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U.S. NUCLEAR REGULATORY COMMISSION REGIONlli Docket Nos:  50-295; 50-304 License Nos:  DPR-39; DPR-48
          ,
Report No:  50-295/98010(DNMS); 50-304/98010(DNMS)
i Licensee:  Commonwealth Edison Company
,
Facility:  Zion Nuclear Plant, Units 1 and 2 Location:  101 Shiloh Boulevard Zion,IL 60099 Dates:  August 14, - October 8,1998 Inspectors:  J. E. House, Senior Radiation Specialist, DNMS  '
R. J. Leemon, Senior Resident. inspector, DNMS D. W. Nelson, Radiation Specialist, DNMS
,.
W. G. Snell, Health Physics Manager, DNMS L      J. R. Kniceley, Fuel Cycle Safeguards inspector, DNMS Approved By:  Bruce L. Jorgensen, Chief Decommissioning Branch Division of Nuclear Materials Safety 9811060142 981103 PDR ADOCK 05000295 G  PM
 
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        .
EXECUTIVE SUMMARY  l
      .
 
Zion Nuclear Plant, Units 1 and 2  J NRC Inspection Report 50-295/98010(DNMS); 50-304/98010(DNMS)
This routine decommissioning inspection covered aspects of licensee facility management and ,
        '
control, decommissioning support activities, spent fual safety,' and radiological safet Facility Manaaement and Control
<
  * . Excellent set'-assessments were being conducted which were identifying deficiencies and prompting timely corrective action e Fire protection and control of combustibles was good, e The plant's material condition and housekeeping remained good, and were being i monitored by plant managemen ,
Decommissionino Supoort Activities
  *- The material integrity of structures, systems and components necessary for the safe storage of spent fuel and conduct of safe decommissioning was being maintaine !
'
e Requirements of the. Physical Security Plan had been met, with effective security measures and training, adequate procedures, and functional equipmen * Maintenance and surveillance observed were properly performe Spent Fuel Safety e The spent fuel pool was operated safely and spent fuel integrity was maintained.
 
;        l e' Those systems that monitor and cool the spent fuel pool can accommodate conditions that would challenge fuel pool level or cooling and thus protect fuel integrit Radiological Safety
-
  * The radiological safety program was very good. Total dose for the Unit 2 fuel removal
,
project was considerably less than predicte * Shipment of the 72 new, unused Unit i fuel bundles to the vendor's facility was in compliance with NRC and DOT requirement .
?
i
 
2 Y
 
__ __ _ _ _ _ ___ . _
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l Report Details    )
I Summary of Plant Activities      I During the inspection period, equipment necessary for the safe storage of spent fuel and  i radioactive liquids was being monitored and maintained by the licensee. The plant was being 1 operated in the Safe Store (SAFESTOR) Mode of Decommissionin l Facility Management and Control General l
- The inspectors conducted reviews of ongoing plant activities and attended licensee .
meetings and reviews that addressed these activities, in order to assess overall facility l management and controls. Specific events and findings are detailed in the sections belo .2 Self-Assessment. Auditina and Corrective Actions Insoection ScoDe (40801)
The licensee's controls for identifying, resolving and preventing issues that degrade safety or quality were examined, including audits, field monitoring, self-assessments and corrective actions. The program's ability to assure that the decommissioning program was conducted safely was reviewe " Observations and Findinas Audits and field inspection activities were carried out through the onsite Nuclear  l Oversight group, which reported directly to the Corporate Nuclear Oversight  '
organization. At the time of the inspection this group consisted of eight individuals. Due to the shutdown status of Zion, a new Quality Assurance (QA) program was being developed to address the facility's needs. It had not been determined whether there would be a stand alone decommissionirng QA manual for Zbn, or if a separate chapter ;
would be added to the existing Commonwealth Edison Company (Comed) QA manua Because of the changes that have occurred at Zion, the Nuclear Oversight staff was relying more on the Field Monitoring Program and the Field Inspections program instead of using formal audits to assess activities. The Nuclear Oversight group used a Monthiy Field Monitoring Schedule of specific assessment / inspection activities that were assigned to specific members of the group. In addition to this list, staff personnel were free to select from other areas of interest, as they chose, for addrtional assessment The inspector reviewed the results c( about 20 of these field inspections. The results indicated that the inspections were very thorough and detailed, identified deficiencies, insured that corrective actions were promptly initiated, and adequately documented the findings. The auditor, who focused on Health Physics (HP) retrated issues, indicated he was spending about 25 percent of his time in the field talking with management and workers, and observing activities in progres The inspector also reviewed the HP, As-Low-As Reasonably-i,chievable (ALARA),
Packaging and Transportation of Radioactive Material, and Process Control Programs
 
. -- - - - - - . -  .- _ . - . . ._- - --  -----
'
 
Audit Report (Comed-98-02) and the Emergency Preparedness (EP), Radiological  j Environmental Monitoring Program (REMP) and Offsite Dose Calculation Manual  l (ODCM) Audit Report (Comed-98-03). These were formal audits that had been carried j out at all six Comed nuclear plants and the Corporate organizations. These audits were broad in scope and of good depth, identified many deficiencies and adverse trends, and I provided numerous recommendations for program improvement Self-assessments were also performed within the Radiation Protection (RP)
Department. These were not dictated by a procedural requirement, but were initiated based on a perceived need to strengthen an area. Issues that were deemed particularly important were placed on the Zion Nuclear Tracking System for a more formal followu One of the areas emphasized in recent assessments addressed the reduction of required equipment and procedures related to the shutdown of Zion. Additional areas for assessment scheduled for the remainder of 1908 includsd the portal monitors (PM-7s), dosimetry, posting and labeling, and radioactive material contro I Conclusions
  - The scope, depth and breath of the audits and set-assessments was excellen Considerable effort was being invested to improve program activities from the big issues to the smaller job specific practices. At all levels, the assessments were identifying deficiencies that needed to be addressed as well as highlighting strengths that should be continued. A timely and acceptable response to identified deficiencies was also eviden .3 Decommissionina Performance and Status Review at Permanentiv Shut Down Reactors Inspection Scooe (718@
Plant tours were conducted to evaluate the material integrity of Structures, Systems and Components (SSCs) necessary for the safe storage of spent fuel and conduct of safe decommissioning. Facility housekeeping and field conditions were assessed for their contribution to safe decommissioning. This included the storage of combustible and flammable materials. The effectiveness of the site fire brigade was assessed during a fire brigade training drill, Observations and Findinas The results of plant tours and discussions of the findings with licensee representatives indicated that the material integrity of SSCs of systems important for the safe storage of spent fuel was being maintained, and that licensee management was actively monitoring plant material conditions. Observations focused on the areas adjacent to and containing SSCs necessary for the safe storage of spent fuel, radiological effluent control, and radiation protection and monitoring. The plant was clean and free of debris accumulation. The storage of combustible and flammable materials was within the fire loading limits for transient combustibles, and combustible materials were not
'
accumulating in the plant. The licensee had removed oils from non-needed pump motors which reduced the fire hazard. The rooms where the motors were located were then changed from fire areas to non-fire areas. This enabled the licensee to reduce the number of fire watch personnel. Fire fighting equipment and stations were properly
 
  . _  _ - _ _ .
      - _ . --
 
. -- . - _- - _~_-  _. -.- - _ . _ - - . _ - . _ - - - - -
- maintained and ready for use. Installed fire detection and suppression systems were effectively rnaintained, and the equipment was capable of performing the intended functlons. The inspector also verified the staffing of the site fire brigad Conclusions The material integrity of SSCs necessary for the safe storage of spent fuel and conduct of safe decommissioning was being maintained. Housekeeping was good, and was  1 being monitored by plant management. Storage of combustible material, operation of  j fire equipment, and staffing of the fire brigade were being monitored and maintaine l The removal of oils from non-needed pump motors had reduced the site fire hazar .4 Orisite Followuo. Written Reports of Non-routine Events at Power Reactor Facilities (92700)
        !
1.4.1 (Closed) LER 50-295/97022: Non-Safety Heating System Affects Control Room Habitability. In a letter to the NRC dated August 28,1998, the licensee submitted Licensee Event Report (LER) 97-022, Supplement 1. The licensee performed a ventilation system test and concluded that the control room would remain at a design basis positive pressure with respect to the adjacent areas at all times in the recirculation mode of operation. This LER is close ; Decommissioning Support Activities 1 Maintenance and Surveillance at Permanentiv Shut Down R6 actors Inspection Scope (62801)
The inspectors evaluated maintenance and surveillance of SSCs that could affect the safe storage of spent fuel and reliable operation of radiation monitoring and effluent  ,
        '
control equipment. Direct observations, reviews, and interviews of licensee personnel were conducted to assess whether maintenance and surveillance were performed in accordance with regulatory requirements and had resulted in the safe storage of spent fue Observations and Findinas
        .
The following surveillances and work requests were observed / reviewe PT 6E Procedure for sampling the refueling water storage tan PT-14 T/S related inoperable equipment test shee PT-11-E-2A 2A diesel generator (DG) cylinder liner test. The test conducted on September 2,1998, resulted in about one-half gallon of water being found in the 8-left-cylinder. The 2A DG was declared inoperable and non-functiona Work Request 970092281  Inspect and clean 1B DG lube oil cooler Work Request 970011325  Inspect and clean 1B DG Jacket water cooler
 
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Some corrosion deposits were found with none blocking the cooler. No Zebra Mussels were found in the coolers.
 
i Conclusions l          l Proper maintenance and surveillance practices were performed for the activities
          {
l  observe ~
l 2'.2 Safeauards Proaram implementation Insoection Scope (81700)  ,    j The inspector reviewed the Zion Safeguards Program to determine whether physical i <
security requirements were implemented in -accordance with the requirennents of the    !
,
Physical Security Plan (PSP) and site security procedure i i Observations and Findinos To determine if the security program was adequately being implemented the inspector toured the Owner Controlled Area, Protected Area (PA) and Vital Areas and observed the integrity of the fences, gates, alarm systems and the vehicle barriers. Fences, gates, assessment and detection systems, and the vehicle barriers were intact, adequately maintained and operable. Access control search equipment was adequately utilized and functioned as required. Personnel requiring access were identified, badged, and escorted as required. Packages and vehicles were inspected by security officers at the entrance to the PA as required by the PSP. Security force manning levels were maintained as required by the PS !
          '
All the officers were armed with a handgun and equipped with a radio. The inspector witnessed radio tests and concluded that there was appropriate communication capability within the PA. . Equipment observed within the alarm stations and the Main Access Facility funchoned as designed and was adequately manned. Maintenance .
support for security equipment seemed timely and adequat The inspector also interviewed officers posted and on patrol and found them to be knowledgeable of their duties and responsibilities. Security procedures were reviewed and updated as required, and located at the appropriate locations. The inspector reviewed selected security procedures, post orders, and other security documents pertaining to security performance and determined that they were adequately being maintained. The security procedures provided adequate guidance for security officer dutie The licensee's semi-annual Fitness For Duty Performance Data Report for the Zion Plant for the first period of 1998 was reviewed. Appropriate reports and actions were taken.
 
b Conclusions
  . Through observations, interviews, independent verification and records review the inspectors verified that the licensee was in compliance with PSP commitments.
 
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The inspectors concluded that security measures are effectively in place, procedures 1 were adequate, training was effective and that the licensee was meeting the  !
I  requirements of the PSP. Security equipment functioned as designed and procedures l  and post orders reviewed were adequate,    j i Spent Fuel Safety Spent Fuel Pool Safety at Permanently Shut Down Reacton  l a. Insoection Scope (60801)
Factors consioered in the evaluation of spent fuel and fuel pool safety included: Spent Fuel Pool (SFP) heat up rate; SFP instrumentation, alarms, and leakage detection; SFP 1 i-  chemistry and cleanliness control; criticality controls; and SFP cooling local valve lineup, I operation and power supply. The inspector reviewed station logs and discussed spent fuel pool safety with the license b. Observations and Findinas The inspector reviewed the shift supervisor status board, control room logs containing SFP parameters and locally monitored SFP temperature, level, and valve positions. The inspector verified that no leakage was coming from the SFP liner and that the SFP area criticality monitor was functioning. The inspector also observed that foreign material ,
controls were being used in and around the SFP During a tour of the SFP, the  l
        '
inspector observed that the SFP temperature was 87.5* F and the SFP level was 615.5 feet. The calculated time to boil on loss of all forced cooling to the SFP was about 50 hours. The operators would have about 50 hours to retum forced cooling to the SF c. Conclusions The safety of the fuel in the SFP was being maintained by design provisions and equipment and process controls to ensure cooling, shielding and monitorin .0 Radiological Safety Removal of New Unit 2 Fuel from the SFP a. Insoection Scooe (83750)
The inspectors reviewed the Radiation Work Permit dose totals for the Unit 2 fuel removal projec b. Observations and Findinas The total dose for the Unit 2 fuel removal project as of September 17,1998, was 341 millirem (3.41 millisievert). That dose included mock-up training, the cleaning and transfer of the fuel assemblies and the decontamination of one contaminated fuel (  assembly. Since the original dose budget for the project was 700 millrem (7.0 millisievert), the final project was approximately 360 millirem (3.6 milliselvert) under
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budge l
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In Inspection Report 50-304 and 295/98009 the planning and execution of the fuel removal project was characterized as being "very good." The dose results from the project support that find:n Conclusions The dose results for the Unit 2 fuel removal project indicated very good planning,
      '
preparation and exe'cution of the projec .2 Transoortation of Unit 1 New Fuel Inspection Scope (86750)
The inspectors reviewed the documents generated for six shipments of 72 new unused
' Unit i fuel assemblies from Zion to Westinghouse Electric Corporation Nuclear Fuel Division, Columbia, South Carolina. In addition, the training records for the Shipp!ng Coordinator, the person responsible for all radiological shipments from the facility, were reviewe Qbgentations and Findinas On June 2,5,10,16,19 and 23,1998, Westinghouse Electric Corporation shipped new Unit 1 fuel assemblies from Zion to its Nuclear Fuel Division in Columbia, South Carolina. In total there were 72 new unused fuel assemblies shipped. All six shipments arrived at the Columbia facility without inciden A review of the shipping documents indicated that Westinghouse had taken possession of the fuel assemblies at the Zion facility and had shipped the assemblies to Columbia, -
South Carolina. Since Westinghouse was the shipper of record, the Zion Shipping Coordinator limited his involvement in the shipments to providing radiation protection services (surveying), inspecting the transport vehicles and reviewing the official shipping documents. No problems were noted in the shipping documents by the Shipping Coordinator or the NRC inspector The inspectors asked for, and received a copy of Westinghouse's license. The inspectors noted, in the license, that Westinghouse was authorized to take possession of the fuel assemblies at the Zion facilit The inspectors reviewed the training rrcords s of the Shipping Coordinator. The records indicated that the Coordinator's hazardous materials shipping training was in full compliance with tne Department of Transportation (DOT) and NRC requirements . Conclusions No problems were noted in the shipping documents prepared for the shipment of 72 new unused Unit 1 fuel assemblies from the Zion facility to the Westinghouse facility in Columbia, South Carolina. Westinghouse Electric Corporation appeared to be in compliance with its license when its representatives took possession of the fuel at the Zion facility. The Shipping Coordinator's hazardous materials shipping training were in compliance with DOT as well as NRC requirement .. . .. . .. ._ _ . . _ . - - - _ - . _ . . - - _ . _ . . - . . . -.
. Exit Meeting Summary      l
. The lead inspector presented the inspection results to members of licensee management at the conclusion of the inspection on October 8,1998. The licensee acknowledged the findings
, presented. The licensee did not identify any of the documents or processes reviewed by the inspectors as proprietar 'l
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:
PARTIAL LIST OF PERSONS CONTACTED D. Bump, Maintenance and Rad / Chem Manager R. Godley, Manager, Regulatory Assurance M. Jeisy, QC Inspector _ . .
R. LaBum, Radiation Protection Manager R. Lane NGG Security Manager
.
~ H. Logaras, Corrective Actions Specialist D. Murphy, Lead Auditor .
B. Saunders, NGG Security R. Schuster, Rad / Chem Superviso R. Starkey, Station Manager J. Waters, Regulatory Assurance M. Wegemer, Lead Auditor LJ. Zeszutek, Regulatory Assurance INSPECTION PROCEDURES USED IP 36801: Organization, Management, and Cost Controls at Permanently Shut Down Reactors IP 37801: Safety Review, Design Changes, and Modifications at Permanently Shut Down Reactors-IP 60801: Spent Fuel Pool Safety at Permanently Shut Down Reactors IP 62801: Maintenance and Surveillance at Permanently Shut Down Reactors -
IP 71707: Operational Safety Verification
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IP 71801: Decommissioning Performance and Status Review at Permanently Shut Down Reactors IP 81700: Physical Security IP 83728: Maintaining Occupational Exposures ALARA IP 83750: . Occupational Radiation Exposure
'
. lP 84750: Radweste Treatment, Effluent and Environmental Monitoring IP 86750: Solid Radweste Management and Transportation of Radioactive Materials
- IP g2700: Onsite Followup, Written Reports or Non-routine Events at Power Reactor Facilities ITEMS OPENED, CLOSED AND DISCUSSED Opened t
None Closed LER 50-295/97022 Non-safety heating system that affects control room habitability
.
 
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  ' DOCUMENTS REVIEWED l
Health Physics (HP), As-Low-As-Reasonably-Achievable (ALARA), Packaging and Transportation of Radioactive Material, and Process Control Programs Audit Report Commonwealth Edison Company (Comed-98-02)
Emergency Preparedness (EP), Radiological Environmental Monitoring Program (REMP) and Offsite Dose Calculation Manual (ODCM) Audit Report (Comed-98-03)
Comed Quality Assurance Manual, January 23,1998 Fitness For Duty Performance Data Reports - First Quarter 1998 Off-Shift Training Roster for Fire Watch Training - 6/19-22/98-Zion Physical Security Plan, Revision 43, dated October 1997 Zion Security Post Orders (ZSPOs)
Monthly Security Barrier inspections,-January - July 1998 Ingress Equipment Daily Operational /Perfc.mance Tests, January - July 1998 Explosive Detector Daily Performance Tests, January - July 1998 Shift Supervisors Daily Checklist, January - July 1998
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Latest revision as of 12:47, 17 December 2020

Insp Repts 50-295/98-10 & 50-304/98-10 on 980814-1008.No Violations Noted.Major Areas Inspected:Facility Mgt & Control,Decommissioning Support Activities,Sf Safety & Radiological Safety
ML20155F883
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 11/03/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20155F877 List:
References
50-295-98-10, 50-304-98-10, NUDOCS 9811060142
Download: ML20155F883 (11)


Text

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U.S. NUCLEAR REGULATORY COMMISSION REGIONlli Docket Nos: 50-295; 50-304 License Nos: DPR-39; DPR-48

,

Report No: 50-295/98010(DNMS); 50-304/98010(DNMS)

i Licensee: Commonwealth Edison Company

,

Facility: Zion Nuclear Plant, Units 1 and 2 Location: 101 Shiloh Boulevard Zion,IL 60099 Dates: August 14, - October 8,1998 Inspectors: J. E. House, Senior Radiation Specialist, DNMS '

R. J. Leemon, Senior Resident. inspector, DNMS D. W. Nelson, Radiation Specialist, DNMS

,.

W. G. Snell, Health Physics Manager, DNMS L J. R. Kniceley, Fuel Cycle Safeguards inspector, DNMS Approved By: Bruce L. Jorgensen, Chief Decommissioning Branch Division of Nuclear Materials Safety 9811060142 981103 PDR ADOCK 05000295 G PM

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. .. . _ . . _ . _ . - _ _ . . _ . _ . _ _ _ . _ . _ _ _ _ . . . . . . . _ . _ _ - _ _ _ '

I

.

EXECUTIVE SUMMARY l

.

Zion Nuclear Plant, Units 1 and 2 J NRC Inspection Report 50-295/98010(DNMS); 50-304/98010(DNMS)

This routine decommissioning inspection covered aspects of licensee facility management and ,

'

control, decommissioning support activities, spent fual safety,' and radiological safet Facility Manaaement and Control

<

  • . Excellent set'-assessments were being conducted which were identifying deficiencies and prompting timely corrective action e Fire protection and control of combustibles was good, e The plant's material condition and housekeeping remained good, and were being i monitored by plant managemen ,

Decommissionino Supoort Activities

  • - The material integrity of structures, systems and components necessary for the safe storage of spent fuel and conduct of safe decommissioning was being maintaine !

'

e Requirements of the. Physical Security Plan had been met, with effective security measures and training, adequate procedures, and functional equipmen * Maintenance and surveillance observed were properly performe Spent Fuel Safety e The spent fuel pool was operated safely and spent fuel integrity was maintained.

l e' Those systems that monitor and cool the spent fuel pool can accommodate conditions that would challenge fuel pool level or cooling and thus protect fuel integrit Radiological Safety

-

  • The radiological safety program was very good. Total dose for the Unit 2 fuel removal

,

project was considerably less than predicte * Shipment of the 72 new, unused Unit i fuel bundles to the vendor's facility was in compliance with NRC and DOT requirement .

?

i

2 Y

__ __ _ _ _ _ ___ . _

'

l Report Details )

I Summary of Plant Activities I During the inspection period, equipment necessary for the safe storage of spent fuel and i radioactive liquids was being monitored and maintained by the licensee. The plant was being 1 operated in the Safe Store (SAFESTOR) Mode of Decommissionin l Facility Management and Control General l

- The inspectors conducted reviews of ongoing plant activities and attended licensee .

meetings and reviews that addressed these activities, in order to assess overall facility l management and controls. Specific events and findings are detailed in the sections belo .2 Self-Assessment. Auditina and Corrective Actions Insoection ScoDe (40801)

The licensee's controls for identifying, resolving and preventing issues that degrade safety or quality were examined, including audits, field monitoring, self-assessments and corrective actions. The program's ability to assure that the decommissioning program was conducted safely was reviewe " Observations and Findinas Audits and field inspection activities were carried out through the onsite Nuclear l Oversight group, which reported directly to the Corporate Nuclear Oversight '

organization. At the time of the inspection this group consisted of eight individuals. Due to the shutdown status of Zion, a new Quality Assurance (QA) program was being developed to address the facility's needs. It had not been determined whether there would be a stand alone decommissionirng QA manual for Zbn, or if a separate chapter ;

would be added to the existing Commonwealth Edison Company (Comed) QA manua Because of the changes that have occurred at Zion, the Nuclear Oversight staff was relying more on the Field Monitoring Program and the Field Inspections program instead of using formal audits to assess activities. The Nuclear Oversight group used a Monthiy Field Monitoring Schedule of specific assessment / inspection activities that were assigned to specific members of the group. In addition to this list, staff personnel were free to select from other areas of interest, as they chose, for addrtional assessment The inspector reviewed the results c( about 20 of these field inspections. The results indicated that the inspections were very thorough and detailed, identified deficiencies, insured that corrective actions were promptly initiated, and adequately documented the findings. The auditor, who focused on Health Physics (HP) retrated issues, indicated he was spending about 25 percent of his time in the field talking with management and workers, and observing activities in progres The inspector also reviewed the HP, As-Low-As Reasonably-i,chievable (ALARA),

Packaging and Transportation of Radioactive Material, and Process Control Programs

. -- - - - - - . - .- _ . - . . ._- - -- -----

'

Audit Report (Comed-98-02) and the Emergency Preparedness (EP), Radiological j Environmental Monitoring Program (REMP) and Offsite Dose Calculation Manual l (ODCM) Audit Report (Comed-98-03). These were formal audits that had been carried j out at all six Comed nuclear plants and the Corporate organizations. These audits were broad in scope and of good depth, identified many deficiencies and adverse trends, and I provided numerous recommendations for program improvement Self-assessments were also performed within the Radiation Protection (RP)

Department. These were not dictated by a procedural requirement, but were initiated based on a perceived need to strengthen an area. Issues that were deemed particularly important were placed on the Zion Nuclear Tracking System for a more formal followu One of the areas emphasized in recent assessments addressed the reduction of required equipment and procedures related to the shutdown of Zion. Additional areas for assessment scheduled for the remainder of 1908 includsd the portal monitors (PM-7s), dosimetry, posting and labeling, and radioactive material contro I Conclusions

- The scope, depth and breath of the audits and set-assessments was excellen Considerable effort was being invested to improve program activities from the big issues to the smaller job specific practices. At all levels, the assessments were identifying deficiencies that needed to be addressed as well as highlighting strengths that should be continued. A timely and acceptable response to identified deficiencies was also eviden .3 Decommissionina Performance and Status Review at Permanentiv Shut Down Reactors Inspection Scooe (718@

Plant tours were conducted to evaluate the material integrity of Structures, Systems and Components (SSCs) necessary for the safe storage of spent fuel and conduct of safe decommissioning. Facility housekeeping and field conditions were assessed for their contribution to safe decommissioning. This included the storage of combustible and flammable materials. The effectiveness of the site fire brigade was assessed during a fire brigade training drill, Observations and Findinas The results of plant tours and discussions of the findings with licensee representatives indicated that the material integrity of SSCs of systems important for the safe storage of spent fuel was being maintained, and that licensee management was actively monitoring plant material conditions. Observations focused on the areas adjacent to and containing SSCs necessary for the safe storage of spent fuel, radiological effluent control, and radiation protection and monitoring. The plant was clean and free of debris accumulation. The storage of combustible and flammable materials was within the fire loading limits for transient combustibles, and combustible materials were not

'

accumulating in the plant. The licensee had removed oils from non-needed pump motors which reduced the fire hazard. The rooms where the motors were located were then changed from fire areas to non-fire areas. This enabled the licensee to reduce the number of fire watch personnel. Fire fighting equipment and stations were properly

. _ _ - _ _ .

- _ . --

. -- . - _- - _~_- _. -.- - _ . _ - - . _ - . _ - - - - -

- maintained and ready for use. Installed fire detection and suppression systems were effectively rnaintained, and the equipment was capable of performing the intended functlons. The inspector also verified the staffing of the site fire brigad Conclusions The material integrity of SSCs necessary for the safe storage of spent fuel and conduct of safe decommissioning was being maintained. Housekeeping was good, and was 1 being monitored by plant management. Storage of combustible material, operation of j fire equipment, and staffing of the fire brigade were being monitored and maintaine l The removal of oils from non-needed pump motors had reduced the site fire hazar .4 Orisite Followuo. Written Reports of Non-routine Events at Power Reactor Facilities (92700)

!

1.4.1 (Closed) LER 50-295/97022: Non-Safety Heating System Affects Control Room Habitability. In a letter to the NRC dated August 28,1998, the licensee submitted Licensee Event Report (LER)97-022, Supplement 1. The licensee performed a ventilation system test and concluded that the control room would remain at a design basis positive pressure with respect to the adjacent areas at all times in the recirculation mode of operation. This LER is close ; Decommissioning Support Activities 1 Maintenance and Surveillance at Permanentiv Shut Down R6 actors Inspection Scope (62801)

The inspectors evaluated maintenance and surveillance of SSCs that could affect the safe storage of spent fuel and reliable operation of radiation monitoring and effluent ,

'

control equipment. Direct observations, reviews, and interviews of licensee personnel were conducted to assess whether maintenance and surveillance were performed in accordance with regulatory requirements and had resulted in the safe storage of spent fue Observations and Findinas

.

The following surveillances and work requests were observed / reviewe PT 6E Procedure for sampling the refueling water storage tan PT-14 T/S related inoperable equipment test shee PT-11-E-2A 2A diesel generator (DG) cylinder liner test. The test conducted on September 2,1998, resulted in about one-half gallon of water being found in the 8-left-cylinder. The 2A DG was declared inoperable and non-functiona Work Request 970092281 Inspect and clean 1B DG lube oil cooler Work Request 970011325 Inspect and clean 1B DG Jacket water cooler

_ _ _ _ . _ _ _ . _ _ . . . _ _ . . _ . _ . . _ . . _ _ _ . _ . _ _ _ . . _ . _ _ _ _ . _ _ _

c

l

'

Some corrosion deposits were found with none blocking the cooler. No Zebra Mussels were found in the coolers.

i Conclusions l l Proper maintenance and surveillance practices were performed for the activities

{

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l 2'.2 Safeauards Proaram implementation Insoection Scope (81700) , j The inspector reviewed the Zion Safeguards Program to determine whether physical i <

security requirements were implemented in -accordance with the requirennents of the  !

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Physical Security Plan (PSP) and site security procedure i i Observations and Findinos To determine if the security program was adequately being implemented the inspector toured the Owner Controlled Area, Protected Area (PA) and Vital Areas and observed the integrity of the fences, gates, alarm systems and the vehicle barriers. Fences, gates, assessment and detection systems, and the vehicle barriers were intact, adequately maintained and operable. Access control search equipment was adequately utilized and functioned as required. Personnel requiring access were identified, badged, and escorted as required. Packages and vehicles were inspected by security officers at the entrance to the PA as required by the PSP. Security force manning levels were maintained as required by the PS !

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All the officers were armed with a handgun and equipped with a radio. The inspector witnessed radio tests and concluded that there was appropriate communication capability within the PA. . Equipment observed within the alarm stations and the Main Access Facility funchoned as designed and was adequately manned. Maintenance .

support for security equipment seemed timely and adequat The inspector also interviewed officers posted and on patrol and found them to be knowledgeable of their duties and responsibilities. Security procedures were reviewed and updated as required, and located at the appropriate locations. The inspector reviewed selected security procedures, post orders, and other security documents pertaining to security performance and determined that they were adequately being maintained. The security procedures provided adequate guidance for security officer dutie The licensee's semi-annual Fitness For Duty Performance Data Report for the Zion Plant for the first period of 1998 was reviewed. Appropriate reports and actions were taken.

b Conclusions

. Through observations, interviews, independent verification and records review the inspectors verified that the licensee was in compliance with PSP commitments.

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The inspectors concluded that security measures are effectively in place, procedures 1 were adequate, training was effective and that the licensee was meeting the  !

I requirements of the PSP. Security equipment functioned as designed and procedures l and post orders reviewed were adequate, j i Spent Fuel Safety Spent Fuel Pool Safety at Permanently Shut Down Reacton l a. Insoection Scope (60801)

Factors consioered in the evaluation of spent fuel and fuel pool safety included: Spent Fuel Pool (SFP) heat up rate; SFP instrumentation, alarms, and leakage detection; SFP 1 i- chemistry and cleanliness control; criticality controls; and SFP cooling local valve lineup, I operation and power supply. The inspector reviewed station logs and discussed spent fuel pool safety with the license b. Observations and Findinas The inspector reviewed the shift supervisor status board, control room logs containing SFP parameters and locally monitored SFP temperature, level, and valve positions. The inspector verified that no leakage was coming from the SFP liner and that the SFP area criticality monitor was functioning. The inspector also observed that foreign material ,

controls were being used in and around the SFP During a tour of the SFP, the l

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inspector observed that the SFP temperature was 87.5* F and the SFP level was 615.5 feet. The calculated time to boil on loss of all forced cooling to the SFP was about 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. The operators would have about 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> to retum forced cooling to the SF c. Conclusions The safety of the fuel in the SFP was being maintained by design provisions and equipment and process controls to ensure cooling, shielding and monitorin .0 Radiological Safety Removal of New Unit 2 Fuel from the SFP a. Insoection Scooe (83750)

The inspectors reviewed the Radiation Work Permit dose totals for the Unit 2 fuel removal projec b. Observations and Findinas The total dose for the Unit 2 fuel removal project as of September 17,1998, was 341 millirem (3.41 millisievert). That dose included mock-up training, the cleaning and transfer of the fuel assemblies and the decontamination of one contaminated fuel ( assembly. Since the original dose budget for the project was 700 millrem (7.0 millisievert), the final project was approximately 360 millirem (3.6 milliselvert) under

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In Inspection Report 50-304 and 295/98009 the planning and execution of the fuel removal project was characterized as being "very good." The dose results from the project support that find:n Conclusions The dose results for the Unit 2 fuel removal project indicated very good planning,

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preparation and exe'cution of the projec .2 Transoortation of Unit 1 New Fuel Inspection Scope (86750)

The inspectors reviewed the documents generated for six shipments of 72 new unused

' Unit i fuel assemblies from Zion to Westinghouse Electric Corporation Nuclear Fuel Division, Columbia, South Carolina. In addition, the training records for the Shipp!ng Coordinator, the person responsible for all radiological shipments from the facility, were reviewe Qbgentations and Findinas On June 2,5,10,16,19 and 23,1998, Westinghouse Electric Corporation shipped new Unit 1 fuel assemblies from Zion to its Nuclear Fuel Division in Columbia, South Carolina. In total there were 72 new unused fuel assemblies shipped. All six shipments arrived at the Columbia facility without inciden A review of the shipping documents indicated that Westinghouse had taken possession of the fuel assemblies at the Zion facility and had shipped the assemblies to Columbia, -

South Carolina. Since Westinghouse was the shipper of record, the Zion Shipping Coordinator limited his involvement in the shipments to providing radiation protection services (surveying), inspecting the transport vehicles and reviewing the official shipping documents. No problems were noted in the shipping documents by the Shipping Coordinator or the NRC inspector The inspectors asked for, and received a copy of Westinghouse's license. The inspectors noted, in the license, that Westinghouse was authorized to take possession of the fuel assemblies at the Zion facilit The inspectors reviewed the training rrcords s of the Shipping Coordinator. The records indicated that the Coordinator's hazardous materials shipping training was in full compliance with tne Department of Transportation (DOT) and NRC requirements . Conclusions No problems were noted in the shipping documents prepared for the shipment of 72 new unused Unit 1 fuel assemblies from the Zion facility to the Westinghouse facility in Columbia, South Carolina. Westinghouse Electric Corporation appeared to be in compliance with its license when its representatives took possession of the fuel at the Zion facility. The Shipping Coordinator's hazardous materials shipping training were in compliance with DOT as well as NRC requirement .. . .. . .. ._ _ . . _ . - - - _ - . _ . . - - _ . _ . . - . . . -.

. Exit Meeting Summary l

. The lead inspector presented the inspection results to members of licensee management at the conclusion of the inspection on October 8,1998. The licensee acknowledged the findings

, presented. The licensee did not identify any of the documents or processes reviewed by the inspectors as proprietar 'l

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PARTIAL LIST OF PERSONS CONTACTED D. Bump, Maintenance and Rad / Chem Manager R. Godley, Manager, Regulatory Assurance M. Jeisy, QC Inspector _ . .

R. LaBum, Radiation Protection Manager R. Lane NGG Security Manager

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~ H. Logaras, Corrective Actions Specialist D. Murphy, Lead Auditor .

B. Saunders, NGG Security R. Schuster, Rad / Chem Superviso R. Starkey, Station Manager J. Waters, Regulatory Assurance M. Wegemer, Lead Auditor LJ. Zeszutek, Regulatory Assurance INSPECTION PROCEDURES USED IP 36801: Organization, Management, and Cost Controls at Permanently Shut Down Reactors IP 37801: Safety Review, Design Changes, and Modifications at Permanently Shut Down Reactors-IP 60801: Spent Fuel Pool Safety at Permanently Shut Down Reactors IP 62801: Maintenance and Surveillance at Permanently Shut Down Reactors -

IP 71707: Operational Safety Verification

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IP 71801: Decommissioning Performance and Status Review at Permanently Shut Down Reactors IP 81700: Physical Security IP 83728: Maintaining Occupational Exposures ALARA IP 83750: . Occupational Radiation Exposure

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. lP 84750: Radweste Treatment, Effluent and Environmental Monitoring IP 86750: Solid Radweste Management and Transportation of Radioactive Materials

- IP g2700: Onsite Followup, Written Reports or Non-routine Events at Power Reactor Facilities ITEMS OPENED, CLOSED AND DISCUSSED Opened t

None Closed LER 50-295/97022 Non-safety heating system that affects control room habitability

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' DOCUMENTS REVIEWED l

Health Physics (HP), As-Low-As-Reasonably-Achievable (ALARA), Packaging and Transportation of Radioactive Material, and Process Control Programs Audit Report Commonwealth Edison Company (Comed-98-02)

Emergency Preparedness (EP), Radiological Environmental Monitoring Program (REMP) and Offsite Dose Calculation Manual (ODCM) Audit Report (Comed-98-03)

Comed Quality Assurance Manual, January 23,1998 Fitness For Duty Performance Data Reports - First Quarter 1998 Off-Shift Training Roster for Fire Watch Training - 6/19-22/98-Zion Physical Security Plan, Revision 43, dated October 1997 Zion Security Post Orders (ZSPOs)

Monthly Security Barrier inspections,-January - July 1998 Ingress Equipment Daily Operational /Perfc.mance Tests, January - July 1998 Explosive Detector Daily Performance Tests, January - July 1998 Shift Supervisors Daily Checklist, January - July 1998

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