify unresolved safety questions resulting frort any facility design change, test, experiment, or modification during SAFSTO Observations and Findinos The inspectors reviewed four safety reviews (evaluations) that had been completed since the last inspection. Those safety reviews addressed the removal of the acid tank showers and eye wash stations, removal of the fuel casks transfer crane, installation of a videographic recorder in the control room and installation of a 24 inch diameter prefabricated manway on the circulation water intake tunnel. The inspectors' reviews indicated that the licensee had applied the appropriate rigor of engineering and management review required for each activity. There were no unreviewed safety questions identified or changes required to the TS Conclusions The licensed configuration of the facility was not changed without the appropriate licensee safety review .5 Self-Assessment. Auditina. and Corrective Action at Permanentiv Shutdown Reactors Inspection Scope (40801)

The inspectors reviewed the results of the 1998 audits of the Health Physics / Chemistry / Process Control (HPCPC) and Corrective Actions Programs (CAP)

to determine if the audits met the requirements and guidance in the QA Observations and Findinas Both audits used a checklist format. Questions about each program were answered with either a simple "yes" or "no" entry. Questions that did not apply were marked

"N/A." In addition to the questions, the audit format also allowed the auditors to address individual questions or issues not raised by questions, in text form, later in the report (checklist remarks section). While the format could have limited the scope of, the audits, the auditors appeared to have examined both programs in some depth and range. The auditors did identify Open items and one Nonconformance during the audits and followup by the auditors of previous audit findings were performed and documented. No safety significant findings were identified in the audi Two Open items were identified in the 1998 HPCPC audit. They were, however, administrative in nature and neither was viewed by the inspectors as being safety significant. One Nonconfonnance was identified in the audit; the results of the examination of the physical condition of two sources were not documented in the

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annual source inventory. Although this was a violation of station procedures, it was viewed by the inspectors as administrative in nature with little or no safety significanc Four Open items were identified in the CAP audit. Although the Open items appeared to be administrative in nature, two raised concemed about the liconsee's lack of timeliness with regard to closing incident Reports (irs) and reviewing documents listed on the Commitment Tracking List (CTL). Open item "B" reported that none of the eight irs generated in 1998 had been put in final form. irs are put into final form when corrective actions to address the issues raised in the irs are documented and implemented. The auditors concluded that management needed to evaluate and document what positive remedial steps have been taken or will be taken to address issues raised in the irs. Open Item "C" reported that documents listed on the CTL had not been reviewed within the time allotted. Documents on the list included, but were not limited to, NRC documents ar.d documents from other regulatory agencie Although timely review of documents listed on the CTL was not required by procedure, the auditors concluded that plant management needed to take a more aggressive and active approach to ensure items on the list are completed in a timely manner. The inspectors concurred with the auditors' conclusion In the HPCPC audit tne inspectors noted that several questions had been marked as a

"yes" response, even though the activities addressed by the question had not been performed during 1998 and some of the questions no longer applied to a plant that was in SAFSTOR. The lead auditor acknowledged these deficiencies and indicated that a review of the contents of the audit would be' performed prior to the next audi At the exit meetin0, management acknowledged the findings of the audits. However, management indicated that the lack of timeliness had been due in part to the staff's commitment to addressing other regulatory issues. Once those issues were resolved, management believed that issues involving timeliness would improv c. Conclusions

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The 1998 audits of the HPCPC and CAPS appeared to have met the requirements and guidance in the QAP. The audits identified the lack of timeliness in the CAP cad minor deficiencies were identified in the content of the HPCPC audi .0 Spent Fuel Safety 2.1 General The inspectors conducted the inspection to verify the safe wet storage of spent fuel at the La Crosse Boiling Water Reactor (LACBWR). Specific findings are detailed in the section belo .2 Spent Fuel Pool Safety at Permanently Shutdown Reactors a. Inspection Scope (60801)

The inspection reviewed the control of fuel element storage well (FESW) water level and impurities in the FESW water to determine tne safe wet storage of spent fue .

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l Observations and Findinas  !

The inspectors reviewed the calibration records for the water level transmitter and the l

daily logs of water level observations made by the operators. The spent fuel pool leak rates were measured by monitoring the water levels in the spent fuel pool. Since fixing the FESW system pump seals in 1992, the FESW leak rate has remained constant at j about 30 gallons a da i A review of the records indicated that the resins used to remove impurities in the FESW

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had been changed prior tu the conductivity of the FESW water reaching ten micromh By changing the resins, the licensee had kept the concentrations of Cs-137 in the FESW to about 1.0E-4 uCi/m Conclusions ,

The spent fuel pool water level, chemistry and cleanliness control programs appeared adequate to ensure the safe wet storage of spent fue .0 Radiological Safety General I i

The inspectors conducted reviews of ongoing activities in order to assess the overall Radiation Protection Program. Specific findings are detailed in the sections belo .2 Occupational Radiation Exposure j Insoection Scope (83750)

The inspection examined and evaluated aspects of the Radiation Protection Progra ,

Specific areas evaluated included staffing, extemal exposure control, radiological surveying, control of radioactive materials and contamination, and maintaining occupational exposure as-low-as-reasonably-achievabl ;

1 Observations and Findinas There were no significant changes in the staffing or management of the Radiation Protection Program since the last inspection. The Radiation Protection Program continued to be staffed by three technicians, one foreman and the health and safety superviso I A review of the extemal dosimetry records for the first two quarters of 1998 indicated

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that personnel exposure-" ere low, accurately reflecting the lack of activity within the  ;

L facility. Of the approxirr ately 50 personnel who were issued extemal dosimetry (film l badges), the highest individual dose during the second quarter was 40 millirem (mrem)

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1998.

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The inspectors reviewed a sempling of direct radiation survey results and smear l sample results for the secono quarter of 199 l Station procedures require that direct radiation surveys be performed quarterly in all i accessible areas within restricted areas. The records of the second quarter results i indicated that the licensee had complied with these requirements and exposure rates l within the facility had not changed significantl l

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Station procedures require that smear surveys be performed once a week in normally l

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contamination-free areas of the restricted areas and once a month in identified contaminated areas within restricted areas. The records of the 1998 results indicated that the licensee had complied with these requirements and the spread of contamination had been contained and contamination levels within the facility had been kept to a minimu ! Conclusions Staffing had been maintained in accordance with station procedures. The licensee had also complied with procedural requirements for conducting surveys and had been successful in controlling extemal exposures and containing the spread of (

contamination. Station dose accurately reflected the amount of work performed at LACBWR during the first two quarters of 199 .3 Solid Radioactive Waste Manaaement and Transportation of Radioactive Materials

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. Inspection Scope (86750)

The inspectors reviewed the shipping documents for three radioactive materials shipments made by LACBWR during the second and third quarters of 1998 and *

I interviewed the individual responsible for ensuring that the shipments were made in

complianca with NRC and Department of Transportation (DOT) requirement Observations and Findinas (

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During the period from April 28,1998, to September 1,1998, the licensee made three shipments of radioactive materials from the LACBWR facility. One shipment contaloed air filters and water samples that h4 been shipped to an offsite laboratory for analyses. The other two shipments were potentially contaminated dry active waste sent to American Ecology for processing and eventual disposal. LACBWR was the shippe? of record for all three shipments. The records maintained by the licensee for  ;

the shipments were excellent and showed that the shipments had been made in full i compliance with the applicable NRC and DOT requirement l l

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Reviews of the shipping documents for radioactive materials shipments made by  !

! LACBWR during April 28,1998, to September 1,1998, indicated that the shipments  !

j had been made in compliance with NRC and DOT requirements.

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i Tours of the Facility Inspection Scope (83750 and 86750)

The inspectors toured the reactor building, the turbine building and the containment buildin Observations ant;l Findinas Housekeeping in all of the buildings was excellent, all areas appeared to be clean and well maintained. Radiological controls and posting appeared to be in full compliance with procedural requirements. The material condition of the equipment and components observed was excellen .0 Exit Management Meeting The inspectors presented the inspection results to mernbers of the staff at the conclusion of the inspection on September 22,1998. The licensee acknowledged the findings as described in this report. The licensee did not identify any of the documents or processes reviewed by the inspectors as proprietar .

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PARTIAL LIST OF PERSONS CONTACTED

• R. Christians, Plant Manager

• R. Cota, Training / Security Supervisor i

• D. Egge, Quality Assurance

• J. Jiracek, Plart Maintenance

. *M. Johnson, Tech Support Engineer  ;

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j *L Nelson, Health and Safety Supervisor

*Denoter, those attending the exit meeting on September 22,199 !

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The inspectors elso interviewed other licensee personnel in various departments in the course

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1 INSPECTION PROCEDURES USED

IP 36801: Organization, Management and Cost Controls at Permanently Shut Down Reactors IP 37801: Safety Reviews, Design Changes and Modifications at Permanently Shut Down Reactors IP 40801: Self-assessment, Auditing, Corrective Action IP 60801: Spent Fuel Pool Safety at Permanently Shut Down Reactors

'lP 83750: Occupational Radiation Exposure IP 86750: Solid Radwaste Management and Transportation of Radwaste Materials Using Ti 2515/133, " Implementation of Revised 49 CFR 100-179 and 10 CFR Part 71" ITEMS OPENED, CLOSED AND DISCUSSED Opened None Closed 50-409/97-01(DRP) LER Both Emergency Diesel Generators were Inoperable contrary to technical specification Discussed None

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DOCUMENTS REVIEWED

.' ACP-04.1, " Design and Facility Change Control," Revision 23, dated 10/17/97 Memorandum from Mike Johnson to the ORC, " Response to ORC-97-01, Assignment 1:

l- Corrective Action for LER 97-01 (Incident Report DPC 97-01, "Less than Required A.C. Power Sources")," July 15,1998 ORC /SCR Commitment Tracking document, August 25,1998 HSP 7.2," Sampling of FESW"

! Direct Exposure Rate Surveys (July and August 1998) '

Smear Survey Results (July and August 1998)

Annual Report for 1997 - Report of Changes, Tests and Experiments, dated 2/23/98 -

Quality Assurance Audit Report of Health Physics / Chemistry / Process Control, dated 9/22/98 l Quality Assurance Audit Report of Corrective Actions, dated 8/28/97 I l

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Shipping Documents: 4/28/98,7/06/98 and 9/01/98

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