ML19347B292
| ML19347B292 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/12/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19347B293 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 LAC-7136, NUDOCS 8010140223 | |
| Download: ML19347B292 (4) | |
Text
--.
D DA/RYLAND
[k COOPERAT/VE
- Po BOX 817
- 2615 EAST AV SOUTH
- LA CROSSE. WISCONSIN S4601 (608) 788 4 000 September 12, 1980 In reply, please refer to LAC-7136 4
DOCKET NO. 50-409 L
Director of Nuclear Reactor Regulation ATTN:
Mr. Dennis M. Crutchfield i
l Operating Reactors Branch'#5 l
Division of Operating Reactors U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR) i PROVISIONAL OPERATING LICENSE NO. DPR-45 APPLICATION FOR AMENDMENT TO LICENSE
REFERENCES:
(1) 10 CFR Section 50.90.
(2)
NRC Letter, Eisenhut to All Power Reactor j
t Licensees, dated April 10, 1980.
I e
(3)
NRC Letter, Eisenhut to All Boiling Water Licensees, dated July 2, 1980.
~~~
Gentlemen:
i As requested by References (2) and (3), we are submitting an application to. amend Provisional Operating License No. DPR-45 by proposing changes to Technical Specifications for the La Crosse Boiling Water Reactor (LACBWR).
The proposed changes deal with clarifying the meaning of the term " OPERABLE" as it applies to the single-f ailure criterion for safety systems in LACBWR and added Technical' Specifications following implementation of the TMI-2 Lessons Learned, Category "A"
items.
The proposed changes enclosed include the applicability and surveillance requirements and associated bases of Standard Tech-nical Specifications (STS) adapted to the LACBWR Technical
. Specifications.
The section on definitions has been revised.
The first paragraph under 4.0.1 has been expanded to apply to Fire Protection Systems, Sections 4/5 2.17, 4/5 2.18, and 4/5 2.19.
There were capitalized j
words in this portion of Technical Specifications that were not in the : list of definitions.
l i
8010140 1-e
~
'E
{
h..
Director of Nuclear Reactor Regulation September 12, 1980 ATEN:
Mr. Dennis.M. Crutchfield LAC-7136
~
Operating Reactors Branch #5 Division of Operating Reactors The list-of definitions itself has been expanded to include definitions which may be used in future proposed changes.
- Lastly, the clarified definition of " OPERATION - OPERABILITY" as requested by Reference (2) is included.
l Delete Section 4.1.4 - This requirement that all reactivity effects l
shall be under the control of or under the direction of a licensed
[
operator in the Control Room is contained in Section 6.2.2 b and c.
i l
Delete Section 4.1.6 - The requirements of an In-Service Inspection Program are contained in a license amendment request, letter LAC-6280, Linder to Ziemann, dated May ll, 1979.
Change Section 4.2.1.1 to read :
CONTAINMENT INTEGRITY shall be maintained.in CONDITIONS 1, 2,
3, and during:
a.
(
b.
handling of irradiated fuel, or c.
moving a spent fuel shipping l
cask in the Containment Building.
A new Page 28 is enclosed reflecting the above changes.
Delete entirely Section 4.2.3, Electrical Power Systems and Associated Surveillance Requirements, i.e. all of Pages 32g, 32h, 32i, 32j, 32 k, 321, 32m, 32n, 32o, 32p, 32q, and 32r; and, substitute the entire enclosed sections on Electrical Power Systems.
The. proposed section has been edited to make it more clear; there is no substantial change in the requirements.
The sections referring to operating has been changed to only include OPERATIONAL
(
CONDITIONS 1 and 2, instead of the ambiguous applicability in the present Technical Specifications.
Likewise shutdown sections refer l
.to OPERATIONAL CONDITIONS 3, 4, and 5.
The explanation of " con trol power off and all control rods fully inserted," has been deleted in
-deference to the Table of OPERATIONAL CONDITIONS.
t The surveillance requirements in the enclosed proposal for the 1A and j
1B Diesel Generators have been augmented to effect increased reliabi-lity of the emergency power supplies.
The specific gravity of the batteries of D.C.
distribution systens has been changed from 1.180 to 1.200, in order to effect an increased margin of battery capacity.
Item 7 of Table I, Operating Limits, has been changed under the Action column to reflect recent changes to add diverse parameter
(
signals to isolate containment penetrations.
i -
gf
~
Director of Nuclear Reactor Regulation September 12, 1980 t
ATTN:
Mr. Dennis M. Crutchfield LAC-7136 l
Operating Reactors Branch #5 l
Division of Operating Reactors Item 16 of Table I, Operating Limits, has been changed under the Action column t~5' separate the actions under 2) and add diverse parameter signals to isolate containment building penetrations.
Table I, Operating Limits, now incorporates the necessary changes requested by Reference (3).
l A page 6-1 is enclosed which incorporates other changes of Reference (3).
A revised page 44 is enclosed which clarifies the wording under the minimum frequency column when a reactor water level calibration is to be performed.
A water-steam interface level in the reactor has been determined monthly by means of a probe, for over 10 years and no change in calibration of the water level channels has ever been l
detected.
The water level probe was originally installed as an j
alternate means of calibrating the water level safety systems.
The requested change on page 44 is to eliminate the requirement for l
utilizing the water level probe as a check on the calibration of the reactor water level channels.
The proposed changes are to be inserted as full pages in the LACBWR Technical Specifications and are numbered accordingly.
The proposed j
changes include at least the requested wording of Reference (2).
l In accordance with the provisions of Reference (1), an application j
l to amend Provisional Operating License No. DPR-45 for the La Crosse i
Boiling Water Reactor is hereby filed with three (3) signed original applications, together with thirty-seven (37) copies.
This change has been determined to be a Class II Amendment, having no safety or environmental significance as defined by 10 CFR 170.22 and a check for $1,200.00 is enclosed to cover the fee.
t The information submitted with this application for license amendment has been reviewed by LACBWR committees as prescribed in Technical Specifications.
If there are any questions concerning this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE t
Frank Linder, General Manager FL: HAT:af Enclosure cc:
J. Keppler, Reg. Dir., NRC-DRO III MRC Resident Inspectors.
ra k
'L A Director of Nuclear Reactor Regulation September 12, 1980 ATTN:
Mr. Dennis M. Crutchfield LAC-7136 il Operating Reactors Branch #5 i
Division of Operating Reactors
. j
-.]
i n.
'I!
STATE OF WISCONSIN )
)
i COUNTY OF LA CROSSE)
Personally came before me this / TV day of September, 1980, the above named Frank Linder, to me known to be the person who executed the foregoing instrument and acknowledged the same, h
/n n
lam. V iUlaL>.
Notary Publiv,' La Crcsse County, Wisconsin.
My Commission Expires 2/26/84.
e i
I i l I