ML20024C175
| ML20024C175 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/05/1983 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20024C176 | List: |
| References | |
| TAC-52692, NUDOCS 8307120364 | |
| Download: ML20024C175 (2) | |
Text
e Wisconsin Electnc roara couraur 23i i Mic:llGAN, P.O. BOX 2046, MILWAUKit. WI 53201 July 5, 1983 CERTIFIED MAIL Mr'.
H.
R.
Denton, Director Office of Nuclear Reactor Regulation U.
S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr.
R.
A.
Clark, Chief Operating Reactors, Branch 3 Gentlemen:
DOCKET 50-266 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 90 STEAM GENERATOR REPLACEMENT POINT BEACH NUCLEAR PLANT, UNIT 1 In accordance with the provisions of 10 CFR 50.59, Wisconsin Electric Power Company, Licensee for Point Beach Nuclear Plant Unit 1 hereby modifies its application for an amendment to Facility Operating License DPR-24 as filed by letter dated May 27, 1982 to include the below described changes to the Point Beach Unit 1 Technical Specifications.
As you know, Licensee's letter dated May 27 provided the NRC notification that Wisconsin Electric was planning to repair the two Point Beach Unit 1 steam generators by a replacement of major components during the unit outage commencing in the fall of 1983.
We concluded that since this repair involved a replacement / repair of facility equipment, rather than an alteration or change to the facility, prior NRC approval pursuant to 10 CFR 50.59 was not required.
In a letter dated July 6, 1982 you notified Licensee that the NRC had determined that repairs of this magnitude and scope could not be conducted pursuant to 10 CFR 50.59 without prior NRC approval and that you would treat Licensee's May 27 letter as an application for amendment to the facility operating license.
As subsequently discussed in supplerrental information provided describing the proposed repair, replacement of the major components of the Point Beach Unit 1 steam generators will restore the steam generators to their original operational capabilities.
Accordingly, we are requesting in this modification to our license amendment application certain changes to the Point Beach Unit 1 Technical Specifications which will provide the same operational flexibility for Point Beach Unit 1 as is presently approved for Point Beach Unit 2.
These changes are described further as follows:
1.
Specification 15.2.3:
The low pressurizer pressure l
and overtemperature AT constants have been revised p
to permit operation at either 2000 or 2250 psia 3 (k primary system pressure.
y' 8307120364 830705
~1-h PDR ADOCK 05000266 P
PDR l
l
Mr. H.
R.
Denton July 5, 1983 2.
Specification 15.3.1.G:
The operational limitations have been revised to permit operation at 2000 or 2250 psia primary system pressure.
3.
Specification 15.4.3:
This specification is revised to specify primary system leak test pressures for operation at 2000 or 2250 psia.
These proposed changes have been identified on the attached Technical Specification pages by margin bars.
In each case the proposed change serves to modify the Unit 1 specification to become identical to the existing Unit 2 specification.
As required by 10 CFR 50.91(a) (1), Licensee has determined that these proposed changes do not involve a significant hazards consideration.
This determination is based on the past approval by the NRC of operation of Point Beach Unit 2 at either 2000 or 2250 psia primary system pressure on April 29, 1980.
That approval concluded that such operation did not involve a significant hazards consideration.
Licensee has been advised by your staff that in accordance with the schedule of amendment approval fees for reactor facility licenses as listed in 10 CFR 170.22 this license amendment approval, which includes the Commission's review of the Point Beach Unit 1 steam generator repair and these proposed Technical Specification changes, will involve a Class IV approval since several environmental, safety, or other issues which involve no significant hazards considerations are involved.
We have therefore enclosed a check in the amount of $12,300 as payment for the requisite Class IV approval fee.
As further specified in the Commission's regulations, we enclose herewith three signed originals and 40 copies of this modification to our license amendment application.
Please contact us if you have any question regarding this submittal.
Very truly yours, b
}l+/
)
C. W.
Fay Vice President-Nuclear Power Attachments (Check No. 737384)
Copies to NRC Resident Inspector C.
F.
Riederer, PSCW Subscribp] day and sworn to before me this ef' f July 1983.
~
Notary Public, State of. Wisconsin
~
My Commission expires 7-/7-f3..
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