ML19331E266
| ML19331E266 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/03/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TASK-1.C.5, TASK-2.K.3.27, TASK-TM LAC-7112, NUDOCS 8009090529 | |
| Download: ML19331E266 (6) | |
Text
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L D DA/RYLAND
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COOPERATNE so eox an. :sts EAST Av soum LA esosse. wisccus.n s4 sos (608) 7884cco i
September 3, 1980 l-In reply, please 1
refer to LAC-7112 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN:
Mr. Darrell G. Eisenhut, Director Division of Licensing U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
DAIRYLAND POWER' COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 ADDITIONAL TMI REQUIREMENTS s
REFERENCES:
(1)
NRC Letter, Eisenhut to All Operating Reactors, dated May 7, 1980.
I (2)
DPC Letter (LAC-70 ll), Linder to Eisenhut, dated July 7, 1980.
Dear Mr. Eisenhut:
Our initial response (Reference 2) to your request for compliance with additional requirements coming from the Three Mile Island Leasons Learned (Reference 1) stated our schedule for submitting this information.
Enclosure I to this letter provides our response to several items.
If there are further questions, please contact us.
Very truly yours,
DAIRYLAND POWER COOPERA7IVE
/t/
Frank Linder, General Manager FL:JDP: abs CC:
J.
Keppler, Reg. Dir., NRC-DRO III S
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ENCLOSURE 1-j ITEM SUBJECT
RESPONSE
'I.A.3.1 Revise Scope and Criteria for Compliance with this item is complete.
' Licensing Examinations 7/29/80 1
I.C.5 Procedures for Feedback of LACBWR will complete this review.
Operating Experiences to Plant Staff i
II. K. 3.1 -
Installation and Testing of Applies to PWR's only.
Automatic PORY Isolation System II.K.3.2 PWR Vendor Report on PORY Applies to PWR's only.
Failure Reduction I I. K. 3. 3 Reporting Safety and Relief (a&b) LACBWR does not utilize primary Valve Failures and Challenges system relief valves.
(c) LACBWR will promptly report to the NRC any future failure of a primary system relief or safety valve to close af ter pressure relief operation.
(d) LACBWR will report all future indicated operations of primary system safety valves for pressure relief.
II.K.3.5 Automatic Trip of Reactor Applies to PWR's only.
Coolant Pumps During LOCA II.K.3.9 Proportional Integral Applies to Westinghouse PWR's only.
Derivative Controller Modification II. K. 3.10 Proposed Anticipatory Trip Applies to Westinghouse PWR's only.
Modi fication II.K.3.12 Confirm Existance of Antici-Applies to Westinghouse PWR's only, patory. Trip upon Turbine Trip' II. K. 3.13 Separation of HPCI and RCIC Applies to SWR's with RCIC and HPCI System Initiation Levels -
systems only.
Analysis and Implementation II.K.3.14 Isolation of Isolation This item proposes a change to increase Condensers On High the availability of isolation condensers Radiation as heat sinks.
It states that currently isolation condensers are isolated by high radiation signals in the steam line
-leading to the condenser and that this
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point of signal should be changed to the shutdown condenser vent.
(Cont'd)-- -
ENCLOSURE 1 f
ITEM'
~ SUBJECT
RESPONSE
II.K.3.14 The shutdown condenser at LACBWR does (Cont'd) not have this isolation feature as part of its design.
Isolation is y
accoglished manually upon indication of radiation levels at the vent.
This modification to increase the availability of-the isolation conden : '
ser is not required at LACBWR.
II.K.3.15 Modify Break Detection Logic Applies to BWR's with HPCI and RCIC to Prevent Spurious Isolation systems only.
of HEI and RCIC systems II.K.3.16 Reduction of Challenges and LACBWR does not utilize primary system Failure of Relief Valves -
relief valves and this item does not Feasibility Study and System apply.
Modifications II.K.3.17 Report on Outage of ECC LACBWR will provide the requested Cystems data specified.
II.K.3.18 Modification of ADS Logic This item applies to BWR's with automatic depressurization systems.
II.K.3.19 Interlock of Recirculation LACBWR is a two-loop Allis-Chalmers Pump Loops
.BWR which has specific Technical Specification restrictions requiring the nonisolation of one of its recircu-lation loops during any time in which the shutdown condenser is in service q
or either steam isolation valve is open. LACBWR is permitted to operate with less than all loops in service.
Therefore, this item is not applicable.
The safety assessment of this mode of operation was completed by the Systematic Evaluation Program under Topic I7-1.A.
II.K.3.20 Loss of Service Water for Applies to Big Rock Point only.
Big Rock Point I i
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ENCLOSURE 1
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j
- i ITEM SUBJECT
RESPONSE
i.
II.K.3.21 Restart of Core Spray a d LPCI The high pressure core spray system Systems On Low Level at LACBWR has in the design of its pump control switches the desired 3
feature. When the pump is switched to the off positfon, the control switch is spring l'
loaded to return to automatic when-ever the handle is released. A low water level in the reactor vessel inanediately restarts the pump. Only by placing the handle in pullout position can the operation of the high pressure emergency core spray pumps be stopped. This system design is in compliance with the staff position for this item.
The alternate core spray system con-sists of diesel engine driven pumps which obtain their water supply fran the Mississippi River and pump the river water through automatic valves to the reactor. The system is designed to operate on high containment building pressure and 1cw reactor water level.
The design of the system is such that the diesel engine driven pumps start on a high containment building pressure signal, and the automatic valves open on a high containment building pressure signal and a low reactor water level signal at -12".
When in operation, the valves will remain open until water level is greater than -12", and will cycle to maintain that level.
The control valves are locked.in auto and require obtaining keys to change their position. Since the valves cycle to maintain reactor water level, the engine driven pumps are lef t running.
The engine driven pump centrol switches have an off position to permit surveil-lance testing of the engines.
- However, a red annunciator would indicate if the switches were off. As this system functions for water level control and
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no operator action is required to secure the pumps, it remains in automatic.
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ENCLOSURE 1 i
}
ITEM SUBJECT
RESPONSE
f II.K.3.22-Automatic Switchover of RCIC Appites to BWR's with RCIC systems T
System Suction only.
II.K.3.24 Affirm Ade:;a.y of Space
~Applies to BWR's with RCIC and HPCI Cooling for HPCI and RCIC systems only.
{
Systems II.K.3.25 Effect of Loss of AC Power Applies to PWR's only.
On Pump Seals i
II.K.3.27.
Provide Comon Reference All operating water level transmitters Level for Vessel Level at LACBWR already have a comon Instrumentation elevation for their vessel taps. All but the " wide range indicators" were indexed for normal operating level.
We have indexed this remaining indicator so all five operating water level transmitters have a comon reference point. LACBWR is in compliance with thi< item.
II.K.3.28 Study and Verify Qualification LACBWR has an MDS rather than an ADS.
[
of Accumulators in ADS Valves This verification of qualification will be performed in the acctmiulators for the MDS valves.
II.K.3.29 Study to Demonstrate Perfor-LACBWR has in its shutdown condenser mance of Isolation Ccndensers design. automatic venting of non-with Not.condensibles condensibles.
It also has remote
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manual capability to vent noncondensibles to ensure adequate natural circulation.
This review giving considaration to removal of noncondensibles was accomplished in the initial system design.
II.K.3.30 Revised Small Break LOCA LACBWR will review existing analysis Methods to Show Compliance methods.
with 10CFR50 Appendix K II.K.3.31 Plant Specific Calculations This item references 10 CFR 50.46 to Show Ccepliance with which is specifically directed tcwards
'.10:CFR 50.46 reactors using zircalloy cladding.
LACBWR will review this item applicability once Draft 4 of NUREG-0660 is issued.
II.K.3.44 Evaluation of Anticipated LACBWR will complete this evaluation.
Transients with Single Failure to Verify No Fuel Damage 1 1
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ENCLOSURE 1
}.
4 s;
ITEM
' SUBJECT
RESPONSE
II.K.3.45 Evaluation of Depressurization LACBWR utilizes an MDS 'rather than an With Other than ADS ADS.
Its shutdown condenser provides an alternate to use of the MDS valves for depressurization. This use of an 1! -
alternate will be documented by procedural reference.
II.K.3.46-Response to List of Concerns Michelson's concerns have been from ACRS Consultant addressed at LACBWR, The results of this revie as it applies to this facility were submitted to the NRC in LAC-6688, dated December 11, 1979.
This item is complete.
II.K.3.57 Identify Water Sources Prior LACBWR uses an MDS rather than an ADS.
l to Manual Actuation of ADS The procedure for actuation of the MDS l
requires that the alternate core spray l
system be functioning prior to use of l
the MDS.
Implementation of this item I
is already in effect.
III.D.3.4 Control Room Habitability This review will be accomplished.
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