IR 05000344/1998002

Insp Rept 50-344/98-02 on 980601-04.No Violations Noted. Major Areas Inspected:Activities Including Spent Fuel Pool Safety,Occupational Radiation Exposure & Decommissioning Performance & Status Review

ML20236G992
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/01/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20236G971	List: IR 05000344/1998002 ML20236G967
References
50-344-98-02, 50-344-98-2, NUDOCS 9807070039
Download: ML20236G992 (15)

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ENCLOSURE 2 U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket No.: 50-344 License No.: NPF-1

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Report No.: 50-344/98-02 Licensee: Portland General Electric Company (PG&E)

Facility: Trojan Nuclear Plant Location: 121 S. W. Salmon Street, TB-17 Portland, Oregon l j

Dates: June 1-4,1998 Inspector: J. V. Everett, Health Physics Inspector Nuclear Materials Safety Branch 2

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Approved By: D. Blair Spitzberg, Ph.D., Chief Nuclear Materials Safety Branch 2 l

Attachment: Supplemental Information i i

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DR g ADOCK 05000344 PDR r-l

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EXECUTIVE SUMMARY Trojan Nuclear Plant NRC Inspection Report 50-344/98-02 The Trojan facility was undergoing active decommissioning and dismantlement. All activities observed during this inspection were being performed safely and in compliance with radiological control requirements. Work areas were being kept clear of unnecessary material. Radiological practices continued to maintain control of radiological material and prevent the spread of contamination to clean areas. Chemical decontamination had been performed on semral systems and wes successful in reducing area dose rates. Personnel worker exposures for 1997 and 1998 were reasonable for the work being performed and were consistent with previous years. No workers received over 1000 mrem for 1997. Overall, health physics personnel were providing strong controls over the radiological work activitie "

A number of required programs and reports were reviewed and found current. All required programs reviewed were being maintained and reports being submitted to the NRC within the required time frames. The licensee's intemal self assessment program was providing an _

acceptable process of identifying and tracking problems found in the plant. The number of problems being identified were comparable to previous year The efforts by the licensee to resolve the free release problem, which had resulted in two previous violations, was nearing completion. The actions taken by the licensee were comprehensive and resulted in strong improvements to the program to prevent re-occurrenc Soent Fuel Pool Safetv

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The spent fuel pool was being maintained in compliance with Technical Specifications for water level and water temperature. Pool water clarity was very good (Section 1).

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Installation of a new system to maintain spent fuel pool cooling, make-up water, and clean-up were progressing and will provide for an isolated system not vulnerable to the

. ongoing dismantlement activities underway (Section 1).

Occupational Radiation Exoosure

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-- Occupational exposures for workers during 1997 and the first quarter of 1998 were

' reasonable for the work being performed and were consistent with exposures reported in 1996 (Section 2).

.~ Contaminat!on controls in the plant were observed during plant tours and were found to j

- be adequateJ Plant workers were observed following proper radiological procedures at l

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step-off pads and the exit to the radiolog:*. ally cortro!'ed area (Section 2). 1

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-3-Decmmissionina Performance and Statna Review i

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Decommissioning activities were progressing in the auxiliary / fuel building and containment. Equipment removalin containment was projected for completion by the end of 1998. The overall completion of all site dismantlement activities was projected for -

the year 2002 (Section 3).

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Work was continuing on plans for shipping the reactor vessel and intemals to Hanford,-

Washington, for burial. The pathway analysis associated with the burial of the vessel had been completed and was under review by the state of Washington (Section 3).

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Tours of the work areas were conducted. Work was being performed safely, areas were properly posted,- contamination controls were established, fire loading was low, and housekeeping was good (Section 3).

Self-Assessments. Audits. and Corrective Actions

The corrective action program at Trojan was documented in procedures and under the -

responsibility of the Nuclear Oversight group. Potential problems were being identified, documented, evaluated, and tracked effectively, No significant issues were fc,und during --

the review of several of the corrective action requests (Section 4).

Oraanivatian! Man =aament. and Co' nt Controls

-+ ' Required documents listed in Technical Specification 5.7.2 were confirmed to be available and current. Changes to the fire protection plan in Amendments 18 and 19 were reviewed and found acceptable (Section 5).

Radioactive Waste Manaamment. Effluents. and Environmental Monitorina

- ' The licensee had submitted the required 19P? radiological and environment . reports to

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the NRC.- Radiological levels around the plant were at background levels except for one location near an area where radioactive material was stored onsite. Liquid radiological releases from the plant were a small fraction of regulatory limits. Solid radwaste shipments in 1997 were comparable to the number of shipments in 1996 but contained a significantly lower total curie content (Section 6).

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Report Details i

Summarv of Plant Statum

- Dismantlement and decommissioning activities were in progress at the Trojan facility. A significant amount of dismantlement had been completed in the containment building and the

' auxiliary / fuel building. A new doorway had.been established into containment to allow easier

access by workers. The protected area security requirements were also removed for

containment. Chemical decontamination techniques had been used on several systems -

successfully and had reduced area dose rates for the workers. The licensee was proceeding with their effort to obtain NRC approval to remove and ship the reactor vessel and intemals to Hanford for burial. The licensee was working with the NRC, state of Washington, and state of Oregon to provide an adequate basis of acceptability i r the project.-

-1 Spent Fuel Pool Safety (60801, 86700) Inspechon Scope

. Cleanliness conditions around the spent fuel pool, cleanliness of the pool water, and

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compliance with Technical Specification 3.1.1 " Water Level", and Technical Specification 3.1.3. " Temperature" were evaluate ' A new system was being installed to provide make-up water, cooling, and water clean-up for the spent fuel pool to allow for the dismantlement of the existing plant systems that i provide services to the spent fuel pool. A review of the licensee's plans for using the new system was conducte L 1.2 - Observation and Findinos i

Technical Specification 3.1.1 required the spent fuel pool water level to be maintained at or.above 23 feet over the spent fuel. Records were reviewed for the first 5 months of

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j 1998. Water level had been maintained above 24 fee !

l 1 Technical Specification 3.1.3 required the spent fuel pool water temperature to be maintained at or below 140*F. Records for the first 5 months of 1998 were reviewe Water temperature was maintained between 50*F and 70*F. During a pool heat-up rate test at the end of 1997, the pool heat-up rate was determined to be 0.45'F/ hou ,

l 'A tour of the spent fuel pool area'found good housekeeping with the area clear of debri Water clarity of the spent fuel pool was very goo l

The licensee was in the process of installing a special cooling, make-up water, and

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, demineralized system for the spent fuel pool. This will allow dismantlement of the .  ;

existing system as part of plaat decommissioning. The existing system was l

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' interconnected with numerous other plant systems such that dismantlement of the other -

systems was restricted due to the many interconnections. The new system will be self contained. This will eliminate the potential that dismantlement activity could inadvertently affect the spen't fuel pool system The domineralizer portion of the new system was installed. The cooling portion of the new system had been installed, however the cooling coils leaked, requiring removal and repair. Because this new system wi!! be necessary to maintain compliance with several Technical Specifications for the opent fuel pool, it is important that the system be reliabl l For this reason, PG&E is expected to maintain the existing systems operable until sufficient confidence has been established with the new system. The NRC requests that prior to dismantling the existing system, the Trojan Site Executive and Plant General Manager provide in writing to the NRC notification that adequate acceptance and testing has been completed such that sufficient confidence has been gained in the operability and availability of the new system to perform it's intended function. Consideration can be given to the current heat load of the spent fuel pool and the time that would be allowed to obtain replacement parts and complete repairs before the Technical Specifica; ions for

- the spent fuel pool were exceeded. A list of procedures describing compensating actions

= that would be implemented to maintain compliance with Technical Specifications during .

failure of the new system should be provided. Review of the procedures will. be

. conducted during a future inspection. Receipt of the licensee's notification letter of :

acceptance of the new system will be tracked as inspection Follow-up item (IFI) .50- l 344/9802-01 Conclusion The spent fuel pool was being maintained in compliance with Technical Specifications for !

water level and water temperature. Pool water clarity was very goo ;

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Installation of a new system to maintain spent fuel pool cooling, make-up water, and clean-up were progressing and will provide for an isolated system not vulnersble to the ongoing dismantlement activities underwa Occupational Radiation Exposure (83750) and Review of Periodic and Special

Reports (90713) '

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2.1- Inapection Scoos Occupational exposures for site personnel were reviewed for 1997 and the first part of 1998 to determine if exposures were reasonable for the work underway and comparable

' to 1996 occupational exposures. Plant tours were conducted which included observation

. of contamination controls and posting of area l l

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. 2.2 - Observation and Findino The Occupational' Radiation Exposure Report, required by Trojan's Technical Specification'5.8.1.1, provided a summary of exposures for personnel receiving over 100 mrem for 1997. The licensee monitored 577 individuals during 1997 of which L 132 exceeded the 100 mrem dose. The total site dose was 49.3 manrem. The total dcse for the 132 individuals exceeding 100 mrem was 39.3 manrem. No individual received over 1,000 mrem. Four individuals received between 750 mrem and

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'1000 mrem and 13 individuals received between 500 mrem and 750 mrem. The dose l for 1997 compared favorably to 1996 in which 368 personnel were monitored and a total dose of 48.5 manrem accumulated.' For the first quarter of 1998, doses were also comparable with previous years. Approximately 390 personnel were being monitore The dose for the first quarter of 1998 was 11.3 manrem. Radiological conditions for work activities conducted in 1997 and the first half of 1998 appeared to be similar to that of the ]

previous yea Plant tours were conducted throughout the plant, except for containment. Observation of j

work activities in containment was performed via closed circuit television. Radiological l controls were adequate and workers were complying with health physics requirement ;

Contaminated areas were posted and protective clothing was readily available. Step-off I pads and receptacles for contaminated clothing were properly positioned at exit points from contaminated areas. Contaminated material was being placed in designated storage containers and proper.ly stored. ~ Unnecessary accumulation of contaminated

~ material in work areas was not observed. Proper frisking and monitoring was being I

performed at the exit to the radiologically controlled are ' 2.3 . Conclusion Occupational exposures for workers during 1997 and the first quarter of 1998 were reasonable for the work being performed and were consistent with exposures reported in 199 ,

Contamination controls in the plant were observed during plant tours and were found to be adequate. Plant workers were observed following proper radiological procedures at step-off pads and the exit to the radiologically controlled are . Decommissioning Performance and Status Review (71801) Insobetion Scooe

, Trojan was actively progressing with dismantlement c,f the facility. Work underway was reviewed with the licensee and compared to the overall schedul i

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A tour of the plant was conducted to observe work activities in progress. During the plant tour, housekeeping, fire loading, and OSHA compliance were observed.

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3.2 ' - Observation and Findinos

' Activities related to the dismantlement of the Trojan facility were progressing. Work appeared to be consistent with schedules. Completion of the dismantlement of the site

' was projected for the year 2002.' in the auxiiiary/ fuel building, approximately 85 percent

' of the equipment in the east and west horizontal pipe chase had been removed. Various holdup tanks, filters, piping for the boron injection tank room, volume' control tanks, and

. equipment from the radiological sample lab had been removed.. In containment,

' equipment removal was on schedule for completion by the end of 1998. The attemate containment access control point had been installed and was being used by workers to -

provide easier access to containmen Chemical decontamination of the regenerative heat exchanger had been completed.-

General area dose rates, which had been aa high as 2,000 mrem /hr, had been reduced -

to 60 mrem /hr. This was estimated to save 5 manrem while decommissioning the -

regenerative heat exchanger and adjacent areas. The containment recirculation sump area decommissioning was almost complete. The remaining work was planned for completion after the reactor drain lines had been flushed to reduce general area dose

' rates, which were as high as 300 mrem /hr. Chemical decontamination of the hold-up tanks was complete with a final decontamination factor of three. The hot sample room -

decommissioning was complete except for the active system L Work was continuing to obtain NRC approval to ship the reactor vessel and internak k Hanford, Washington, for burial. The construction of the barge for shipment had been completed. ' A pathways analysis for burial of the vessel was completed and sent to U.S. Ecology, which forwarded the analysis to the state of Washington for revie A tour of the plant was conducted to observe work underway. All workers were observed to be following radiological protection requirements. Work areas were, in general,

' organized and orderly. No accumulation of waste material or material that presented a fire hazard was observed, Work appeared to be conducted safely in the areas toure From conversations with several workers, their attitude about safety and the work being c performed at the site was positiv .3 - Conclusion -

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' Decommissioning activities were progressing in the auxiliary / fuel building and

. containment. Equipment removalin containment was projected for completion by the end of 1998. .The overall completion of all site dismantlement activities was projected for the year 2002, i

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L Washington for buria!. The pathway analysis assoc'ated with the burial of tha vessel had been completed and was under review by the state of Washingto .

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8-Tours of the work areas were conducted. Work was being performed safely, areas were J properiy posted, contamination controls were established, fire loading was low, and housekeeping was goo : Self-Assessments, Audits,' and Corrective Actions (40801) and Effectiveness of Licensee Controls in identifying, Resolving and Preventing Problems (40500)

- Inspection Scope The licensee's process for self identifying potential problems, assessing the significance of the concem and tracking corrective actions was evaluate >

'4.2 - Observation and Findinas l The Trojan Nuclear Oversight group was responsible for the overall administration of the site corrective action program. The corrective action program was documented in 1 l

- Procedure TPP 17-1, " Corrective Action Program," Revision 8. This procedure K established the process for identifying, evaluating and tracking conditions adverse to quality related to the safe storage of irradiated fuel. A corrective action request was used

. to initiate the process of identifying a potential problem. The corrective action request also provided an effective mechanism to inform' management of problems being -

. identified in the plant. If the corrective action request was determined to not involve an adverse safety issue, it could be canceled through a process described in Procedure-TPP 17-1 by obtaining the proper signature ' For the first 5 months of 1998,18 corrective action requests were initiated. . This compared to 32 corrective action requests in.1997 and 25 corrective action requests in l 1996. The 1938 corrective action requests covered areas such as security, radiological

' controls, fire extinguishers, and radiological shipments. Of the 18 corrective action requests, five were identified through audits and surveillences and 13 were identified by ;

plant staff. The corrective action requests were rated in accordance to significance as either "A,* "B," or "C." "A" had the highest significance. Of the 17 corrective action requests that had been rated,8 were rated as "A," 7 as "B," and two as "C." The -

eighteenth corrective action request was still being evaluated for a rating. The corrective l

action requests were tracked on computer and could not be closed until all corrective

' actions were completed. The program was well organized. Open corrective action ,

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. requests were readily retrievable and well documented. A review of several corrective

' action requests found no significant issues requiring additional NRC evaluatio ! Conclusion aThe corrective action program at Trojan was documented in procedures and under the

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responsibility of the Nuclear Oversight group. Potential problems were being identified,'

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- documented, evaluated and tracked effectively. No significant issues were found during L the review of several of the corrective action requests.

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5 Organization, Management, and Cost Controls (36801), Inspection Scope Technical Specifications 5.7.2 required the licensee to maintain a number of specific

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. programs and manuals.. A review was conducted to verify that the required manuals and

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procedures were being maintained and updated as necessary. The licensee had also issued two revisions to the fire protection plan which were reviewe ; Observahon and Findings The following programs were required by Technical Specification 5.7.2 and were.-

confirmed to be documented by the licensee and curren Required Program Documented in Rev/Date Radiation Protection Program' TPP 20-2, Radiation Protection Rev.7<

T.S.5.7. Program 4/97 Process Control Program Offsite Dose Calculation Manual Amend.14 T. S. 5.7. /97 Offsite Dose Calculation Manual Offsite Dose Calculation Manual Amend.14 T.S.5.7. /97-Radioactive Effluent Control Offsite Dose Calculation Manual Amend.14 Program, T. S. 5.7. /97 Radiological Environmental . Offsite Dose Calculation Manual Amend.14 Monitoring Program, T. S. 5.7. /97 Storage Tank Radioactivity - TPP 26-3, Storage Tank Re Monitoring Program, T. S. 5.7. Radioactivity Monitoring Program 5/95 Fire Protection Program Fire Protection Plan Amend.19 T. S. 5,7. /98 Spent Fuel Pool Water Chemistry TPP 26-2, Spent Fuel Pool Water Re Program T. S. 5.7. Chemistry Program 5/95 Control Building Structural TPP 12-22, Control Building Re ,

Monitoring T. S. 5.7.2.9- Modification Through Bolt 12/96 3 Surveillance L Spent Fue! Pool Cooling and TPP 30-1, Nuclear Division Rev.11 Makeup Monitoring Prcgram Defueled Requirements and 5/98 T. S. 5.7.2.10 Defueled System List

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-6 All documents were readily available and maintained as contresad documents.-

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-10-l The licensee' issued Amendment 18 to the site fire protection plan on April 22,1997, and -l Amendment 19 on April 27,1998. These revisions updated the fire protection plan to l reflect current plant conditions. The changes reflected new smoke detectors added to I the radwaste processing building, updated the Chapter 3 listing of which systems were remover 8 or deactivated to reflect actual status in the plant, and incorporated the recent i addition of a doorway to allow access from the cold chemistry lab into containmen l Containment had been removed from the security controls associated with the protected i are .3 Conclusion j l

Required documents listed in Technical Specification 5.7.2 were ceafirmed to be available and current. Changes to the fire protection plan in Amendments 18 and 19 were reviewed and found acceptabl Radioactive Waste Treatment, Effluents and Environmental Monitoring (84750) and Review of Periodic and Special Reports (90713) l l Insoection Scooe  !

The licensee's Technical Specifications required the submittal to the NRC of several radiological and environmental reports. These reports were reviewed to determine if  ;

environmental conditions were consistent with previous levels and were within regulatory ]

limit .2 Observation and Findinas The Operational Ecological Monitorin<) Program Report, required by Technical Specification 5.4.1 of Appendix B to th license, documented nor.-radiological monitoring information for calendar year 1997. During the year, two non-routine National Pollution Discharge Elimination System (NPDES) reports were filed with the Oregon Department of Environmental Quality. The two discharges involved releases in which the pH was below the lower limit of 6.0 for approximately 10 minutes on each occasions. During 1997, no Environmental Protection Plan non-compliances occurred and no changes in station design or operations, tests, or experiments involving a significant unreviewed envirc7 mental issue were completed. On November 10,1997, PG&E received permission from the Oregon Department of Fish and Wildlife to eliminate the non-radiological ecological monitoring portion of the program since the plant was no l longer operational. This included the terrestrial and aquatic monitoring program The Annual Radiological Environmental Monitoring Report, required by Technical Specification 5.8.1.2, provided a summary of measured radiation levels in air, water, and soil around the Trojan plant for 1997. Samples collected included weekly air particulate, l quarterly thermoluminescent dosimetry (TLD) badges, quarterly well water samples, four . )

week composite drinking water samples, and shoreline soil samples taken twice a yea !

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-11-Radiation levels were consistent with levels recorded during 1996 and with natural background levels. One exception was TLD No.15.- This TLD, located on the east j industrial area fence, measured slightly higher levels of radiation due to the refueling

- water storage tanks and radioactive material stored onsite. The TLD averaged j

' 0.16 mR/ day compared to the site average of 0.0810.02 mR/ day and the average at the .

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I licensee's offsite controllocations of 0.09t0.02 mR/ day. The report also provided the ' !

results of the U.S. Environmental Protection Agency (EPA) and Department of

. Ener0y (DOE) interlaboratory comparison program evaluation conducted with the licensee's contract environmental analysis laboratory.' Results indicated good correlation -

for water, soil, and filter samples. All areas passed the eva!uatio The Radioactive Release Effluent Report, required by Technical Specification 5.8.1.3, provided a summary of radiological releases for 1997. For liquids, there were 15 batch releases in 1997. This compares with 13 batch releases in 1996. The releases were a small fraction of allowable release limits and were consistent with 1996 levels, except for tritium. Tritium was slightly higher than 1996 due to pool clean-up activities, but was still I well below release limits. For solid radwaste, 50 shipments to U.S. Ecology at Hanford, Washington, were made in 1997, This compared to 44 shipments in 199 ]

Approximately 24 curies were buried in 1997 compared to 355 curies in 199 , Conclusion - l The licensee had submitted the required 1997 radiological and environmental reports to the NRC Radiological levels around the plant were at background levels except for one location near an area where radioactive material was stored onsite. Liquid radiological

. releases from the plant were a small fraction of regulatory limits.' Solid radwaste .

shipments in 1997 were comparable to the number of shipments in 1996 but contained a I

? significantly lower total curie conten . 7- Follow-up on Corrective Actions for Violations (92702)

(Discussed) Violation 50-344/9703-01f Failure to Perform Adecuate Survev ,

Follow-uo item 50-344/9704-01. Corrective Actions-Survevs. and~

i Violation 50-344/9705-01: Free Release of Contaminated Material: The issues )

concerning the use of the CM-11 survey instrument and the free release of contaminated material from the radiologically controlled area have been the subject of two violations ,

and one follow-up item. Corrective actions related to the violations were being )'

- completed as discussed in letters issued to the NRC by the licensee on November 26, t 1997, March 3,1998, and May 20,1998. Satisfactory progress was being made. The

_ licensee had comp!sted radiological surveys of approximately 65,000 items onsite and 1,700 items offsitef The offsite locations included several PG&E facilities that had

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received tools and equipment from Trojan after shutdown. Good records had been kept by PG&E concerning the transfer of surpiused Trojan items to several coal, gas, and hydroelectric facilities. Recovery of the items for survey was successfully accomplishe None of the tools and equipment released from Trojan were found to be contaminate . . _ _ _ ._ ____-_-___ _ __ _ _ _

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I-12-l For items sold to the public, no records were kept. Requests were made to Trojan plant supervisors to inform their employees to bring in any tools that they had bought from Trojan. Only one individual responded with several tools. None of the tools were found to have contaminatio For tools and equipment found during the onsite survey,78 items had detectable levels of contamination above the release limits specified in Trojan Procedure TPP 20-19,

" Release of Materials from Radiologically Controlled Areas". Twenty additionalitems were found with small but detectable levels of contamination below the limits in Trojan Procedure TPP 20-19. Items included swedgelock fittings, a hammer, wood planks, scaffolding poles, electrical cords, and an assortment of tools. All contamination found was fixed except for one shackle which had contaminated grecs The licensee had completed the majority of corrective actions related to the material release issues. Activities remaining included testing and placing a SAM-9 tool monitor in-service and resurveying a portion of the Independent Spent Fuel Storage Installation pad where scaffolding had been stored that was found to have fixed contamination. The !

tool monitor was undergoing testing including determination of the alarm point which I would indicate that contamination had been detected. All material being released from the radiologically controlled area required two independent surveys. One of these could be with the tool monitor, If either of the two surveys indicated contamination, then the materialwas not release The tool monitor alarm had been set at 5,000 disintegrations / minute (dpm). The alarm setpoint was slightly above background to avoid false alarms due to background

- radiation fluctuations. The tool monitor calculated a background level intemally which could be printed out. On the day of the evaluation, background was 285 counts /secon The tool monito'c's minimum detectable activity was determined to be 4885 dpm at this background level. The ' alarm point setting of 5000 dpm provided as close to minimum detectable levels as practical without resulting in excessive false alarms. This alarm setting was consistent with two other operating reactor facilities contacted by Trojan. A test specimen with very low contamination levels was placed in the tool monitor and resulted in an alar j

, The violations and follow-up item will remain open until all actions are completed by the licensee. The actions taken by the licensee to prevent the release of contaminated j

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material from the site and to verify that no contaminated material had been previously released from the site had been extensive and provided a good level of assurance that future problems should not occu Exit Meeting

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The inspector presented the inspection results to members of the licensee management at the exit meeting on June 4,1998. The licensee acknowledged the findings presente l

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-13-The licensee did not identify as proprietary any information provided to, or reviewed by, the inspecto .

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ATTACHMENT PARTIAL LIST OF PERSONS CONTACTED Licensee ,

l l K. Allison, ISFSI Loading Project Manager i A. Bowman, Radiation Protection Supervisor  !

J. Cooper, Emergency Preparedness Engineer M. Gatlin, Nuclear Security Manager G. Huey, Radiation Protection Technical Support Manager j T. Meek, Radiation Protection Manager H. Pate, Licensing Manager J. Reid, Quality Assurance T. E aling, Radiation Protection Supervisor S. Schnieder, Plant Operations Manager R. Thomson, Radiation Protection Supervisor M. Walden, Radiation Protection Supervisor 1 J. Vesik, Fire Protection Engineer i i State of Oreaon

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A. Bless, Resident inspector, Oregon Office of Energy J l

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INSPECTION PROCEDURES USED l l 36801 Organization, Management, and Cost Controls at Permanently Shutdown Reactors 40500 Effectiveness of Licensee Controls in Identifying, Resolving, and Preventing l Problems I 40801 Self-Assessments, Audits, and Correef Actions 60801

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Spent Fuel Pool Safety at Permanently snutdown Reactors l 71801 Decommissioning Performance and Status Review at Permanently Shutdown  !

Reactors 83750 Occupational Radiation Exposure 84750 Radioactive Waste Treatment, Effluents and Environmental Monitenng i 86700 Spent Fuel Pool Activities 90713 Review of Periodic and Special Reports l

92702 Follow-up on Corrective Actions for Violations f

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ITEMS OPENED, CLOSED, AND DISCUCSED

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i 50-344/9802-01 IFl notification letter of acceptance of the new SFP system -

l Closed None Discussed 50-344/9703-01 VIO failure to perform adequate surveys 50-344/9704-01 IFl follow corrective actions re: surveys 50-344/9705-01 VIO free release of contaminated material LIST OF ACRONYMS CFR Code of Federal Regulations ,i DOE U. S. Department of Energy l dpm disintegrations per minute 1

' EP U. S. Environmental Protection Agency NPDES- National Pollution and Discharge Effluent System ppm parts per million TLD Thermoluminescent Dosimetry

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