ML20202J069

Revised LACBWR Decommissioning Plan

ML20202J069
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Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	01/31/1998
From:	DAIRYLAND POWER COOPERATIVE
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ML20202J042	List: ML20202J038 ML20202J069 ML20202J078
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NUDOCS 9802230075
Download: ML20202J069 (17)

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LA CROSSE BOILING WATER REACTOR (LACBWR)

DECOMMISSIONING PLAN Revised January 1998 DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR) 4601 State Road 35 Genoa, WI 54632-8846 c' $R DOCK O O O 09 W PDR

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3. FACILITY SITE CilARACTERISTICS -(cont'd)

, St. Louis, Missouri, is on the opposite side of the Mississippi River from the plant and was abandoned from 1980 to 1981. The line has since been restored to service but is not frequently .t used. State Trunk Highway 56 originates in the village of Genoa and runs East towards Viroqua, the county seat. The origin point for Highway 56 is approximately 1-1/2 miles north of the reactor plant.

On the Iowa and Minnesota side of the river, State Trunk Highway 26 mns within 4 miles of the original exclusion area. All the mentioned highway facilities are two-lane paved roadways with unlimited access.

The car count on the road (Highway 35) passing through the nuclear facility onginal exclusion area is 2,950 cars per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, as determined by the Vernon County Wisconsin Highway Department in 1984.

There does exist north on the plant, approximately .9 mile, a U.S. Army Corps of Engineers Lock and Dam on the Mississippi River. This lock is not classified as an industrial facility, although it employs approximately 11 individuals.

3.3 METEOROLOGY 3.3.1 Meteorological Measurement Program The LACBWR meteorological measurement program consists of onsite equipment located within the Mississippi River valley. Meteorological parameters monitored are wind speed, wind direction, and temperature. Data is also available from the National Weather Service (NWS),

approximately 35 km (21.7 mi.) north of LACBWR. l 3.3.2 Deneral Climatology The plant site area exhibits a typical cotitinental type of climate. Temperature extremes in the ,

La Crosse /LACBWR region are more marked because of the river-valley location. Average temperatures vary from -7. l*C (19.2 F) in the three months of winter to 21. C (71.4 F) in the summer months.' A maximum temperature of 42.2 C (108.0 ) was recorded in July 1936, with a minimum low of-41.7#C (-43.0"F) recorded in January 1873, both in La Crosse. Monthly precipitation in the area averages between 5.1 cm (2.0 in.) and 10.7 cm (4.2 in.) from March through October and 2.5 cm (1 in.) and 5.1 cm (2 in.) for the rest of the year. Awrage annual precipitation is 79.2 cm (31.2 in.). Monthly snow and sleet averages between 12.7 cm v in.) and 35.6 cm (14 in.) from November through March, the largest amount normally occurring during March. The normal annual amount of snow and sleet is 110.5 cm (43.5 in.).

D-PLAN 3-2 January 1998

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5. PLANT STATUS -(cont'd) 5.2.19 Station and Control Air Systeln There are two station air compressors, a single-stage compressor and a 2-stage compressor. The l single-stage compressor is a positive displacement lubricated type compressor which includes encapsulated compressor, fluid management system, motor section, and compressor cooling ,

system. The 2-stage compressor consists of essentially three parts: the low-pressure unit, the l high-pressure unit and the motor. Air from this compressor passes through an after-cooler and an oil separator to cool the air and to remove moisture and oil from the air before permitting it to enter the air receiver. One compressor is normally running, and the other compressor can be started when necessary. The air receivers act as a volume storage unit for the station.

The air recci"cr outlet lines join to form a header for supply to the station and the control air systems. Station air is provided to the Cribhouse, where it is piped to near the suction of the Low Pressure Service Water pumps; to ihe High Pressure Sersice Water tank to charge the tank; and to the generator and reactor plants at all floor levels, for station usage as needed.

Control air is supplied from the receiver discharge header through a control air prefilter, air filter, and Sullair air dryer, or through Dettech filters and Trinity air dryers to various instruments and valves in the reactor and generator plants, Alarms are previded in the Control Room to warn oflow control air header pressure, compressor breaker trip or low oillevelin IB Air Compressor.

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System Status This system is maintained and in continuous operation.

D-PLAN 5-21 January 1990 1

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5. PLANT STATUS -(cont'd)

. 5.2,29 IJe_atiDE3ntihtian.and Air-Conditioninglyfiems The Reactor Building ventilation system utilizes two 30-ton,12,000-cfm air conditioning units for drawing fresh air into the building and for circulating the air throughout the building. The air enters the Reactor Building through two 20-inch isolation dampers in series, and is exhausted from the building by a centrifugal exhaust fan which has a capacity of 6000 cfm at 4 inches of water static pressure. The exhaust fan discharges through two 20-inch isolation dampers in series to the tunnel.

A 20-inch damper is also provided for recirculation of the exhaust fan discharge air. The exhaust system is provided with conventional and high-efliciency filters and with a gaseous and particulate radiation monitor system.

The Waste Treatment Building ventilation is provided by a 2000-cfm exhaust fan that drav s air from the shielded vault areas of the building and exhausts the air through a duct out the floor of i the building to the waste gas storage vault. The stack blowers then exhaust the air from the waste gas storage vault through the connecting tunnel and discharge the air up the stack.

The exhaust air from the Reactor Building and from the Waste Treatment Building are discharged into the tunnel connecting the Waste Treatment Building, the Reactor Building, and the Turbine Building to a plenum at the base of the stack. The stack is 350 feet high and is of structural concrete with an aluminum nozzle at the top, The nozzle tapers to 4 feet 6 inches at the discharge, pioviding a stack exit velocity of approximately 70 fps with the two 35,000 cfm stack blowers in operation.

The Turbine Building heating system provides heat to the turbine and machine shop areas through unit heaters and through automatic steam heating units.

The Control Room Heating and Air-Conditioning unit serves the Control Room. Electrical Equipment Room, Shift Supervisor's area, and adjacent oflice. l The office area and laboratory are provided with a separate multi-zone heating and air-conditioning unit.

The heating boiler is a Cleaver-Brooks, Type 100 Model CB-189,150-hp unit. At 150 psig, the boiler will deliver 6,275,000 Btu /hr. The boiler fuel is No. 2 fuel oil. The oilis supplied by and atomized in a Type CB-1 burner which will deliver 45 gph.

Two 14.7 kW resistance heaters with power supplied from the essential busses are available to heat the Containment Building in the event normal heating is lost.

SystanLSlatus These systems are maintained operational and used as conditions require.

D-PLAN 5-31 January 1998

5. PLANT STATUS -(cont'd) 5.2.34.2 Stack Gas PASESyfkm Descriplom The Stack Gas Post-Accident i ampling System makes use of the same equipment that provides the normal stack gas sample flo w. The vacuum pump for stack gas sampling draws the extra flow, r%ve what the stack morn.' ors draw, to make the total flow isokinetic to the stack dischorge. This flow can be divened through the post-accident sample canister by opening manual isolation valves. The sample cei.Wer is connected to the system by two quick disconnects, and, therefore, can be easily removed from the system and taken to the laboratory for analysis. The sample canister diversion valve is controlled from the local control panel in the No. 3 Feedwater Heater area.

5.2.34.3 Reactor Coolant PASS Sysum Descriptiom The Reactor Coolant Post-Accident Sampling System takes primary coolant from an incore flux monitoring flushing connection, through 2 solenoid-operated isolation valves with a heat exchanger between them, to a motor-operated pressure reducing valve. Downstream of the pressure reducing valve, the coolant sample can be diluted with demineralized water which then flows through the sample cylinder or its bypass valve, through another solenoid isolation valve, and back to the Containment Building basement or to the waste water tanks.

System Status The Stack Gas PASS System is maintained in contia 2 operation. The Reactor Coolant PASS System is no longer needed. The Containment Atmo %re PASS System is retained in place.

5.2.35 Containment integrity Systems With the plant in the SAFSTOR condition, there is no longer a postulated accident that woula result in containment pressurization or that takes credit for Containment integrity.

System SWm Containment integrity systems are not required to be operable. l D-PLAN 5-38 January 1998

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5. PLANT STATUS -(cont'd)

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5.7.1.2 CoritaintncnlJ1pilding Air Exila]ELGa_1cous and Pallisp. late Monitor. A monitor is located on the Containment Building mez2.anine level. This monitor has a fixed filter particulate detector and a gaseous detector. It takes its suction from the outlet of the C.B. ventilation filters.

5.7.1.3 Sinsk Monitpl. A monitor is installed to sample the stack emissions. This monitor draws air from the stack through an isokinetic nozzle. This monitor detects particulate and gaseous activity released to the stack. This monitor alarms locally and in the control room.

5.7.1.4 Tizediacatienjdonjitols. Aiea radiation monitors are used to detect and measure gamma radiation fields at various remote locations. There are filleen remote units located throughout the plant. The measured dose rate is displayed on meters located in the Control Room.

5.7.2 P_o_ruhlp_ Monitors Portable instruments are located throuc'.iout the plant. Insu uments are available to detect various levels of beta, gamma, and alpha radiation.

5.7.3 Laboratorv-Type Monitors Laboratory instruments are available to determine contamination levels and radioisotope concentrations. These instmments consist ofintemal proportional counters, gamma analyzers, and liquid scintillation counters.

D-PLAN 5-45 January 1998

. 6. . DECOMMISSIONING PROGRAM 6.1 QEJECTIVES The primary objective of the Decommissioning Program at LACBWR will be to safely monitor the facility and prevent any unplanned release of radioactivity to the environment. Some of the goals during the SAFSTOR period are as follows:

+ To safely store activated fuel until it can be removed from the site.

• To establish a monitoring and surveillance program for comparison to baseline conditions.

+ To maintain systems required during the SAFSTOR period.

+ To lay up non-operating systems.

+ To salvage equipment that is no longer being used.

• To handle radioactive waste generated during the SAFSTOR period in accordance with plant procedures and applicable requirements.

+ To reduce generd area radiation levels in the vicinity of equipment operated or maintained during the S AFSTOR period to limit personnel dose to as low as reasonably achievable.

• To start decontaminating and dismantling unused systems while minimizing the generation of radioactive waste and personnel dose from this activity.

• Maintain qualified and trained stafTto fulfill these goals.

6.2 ORGANIZATION AND RESPONSIBILITIE_S The organization of the SAFSTOR stalTat LACBWR is as indicated in Figure 6-1. The staff may change as activities being perfu.ned vary and stalling needs change. The organization is directed by a Plant Manager, who reports directly to the Dairyland Power Cooperative Assistant General Manager for Generation. The individuals who report directly to the Plant Manager each have distinct ftmetions in insuring the safety of the facility during the SAFSTOR mode.

The Plant Manager is responsible for the safety of the facility, its daily operation and surveillance, long rarge planning, licensing and any of .er responsibilities which may come to light in long-term SAFSTOR operation. Quality assurance activities and security control and support are provided by a Cooperative-wide quality assurance and security program. The Plant Manager is responsible for operation of any onsite security required as well as insuring compliance with the quality assurance program.

D-PLAN 6-1 January 1998 i

6. DECOMMISSIONING PROGRAM -(cont'd)

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. responsible for coordinating the deve'opment in-house of the procedures necessary to totally dismantle the facility ence the fuel is shipped from site.

The Radiation Protection Engineer will be responsible for radiation protection, projections and trending. This engineer will be respcnsible for working with the IIealth and Safety Supervisor in preparing long-term prognosis for exposures and procedures necessary for decon, waste management, chemical control and fuel shipment. The Radiation Protection Engineer will assist in ,

ensuring that an aggressive ALARA program is carried out and that contamination and background radiation exposure is reduced as low as reasonably achicvable during the SAFSTOR period.

The Reactor Engineer will be responsible for all activities invoking the stored fuel and will assist with plans for eventual decommissioning of the facility. This engineer will be responsible for any required reports to be generated on the stored special nuclear material.

The Safety Review Committee will remain the OITsite Review Group responsible for oversight of facility activities. It will have a quorum of 4 persons including the chairman. No more than a minority of the quorum shall have line responsibility for operation of the facility. The SRC shall ineet at least once per year.

The Operations Review Committee (the Onsite Review Committee) will remain responsible for the review of day-to-day cperations it will consist of a quomm of at least 4 individuals drawn from the management stafTat the site. It is chaired by the Plant Manager. The Safety Review Committee and the Operations RcGw Committee will review all material as required by Technical Specifications including, but not limited to, facility changes, license amendments, and plan changes in Emergency Plan and Security Plan. The committees will also review any special tests.

6.3 CONTRACTOR USE The use of contrectors at LACBWR will continue as required throughout the SAUSTOR and DECON periods.

The use of contractors will be minimized and generally limited to areas of specialty which cannot be accomplished by Dairyland staff personnel. The use of contractors will be complementary in nature. It will highlight areas where DPC expertise or stafiing is inadequate to perform specific tasks without outside help.

Contractor employment for specific tasks, possibly including monitoring or evaluating the facility during the SAFSTOR or aiding in dismantlement or cleanup during the DECON, will continue to be governed by the requirements of the LACBWR Quality Assurance Program. l 1

D-PLAN 6-4 January 1998 )

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6. DECOMMISSIONING PROGRAM - (cont'd)

Contractors will be selected in each case on a basis of ability, price, past performance and regulatory requirements.

The licensee, Dairyland Power Cooperative, will retain full responsibility for the performance of contractor tasks and will provide the supervision nocessary to ensure that the tasks performed by contractors are in full compliance with the Quality Assurance Program, the purchase agreement and other appropriate regulations.

The use of contractors has the potential of aiding the LACBWR Decommissioning Project over the next 20+ years in certain select areas of unique expertise.

The ability to eaximize the benefit from contractors will be closely-tied to adherence to the principles stated in the Quality Assurance Program and other DPC purchasing policies and procedures.

6.4 TRAINING PROGRAM 6.4.1 Trainine Program Description 6.4.1,1 LACBWR has established General Employee Training (CET) requirements for all personnel who may be assigned to perform work at LACBWR.

6.4.1.2 In addition to GET, programs have been designed to initially qualify personnel, and waintain their proficiency, in the following areas:

a) Health Physics Technician (HPT) b) Operator c) Certified Fuel Handler (CFH) 6.4.1.3 - Special infrequently performed evolutions relating to decommission-ing activities may be included for training as they approach.- These evolutions may typically be:

a) Cash Handling b) Systems Internals and Equipment Decontamination and Dismantling c) Special Tests d) Any other evolution determined by plant management to require special training.

6.4.2 General Employee Trainine (CET) 6.4.2.1 All personnel either assigned to LACBWR, or who may be assigned duties at LACBWR, will receive CET commensurate with their assignment. This training will include, as appropriate:

a) ' Emergency Plan Training b) Security Plan Training c) Radiation Protection Training d) Quality Assurance Training e) Respiratory Protection Training f) Industrial Safety, First Aid, and Fire Protection D-PLAN 6-5 May 1991

6. DECOMMISSIONING PROGRAM -(cont'd)

. The LACBWR Spent Fuel (333 assemblies) is stored under water in the high density spent fuel storage racks in the LACBWR Fuel Storage Well which is located adjacent to the reactor in the LACBWR containment building.

Additional small quantities of SNM are contained in neutron and calibration sources and in fission detectors which are appropriately stored at various locations in the LACBWR plant.

All fuel handling and all shipment and receipt of SNM is accomplished according to approved written procedures. Appropriate accounting records will be maintained and appropriate inventories, reports and documentation will be accomplished by or under the direction of the LACBWR Accountability Representative in accordance with the requirements set forth in 10 CFR 70,10 CFR 73 and 10 CFR 74.

6.9 SAFSTOR FIRE PROTECTION PROGRAM 6.9.1 Program Administration 6.9.1.1 The LACBWR Plant Manager is responsible for the fire protection program. A member of the Dairyland technical staffis responsible for annual evaluation of equipment provided for fire fighting, training, and maintaining a current and effective fire protection program.

6.9.1.2 The training program for the Fire Response Team will be maintained under the direction -

of a designated stafTmember and will meet or exceed the requirements of Section 27 of the NFPA Code 1976.

6.9.1.3 The Fire Response Team will consist of a minimum of two (2) members. These j individuals will be available to respond in the event of a fire emergency at the LACBWR Unit.

The Fire Response Team Leader will be a member of the Operations Department. The Fire Response Team will not include any personnel required for other essential functions during a fire emergency.

6.9.1.4 Implementing procedures for surveillance testing and inspection, to assure that necessary equipment is in place and operr' le, have been established. Four fire drills, conducted under the direction of the Fire Protection Supervisor, will be held each quarter, with the intent of maximizing the number of fire brigade members to be drilled.

6.9.1.5 Self-contained breathing apparatus will be supplied for each member of the Fire Response Team and for any control room personnel. One hour of breathing air spare bottles for each of the above required masks will be available within the confines of the unit with cascade recharging facilities located on the Genoa site.

6.9.1.6 A section of the Fire Protection Plan delincaies inspection and surveillance test l frequency, reports necessary, and statements of actions.

D-PLAN 6-14 January 1998

6. DECOMMISSIONING PROGRAM -(cont'd)

, 6.9.2 SAESTOR Analysis LACBWR can safely maintain and control the FESW in the case of the worst postulated fire in each fire area of the plant.

The SAFSTOR fire protection program and systems were reviewed using the criteria and guidelines of Branch Technical Position 9.5-1 for general guidance, h was concluded th4 the LACBWR Fire Protection Program and detection and extinguishing systems are adequate, considering the reduced risk due to plant being in the SAFSTOR mode. The installed fire protection equipment being maintained durin3 the SAFSTOR period is the same as that used during plant operation.

Fire protection practices include isolation of fire areas via sealed penetrations; detection of potential fires and location identification for the plant operators, coverage by automatic extinguishing systems in the plant, protecting cables with fire resistant coverings, and i, stalled emergency lighting systems.

6.9.3 Plant Fire Layo.nl The LACBWR plant is divided into fire areas. These areas are separated from each other by one or more of the following:

1) 3-hour, or better, fire walls.

2) Walls and ceilings with ratings well in excess of the combustibles involved.

6.9.4 Fire Protection Systems The LACBWR Fire Protection System and equipment provide the means to quickly combat all a types of fires that might occur at the plant and to maintain the plant in a safe condition. The Fire Protection System consists of a CO2 flooding system for the IB Emergency Diesel Generator (EDG), Halon flooding system, portable extinguishers, sprinkler systems, hose stations and fire hydrants, transformer deluge systems, portable smoke ejectors, and a fire and smoke detection l system.

6.9.4.1 Fire Suppression Water. The fire suppression water system is a combined usage water system and is called the High Pressure Service Water System (HPSW). Water is supplied from the Mississippi River which is the west boundary of the plant. A reinforced concrete flume juts out from the cribhouse to channel water to the pumps.

Two 125 psi net head, vertical turbine, diesel fire pumps are connected in parallel and take suction from the well supplied by the flume.

D-PLAN 6-15 January 1998

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Year 1987 1988 1989 1990 - 2039 2nd 3rd 4th Actisities Qtr Qtr Qtr Reactor Shutdown x x

l File for Possession-Only License Reactor Defueling x l Receive Possession-Only License x l

! File Technical Specifications for Interim Period Submit Decommissioning Plan x Submit SAFSTOR Technical Specifications x Perform Baseline Radiation Survey l Perform System Modifications.

' Decommissioning Plan Approval x l

SAFSTOR Penod

• Limited Dismantlement x

l Shipment of Fuel OITsite **

4 Modification to Decommissioning Plan x

for SAFSTOR **

Update DECON Plan

• 3 Commence DECON *

• SAFSTOR period expected to last 30-50 years. A detailed DECON Plan will be submitted prior to end of that period.

• • Dependent on schedule of federal repository.

Tentative Schedule for LACBWR Decommissionine FIGURE 6.2 January 1998 D-Plan

7. DECOMMISSIONING ACTIHTIES l

7.1 Piml% RAT 10RE0]l SAFSTOR The plant was shut down on April 30,1987. Reactor defueling was completed June 11,1987.

Since the plani shut down, some systems have been secured. Additional systems will be shut down following determination orlayup methodology. Others are awaiting changes to plant Technical Specifications. Section 5.2 discussed the plant rvstems and their status.

In addition to preparation of this Decommissioning Plan, proposed revisions to Technical Specifications, the Securio Plan, the Emergency Plan, and the Quality Assurance Program Description have been completed. An addendum to the Environmental Report and a preliminary DECON plan have also been submitted.

7. 3 SAFSTOR MODIFICATIONS The LACllWR stafTreviewed t' facility to determine if any inodifications should be implemented to enhance safety or improve monitoring during the SAFSTCR period while fuel is stored onsite.

Some modifications were evaluated as being beneficirJ and therefore have been performed.

The majority involve the Fuel Element Storage Well System (FESW). A redundant FESW level indicator has been added. A second remote manually- operated FESW makeup line has been installed, which rupplies water from the Overhead Storage Tank. Also, a local direct means of measuring FESW water level has been installed.

Even though credit is not taken in the safety analyses (Section 9) for containment integrity, the automatic closure signals for containment isolation valve which will stm be rsed have been modified. The valves close on either a high Containment Building activity signal or a low FESW level signal, which has been set below the normal water level range. An FESW level indicator is used to generate the low FESW level signal. A ne'v Containment Building activity monitor has been installed, which will generate the high activity signal.

The gas activity monitors have been recai;brated to a Kr-85 equival: Kr-85 will be the predominant gaseous isotope during the SAFSTOR period.

D-PLAN 7-1 January 1998

7. DEC0!iMISS10!11 tic ACTIVITIES - (cont'd) 7.3 ACTIVITIES DUR1!10 SAFSTOR PERifD 7.3.1 F10dline Syst(ms and Decont opination Durinr. SAFSTOR During the SAFSTOR peri 7d, selected systems and components, especially those in accessibic areas, will be flushed or decontaminated. Surface areas in accesaible areas will continue to be decontaminateo. The principal reasons j for a selected flushing and oscontamination program are:

1) To reduce the contamination lovels and radiation dose rates in areas that will be accessibic for periodic maintenance and surveillance activities during the SAFSTOR period.

2) To reduce radiological surveillance requirements.

3) To reduce the need for protective equipment for personnel conducting maintenance and surveillance.

4) To reduce the inventory of radioactive material and the potential for the transfer of radioactive material to non controlled areas.

7.3.1.1 Internal System Flushing. Various closed plant systems, which contain water, will be flushed by recirculating water through the system's piping, vessels, tanks and othe components, with subsequent removal of suspended solids and radioactive ions by filtration and/or demineralization.

Some of these systems or components will bc ' rained after the flushing operations indicate that further reductions in radioactivity by this method are impractical. These systems may be maintained in a dry layup condition, Other systems will not he drained and may be maintained in a wet layup condition to reduce radiation dose rates in accessibl- locations. In sone r cases. the installation of additional shiciding to reduce radiation dose

[2 rates near the accessible areas of previously flushed systems or components may be necessary for AIARA.

7.3.1.? Aren and System Decontamination. The decontamination prograin during the SAFSTOR period will be a continuation of routino decontamination work performed at IACBVR. Plant areas and component outer surfaces will be decon-taminated to reduce the requirements for protective equipm at ute and to reduce the potential for the translocation of radioactive material. Decon-tamination methods that are used are dependent upon a nun.ber of variables, r

D- Pl/J4 7-2 March 1992 k.

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7. DECOMMISSIONING ACTIVITIES -(cont'd)

, such as surface texture, material type, contamination levels, and the tenacity with which the radioactive material clings to the contaminated surfaces.

Surface areas are primarily decontaminated using hand wiping, wet mopping, and wet vacuuming techniques. Detergents and other mild chemicals may be used with any of these techniques. The residual water cleaning solutions are collected by floor drains and processed through the liquid waste system. Most areas are routinely decontaminated to levels below 2000 dpmM'(about 500 dpm/100 cm'). Many areas are maintained below the Lower Limit of Detection (LLD).

Efforts will be made to maintain all accessible areas in the plant as free of surface contaminatica as h reasonably achievable.

Small tools and components will be periodically decontaminated by wiping with cleaning agents, steam cleaning, abrasive blasting, dishwasher, ultrasonic cleaning, electropolishing or other methods. Some unused equipment may be decontaminated as a prior step to removal for disposal as commercial or radioactive solid waste. Some unused equipment may be decontaminated prior to continued use in umestricted areas.

Larger systems and components in accessible areas may be decontaminated using hydrolazers, abrasives, chemicals or cther methods, aaer appropriate ALARA and economic evaluations are conducted.

7.3.2 Removal of Unusedjiquipanent During SAFSTOR During the SAFSTOR period, some equipment and plant components will no longer be considered useful or necessary to maintain the plant in the SAFSTOR condition. Some equipment located in unrestricted areas may be transferred directly for use at another location or disposed of as commercial solid easte.

Some unused equipment or components located within restricted areas, which have not previously been used for applications involving radioactive materials will be thoroughly surveyed and documented as having no detectable radioactive material (less than LLD) prior to transfer to another user or disposal as commercial solid waste.

Other unused equipment or plant system components which have previously been used for applications involving radioactive materials may be removed, thoroughly surveyed a id transferred to another licensed user, or disposed of aa low level solid radioactive waste material. Some equipment may be decontaminated and will be surveyed to verify that it contains no detectable radioactive material (less than LLD), prior to transfer to an unlicensed user, or for disposal as commercial solid waste.

Removal of plant equipment will be performed only afler review. A 10 CFR 50.59 safety analysis l will be conducted prior to dismantling any system.

D-PLAN 7-3 January 1998

7. DECOMM!S510NING ACTIVITIES -(cont'd)

> 7.42 Jn.1%nd[onitoring Routine radiation dose rate and contamination surveys will be taken of plant arcus along with more specif#c survey , d to support maintenance at the site. A pre-established location contact dose rate survey ... . be routinely performed to assist in plant radionuclide trending Tliese pointe sre located throughout the plant on systems that contained radioactive liquid / gases dunng plant operation.

7.4.3 Relenchi11tdifIluertOlojitnting During the SAFSTOR period, efiluent relense points for radionuclides will be monitored during all periods of potential discharge, as in the past. The two potential discharge points are the stack arf the liquid waste line.

a) Slack - the ellluents of the s:ack will be continuously monitored for paniculate and gaseous activity. The noble gas detector (s) have been recalibrated to an equivalent Kr.85 energy. The stack monitor will be capable ofdetecting the maximum Kr 85 concentration postulated from any accident during the SAFSTOR period. Filters for this monitor will be changed and analyzed for indionuclides on a routine basis established in the ODCM. l b) liquidischarge the liquid ellluents will be monitored during the time of release.

Each batch release will be gamma analyzed before discharge to ensure ODCM requirements will not be exceeded.

All data collected concerning efiluent releases will be maintained and will be included in the annual ellluent report. l 7.4.4 EnvironmentaLMonitoring Offsite area dose rates as well as fish, air, liquid, and earth samples will continue to be taken and analyzed to ensure the plant is not adversely afTecting the surrounding environment during SAFSTOR. The necessary samples and sample frequencies will be specified in the ODCM.

All data collected will be submitted in the annual environmental report.

D-Pl.AN 7-5 January 1998

8. IlEALTil PilYSICS -(cont'd)

. A dry filter paper or cloth dix will be wiped over approximately one square foot (12"x12" square l or 12'-long S shaped) of the surface being monitored. Swipes will be counted for beta gamme  :

activity in a gas-flow proportional detector or with a 2 n GM probe or equivt.!cnt in fixed geometry sample holder as necessary. Alpha activity of a swipe will be determined by means of a j windowless gas-flow pioportional detector and a sesler or equivalent, when alpha radioactivity is suspected of being present.

8.4.4 LiquidAttivity Surveys l Samples of water containing radiorctivity are collected and analyzed on a routine basis. Spent fuel pool water is analyzed to dete:t indications of degradation of the fuel stored in the pool.

Samples ofliquid radioactive was es and processed wastes are analyzed to ensure levels of radioactivity are below the levels permitted for release. Samples are analyzed by Health and Safety Department personnelin accordance .vith established procedures.

8.4.5 EnvironmentaLSurveys Environmental samples will be taken within the surrounding areas of the plant, These sample::

will be analyzed to determine any efTects plant efIluent releases may have on the environment.

This program wiii be conducted as per the ODCM. l 8.5 RADIATION PROTECTION EOUlPMFET AND INSTRUMENTATION A variety of equipment and instruments are used as part of the radiation protection program.

Equipment and instrumentation are selected to perform a particular function. Sensitivity, case of operation end maintenance, and reliability are factors that are considered in the selection of a particular instrument. As the technology of radiation detection instmmentation improves, new instmments are obtyned ta more accurately measure radioactivity and ensure an effective radiation protection program.

This equipment can be broken down into several specific groups each with its own dedicated functions. These groups are:

a) Portable instruments b) Installed instruments c) Personnel Monitoring Instmments d) Counting Room Instruments This equipment will be used, checked and calibrated by trained personnel according to in-plant procedures.

l D. PLAN 8-8 January 1998 i l

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