ML20211M695

Forwards Tentative Schedule for Completion of Remaining Analyses,Engineering & Implementation of Plant Mods for Integrated Consequence Study,Integrated Plant Safety Assessment (NUREG-0827)

ML20211M695
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/11/1986
From:	Taylor J DAIRYLAND POWER COOPERATIVE
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0827, RTR-NUREG-827 LAC-12001, NUDOCS 8612180022
Download: ML20211M695 (5)

Text

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D DA/RYLAND hh[a/[ COOPERATlVE P O BOX 817 2615 EAST AVE. SO LA CROS (608) 788 4 000 JAMES W. TAYLOR Gereral Manager In reply, please refer to LAC-12001 DOCKET NO. 50-409 Mr. John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE (DPC)

LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 INTEGRATED CONSEQUENCE STUDY, NUREG-0827 INTEGRATED PLANT SAFETY ASSESSMENT REFEREBCES: 1) NRC Letter, Zwolinski to Taylor, dated September 9, 1986.

2) DPC Letter, Linder to Paulson, LAC-10251, J>ted October 11, 1984.

3) DPC Letter, Linder to Zwolinski, LAC-10639, dated March 15, 1985.

4) DPC Letter, Taylor to Zwolinski, LAC-11494, dated April 1, 1985.

Dear Mr. Zwolinski:

Reference 1 provided the NRC safety evaluation of the LACBWR Integrated Consequence Study, which was submitted in Reference 2 and supplemented by Reference 3 and 4. The NRC letter requested that DPC provide a schedule for completion of the remaining analyses, engineering and implementation of plant modifications.

This letter provides a tentative schedule. The schedule may need to be modified as the analyses are completed, because the engineering work and plant modifications necessary may be affected by the results of the analyses. Some of the modifications are dependent on plant outages. No firm long term outage schedaled has been established, so the modification dates may change as outage schedules are determined. For purposes of scheduling, a fall refueling outage was assumed for the ne: t 3 years.

8612180022 861211 PDR ADOCK 05000409 WPl.6.10 p PDR _

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Mr. John Zwolinski, Director December 11, 1986 4

BWR Project Directorate #1 LAC-12001 Reference 1 requested that when the detailed engineering of proposed plant modifications is complete, a report be submitted to the NRC. Since modifications are scheduled over a three-year period, several reports will be generated, rather than one report covering the engineering of all modifications. .

If prior NRC approval is necessary, the modification schedule will be dependent on the NRC review process and the required detail of the design re port. A prompt response to this issue is necessary since some of our design work is scheduled for early 1987, with installation in fall 1987.

.{ The tentative schedule of actions necessary for the wind and tornado events is contained in Table 1. The tasks involved in the seismic event topic are listed in Table 2. Table 3 is a summary sheet of the schedule for the seismic topic activities.

DPC will submit the seismic analyses as they are completed. To expedite seismic work, analysis is scheduled to commence in February 1987 and to be completed mid 1988. During this time-frame, modifications are scheduled as plant conditions permit. Work involving containment or system integrity will be scheduled during the next three refueling outages.

Seismic task items 9 and 10 are scheduled towards the end of the analysis period. It is DPC's engineering judgment that no modifications will be required to these areas. Seismic task items 3 and 6 cannot be individually scheduled for modifications until the results of the analyses are complete.

Although the schedule reflects work being performed in certain months, DPC will perform shop fabrication and other task support work that can be accomplished during plant operation. This will minimize the actual work required during scheduled refueling outages and hasten the task completion.

If there are any questions regarding the listed tasks or tentative schedule, please contact us.

j j Sincerely, 1

i JWT:LSG:RMB:sks Enclosures

! cc: R. Bevan, LACBWR Project Manager J. Keppler, Regional Administrator I. Villaiva, Resident Inspector WPl.6.10  !.

4 Table l Wind / Tornado Tasks Task Scheduled Completion Report on Stacks January 1987 Design of Shutdown Condenser / Spring 1987 Overhead Storage Tank Cross-Connect Line Installation of Cross-Connect Fall 1987 Line Task Analysis of Wind / Tornado Fall 1987 Actions Procedure Preparation Fall 1987 Procedure Validation Fall 1987 1 Training Fall 1987 Procedure Laplementation Fall 1987 i

i 4

WPl.6.10

, [d Table 2 Seismic Event Topic TASKS

, 1. OHST/ Shutdown Condenser Cross-Connect Make-up Line

2. OHST/ Shutdown Condenser Make-up Line

' (Containment - Grade to OHST)

3. Valve Functionability

a. Shutdown Condenser Steam Inlet Control Valve

b. Shutdown Condenser Condensate Outlet Control Valve

c. Manual Depressurization Valve

d. Alternate Core Spray Check Valves

e. Shutdown Condenser Steam Inlet Manual Valve

f. Low Pressure Core Spray Valve

4. Shutdown Condenser Platform

' 5. Shutdown Condenser Tube Sheet

6. Valve Anchorage

a. Shutdown Condenser Steam Inlet Control Valve 7

b. Shutdown Condenser Condensate Outlet Control Valve 4 c. Manual Depressurization Valve

d. Alternate Core Spray Valves

e. Shutdown Condenser Steam Inlet Manual Valve

f. Low Pressure Core Spray Valve i

7. Alternate Core Spray Line

8. Seismic Operating Locker 9.: Mechanical Penetration Area 10.. Electrical Penetration Area

11. Remote Monitoring Station WPl.6.10

s

+?

TABLE 3 - SEISMIC ACTIVITY SIMfARY SHEET Task  : 1987  :: 1988 :l 1989

1. OHST / Shutdown Condenser lJ:F:M:A:M:J:J:A:S:O N D::J:F:M:A!M:J:J:A:S:O:N:D: J F:M:A:M:J:J:A:S:0:N Cross-Connect Make-up Line

//// X X(X) ::  ::

2. OHST / Shutdown Condenser Make-up Line //  ::

X X(X)  ::

(Containment - Grade to OHST)  :  ::  ::

3. Valve Functionability  ::

///  :: (X)

a. Shutdown Condenser Steam Inlet Control  :  :: ll Valve  ::

b. Shutdown Condenser Condensate Outlet  :  ::  ::

Control Valve  ::

c. Manual Depressurization Valve

d. Alternate Core Spray Check Valve  ::  ::

e. Shutdown Condenser Steam Inlet Manual  :  ::  ::

Valve  ::

f. Low Pressure Core Spray Valve

4. Shutdown Condenser Plat form ///

5. X X X X :X X X X X X X X X X(X) :

Shutdown Condenser Tube Sheet  : (/)*  ::  ::

6. Valve Anchorage //

Shutdown Condenser Steam Inlet Control ll/ / X X X X::X X X X X X X X X X(X)

n.  :  ::  ::

Valve  ::

b. Shutdown Condenser Condensate Outlet  :  ::  ::

Control Valve  ::  ::

c. Manual Depressurization Valve  !  ::  ::

d. Alternate Core Spray Check Valve  :  ::  ::

e. Shutdown condenser Steam Inlet Manual  ::  ::

Valve  :  ::  ::

f. Low Pressure Core Spray Valve

7. Alternate Core Spray Line l ll  ::

!/ / X X(X) ::

H. Seismic Locker  ::

9. Mechanical Penetration Area

/ / / X X X X::X X X X X(X) l  :: (/)*  ::

10. Electrical Penetration Aren ll (/)*  ::

11. Remote Monitoring Station  :  :/ / / X X X X X::X X X X X X X X X X(X)

/ = Analysis or Design X = Installation

( ) = Anticipated Completion

+

= Do Not Anticipate any Modifications pc2-9