ML20046A636

Informs of Rev to Decommissioning Plan

ML20046A636
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/29/1993
From:	Berg W DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LAC-13277, NUDOCS 9307290151
Download: ML20046A636 (8)

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RO. BOX 817 LA CROSSE. WISCONSIN 54602-0817 (608) 788-4000' FAX NO. (608) 787-1420 WILLIAM L BERG General Manager June 29, 1993 In reply, please refer to LAC-13277 DOCKET NO. 50-409 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:

SUBJ ECT:

Dairyland Power Cooperative La Jrosse Boiling Water Reactor (LACBWR)

Possession-Only License DPR-45 Decommissioninn Plan Revision REFER.ENCES :

(1) DPC Letter, Taylor to Document Control Desk,' LAC-12460, dated December 21, 1987 (original submittal of LACBWR's Decommissioning Plan)

(2) NRC Letter, Erickson to Berg, dated August 7, 1991, issuing Order to Authorize Decommissioning of LACBWR This letter will inform you of several changes necessary to keep the LACBWR Decommissioning Plan current. The changes are for various reasons, as outlined below, and modified pages have been provided for your copies of the Decommissioning Plan. None of the changes to the Plan were determined to require prior NR.C approval.

The changes have been reviewed and approved by the LACBWR Operations Review Committee and Safety Review Committee.

The individual pages requiring revision are included with this letter.

The changes are indicated on each page by a bold har in the right-hand margin.

Reasons for the changes are as follows:

(1) Page 4-1.

"...and acid storage tanks,..

Description has been removed from the General Plant Description. The acid storage tanks were utilized for regeneration of full-flow demineralizer resins. To reduce waste water volume, regeneration of the full-flow domineralizers was discontinued in 1970. The sulfuric acid tank was removed and appropriately disposed of.

This system no longer exists.

(2) Page 4-5.

Remove ".. final offgas line HEPA/ charcoal filters...."

The offgas system has been substantially removed, as part of the limited dismantling which has been discussed with our project manager at the U.S. Nuclear. Regulatory Commission. This portion of the facility description is no longer accurate as the system is being removed.

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Document Control Desk LAC-13277 Pa'ge 2 June 29, 1993 (3)

Page 5-12.

"A 4-inch offgas header....and closed the offgas storage tanks discharge valve."

Remove the description currently in place under section 5.2.10, Gaseous Waste Disposal System, and substitute a sentence that this system has been mostly removed under limited dismantlement.

l The offgas system was not necessary for SAFSTOR or plant repowering.

Therefore, piping, tanks, filters, etc. of this system have'been removed i

and disposed of in an appropriate manner for radioactive material.

(4)

Page 6-3.

The current SAFSTOR plan calls for the services of an Administrative Assistant who works jointly between LACBWR and the adj acent fossil unit and a Secretary responsible for all clerical tasks at LACBWR. The Administrative Assistant currently in place,_who has j

extensive experience, has reached retirement.

Her duties will be assumed by the current Secretary, and an additional clerical person will be shared between the two facilities (50 percent each place). This will permit the senior clerical person at each facility to concentrate on the specialized work required and the person shared by the plants to perform i

more general work.

This will retain the 1-1/2 person commitment for clerical purposes at the LACBWR facility but will change the structure and level of the job rating.

(5)

LA CROSSE BOILING WATER REACTOR SAFSTOR STAFF organization flow-chart.

This figure is being changed to reflect the change from the Administrative Assistant.

(6) Figure 4.3.

This diagram showing the main floor of the turbine and containment buildings is revised to show the removal of the shield walls around the steam turbine. The shield walls were originally designed to reduce personnel radiation exposure from short-lived isotopes in the steam.

Since plant shutdown, this source of radiation has ceased to exist.

Repowering of the plant would not increase radiation levels in this area.

The shield walls have been properly disposed of.

Please contact either John Parkyn or Roger Christians of my staff, at 608-689-2331, if you have any questions or comments.

Yours truly, DAIRYLAND POWER COOPERATIVE

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William L. Berg, General Manager VLB :J DP : dh Enclosures i

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A. Bert Davis, NRC Region III Larry Pittiglio. NRC Project Manager

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FACILITY DESCRIPTION 4.1 CENERAL PLANT DESCRIPTION The LACBWR was a nuclear power plant of nominal 50 Mw electrical output, which utilizes a forced-circulation, direct-cycle boiling-water reactor as its heat source.

i The reactor and its auxiliary systems are within a steel containment building. The turbine-generator and acsociated equipment, the control room for both turbine and reactor controls, and plant shops and offices are in a conventional building adjacent to the containment building.

Miscellaneous structures which are associated with the power plant, and are j

located adjacent to the Turbine Building, include the electrical switchyard, Cribbouse, Waste Treatment Building, LSA Storage Building, oil pump house,.

stack, warehouses, administration building, annex building, guard house, outdoor fuel oil tanks, underground septic tanks, gas storage tank vaults, l

underground oil tanks and the condenser circulating water discharge seal well at Cenoa Unit 3.

Miscellaneous onsite improvements include roads, walks, parking areas, yard lighting, fire hydrants required for plant protection, access to and use of rail siding facilities, fencing, landscaping, and communication services.

4.2 BUILDING AND STRUCTURES 4.2.1 Containment Buildinn The containment building (Figs. 4.1 and 4.2) is a right circular cylinder

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with a hemispherical dome and semi-ellipsoidal bottom.

It has an overall internal height of 144 ft. and an inside diameter of 60 ft., and it extends 26 ft. 6 in below grade level. The shell thickness is 1.16 in., except for the upper hemispherical dome which is 0.60 in. thick.

The building contains most of the equipment associated with the nuclear steam supply system, including the reactor vessel and'oiological shielding, the fuel element storage well, the forced circulation pumps, the shutdown condenser, and process equipment for the reactor water purification system, decay heat cooling system, shield cooling system, seal injection system, emergency core spray system, boron injection system, and storage well cooling system.

The containment building was designed to withstand the instantaneous release of all the energy of the primary system to the containment atmosphere at an initial ambient temperature of 80 F, neglecting the heat losses from the building and heat absorption by internal structures.

Its design pressure is 52 psig, compared to a calculated maximum pressure buildup of 48.5 psig following the maximum credible accident while in operation. The containment building shell is designed and constructed according to the ASME Boiler and Pressure Vessel Code, Sections II, VIII, and IX, and Nuclear Code Cases 1270N, 1271N, and 1272N.

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1 D-PIAN 4-1 June 1993

4 FACILITY DESCRIPTION - (cont'd)

The remaining grade or above grade areas contain a shower / wash / frisking area, and the dry active waste (DAW) compactor unit and temporary storage space for processed DAV containers.

Beneath the grade floor are two shielded cubicles. One cubicle, through which access is gained by removal of floor shield plugs, is available for the storage of up to nine higher activity solid waste drums. The other area, through which access is gained by a stairway, contains the dewatering ton exchanger, the WTB sump and pump, and additional waste storage space.

l The Waste Treatment Bulding ventilation is routed through an 11 EPA filter to the stack plenum. The building is normally maintained at a negative pressure. The general arrangement of the WTB is shown on Figure 4.5.

The LSA Storage Building is southwest of the Turbine Building.

It is used to store processed, packaged and sealed low level dry active waste materials, and sealed low level activity components for a period of approximately 5 years. The building has the capacity for 500 DOT 17H-55 gallon drums of waste.

No liquids are stored in this building.

There are no effluent releases from this building during normal use.

4.2.4 Cribhouse The Cribhouse is located on the bank of the Mississippi River to the west of the plant and through its intake structure, provides the source of river water to the various pumps supplying river water to the plant. The Cribhouse contains the diesel-driven high pressure service water pumps, travelling screens, low pressure service water pumps and the circulating water pumps.

1 D-PLAN 4-5 June 1993

5 PIANT STATUS - (cont'd) 5.2.10 Caseous Waste Disposal System This system routed main condenser gasses through various components for drying, filtering, recombining, monitoring and holdup-for decay. Most of the system has been removed since it was no longer required for SAFSTOR nor necessary for any potential repowering.

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D. PIAN 5 12 June 1993 i

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DECOMMISSIONING PROGRAM - (cont'd) stationed at or visiting LACBWR comply with it in spirit as well as regula-tion.

This supervisor will also assign the day-to-day duties of the health physics technicians.

The Health Physics Technicians will be responsible for the radiation protection and chemistry programs at LACBWR. They will perform all tasks required for surveillance and will provide all work coverage required by special work permits. They will maintain as required the exposure records of personnel, take all the readings necessary to guard against the spread of contamination and provide input to the long-term radienuclide inventory program. They will report, as directed by the Health and Safety Supervisor, to the Duty Shif t Supervisor as required.

The Mechanical Maintenance Foreman is responsible for the assignment of mechanical maintenance duties and will direct the completion of all mainte-nance requests and surveillance tests of a mechanical nature. The Mechanical Maintenance Foreman is responsible for the preventive maintenance program established on those systems necessary to maintain the SAFSTOR condition.

This foreman is responsible for overall maintenance on all of the plant equipment which may serve as backups to the required systems or backup supplies to the rest of the Dairyland system.

Maintenance Mechanics are responsible for the completion of all mechanical maintenance tasks. These tasks include all surveillance requirements and work requests defined in maintenance orders as well as general duties as assigned by the maintenance supervisor.

The Administrative Secretary is responsible for overall administration of

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LACBWR. She will maintain all records required under technical specifi-cations for plant operation and will maintain a record of all activities involved in facility shutdown and establishment of the SAFSTOR mode. The Administrative Secretary will ensure that all clerical functions are performed adequately. She will maintain all budget expense and project accounts and will coordinate preparation of the LACBWR budget. Duties will i

also include assigning to staff personnel required re=ponses to regulatory agencies, other Dairyland departments, etc., and ensuring that these tasks are completed by the established deadline.

The Clerk Typist will report to the Administrative Secretary two and one-half days per week and will assist in the clerical tasks at LACBWR, including word processing and the personal computer database.

She will also operate the telephone communication switchboard and other tasks as assigned by the Administrative Secretary.

The Licensing Engineer will be responsible for all facility licensing. This will include steps preparatory to eventual shipment of SAPSTOR fuel and proceeding into the DECON mode.

The Licensing Engineer will be the principal liaison on behalf of the Plant Manager for the contact with the Nuclear Regulatory Commission and other regulatory agencies. This engineer will be i

D-PLAN 6-3 June 1993

l LA CROSSE BOILING WATER REACTOR SAFSTOR STAFF PLANT MANAGER

-i ORC, SRC, QA OPERATIONS /I&E/ MECHANICAL HEALTH & SAFETY SUPERVISOR MAINTENANCE GROUP 3 Health Physics Technicians 2 Instrument Technicians 2 Electricians 5 Shift Supervisors 6 Operators 3 Mechanics ADMINISTRATIVE LICENSING REACTOR / RADIATION SECRETARY ENGINEER PROTECTION ENGINEER *

.5 Clerk Typist Assumes Cooperative-wide Security & QA

• Duties to be performed with assistance of qualified consultants when necessary.

FIGURE 6.1 D-PLAN June 1993 m

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$ PENT FUEL STORAGE WELL EXCITATION FE6W TURBINE BUILDING SWITCHGEAR 10 0

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&p Main Floor of Turbine and Containment Buildings.'El. 668'0" FIGURE'4,3 D-PLAN June 1993

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