ML19211D205
| ML19211D205 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/03/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19211D206 | List: |
| References | |
| NUDOCS 8001170053 | |
| Download: ML19211D205 (3) | |
Text
.
U"ITED STATES OF A"ER!CA NUCLEAR REGULATORY C0!:."ISSION In the Matter of
)
)
WISCONSIN ELECTRIC POWER COPPANY
)
Docket No. 50-266 (Point Beach Nuclear Plant,
)
Unit 1)
)
)
ORDER MODIFYING CONFIRMATORY ORDER OF NOVEMBER 30, 1979 I
Wisconsin Electric Power Conpany (the Licensee) is the holder of Facility Operating License No. DPR-?4 which authorizes the Licensee to operate the Point Beach Nuclear Plant, Unit 1, located in Two Creeks, Wisconsin, under certain specified conditions.
License No. OPR-24 was issued by the Atomic Energy Comission on October 5,1970, and is due to expire on July 25, 2008.
II Inservice inspections of the Point Beach Unit I steam generators perfomed during August 1979 and October 1979 outages have indicated extensive general intergranular attack and caustic stress corrosien cracking on certain of the external surfaces of the steam generator tubes.
The NRC Staff detemined in November 1979 that additional operating conditions would be required to assure safe operation prior to resumption of operation of Point Beach Unit 1 from a refueling outage.
Such conditions were imposed by Confimatory Order for Modification of License dated November 30, 1979.
In addition to those conditions, the Staff has now detemined that additional conditions are required to provide continued assurance that Point ' Beach Unit I can be 0;erated safety.
1761 340 8001170 Oh
. These acditicnal conditions are analyzed in a Staff Safety Evaluation :eport, dated this date, which is attached to this Order.
The Licensee has agreed to this condition by letter dated December 31, 1979.
III Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, and the Comission's Rules and Regulations in 10 CFR Part 2 and Part 50, IT IS HEREBY ORDERED THAT License *:o. DPR-24 be amended, in the manner hereafter provided, to include the following conditions in addition to those conditions listed in the Confimatory Order of November 30, 1979:
1.
Unit I will be operated at a reactor coolant pressure of 2000 psia with the associated parameters (i.e., overtemperature aT and low pressurizer pressure trip point) with the limits indicated in the Safety Evaluation Report appended to this Order.
2.
The licensee shall develop and follow the necessary procedures for operating Unit 1 at the conditions described in condition 1 above.
IV In view of the above, this amendment of License No. DPR-24 is made imediately effective.
Accordingly, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of receipt of this Order, the Point Beach Unit 1 facility shall be operated at a reactor coolant system pressure of 2000 psia within the parameters described above.
1761 341
l Any person.. hose interest may be affected by this Order may within ttenty days of the date of this Order request a hearing with respect to this Order.
Any such request shall not stay the effectiveness of this Order.
Any request for a hearing shall be addressed to the Director of Nuclear Reactor Regulation, U. S.
Nuclear Regulatory Conmission, Washington, D. C.
20555.
In the event a hearing is requested, the issues to be considered at such hearing shall be:
- 1) Whether the facts stated in Section II of this Order are correct; and
- 2) Whether this Order should be sustained.
FOR THE NUCLEAR REGULATORY COMMISSION
/
M Harold Denton, Di rector Office of Nuclear Reactor Regulation Attachnent:
Staff Safety Evaluation Report, dated January 3,1980 Effective date: January 3,1980 Bethesda, Maryland i761 342
S METY E"flUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PELATED TO THE POINT BEACH UNIT 1 STEAM GE*;ERATOR TUBE DEGRADATION DUE TO DEEP CREVICE CORROSION WISCCNSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNIT NO.1 DOCKET NO. 50-266 INTRODUCTION Wisconsin Electric Power Company (the licensee) has requested changes to the Technical Specifications of Point Beach Units 1 and 2 to alls operation at either 2000 or 2250 psia (Reference 1).
These changes include (1) defining over-temperature - aT trip equation for each operating pressure, and (2) redefining the low pressure trip to allow adequate operating margin when operating at the 1ower pressure (2000 psia).
Although 2250 psia is the design operating pressure, both units have been previously operated at the lower pressure.
A brief history of the previous operation of Point Beach Units 1 and 2 is given by the licensee in References 1 and 7 outlining the reasons for changing the pressure, the dates at which these changes were made and providing the references to the various Amendment requests for NRC and the subsequent Staff Safety Evaluation Reports. Presently both units are operatiag at 2250 psia.
The licensee requested the change to pennit operation at 2M0 psia to reduce stress on the steam generator tubes.
This change to a lower pressure adversely affects the departure from nucleate boiling ratio (DNBR) and requires justification that the reactor is still adequately protected.
The proposed change in the over temperature - aT(OTaT) trip provides this protection for some cases.
For situations where the OTAT trip does not operate, adequate protection must be shown by other analysis.
The loss of flow and rod drop events are two events in which ONBR protection is provided by means other than the OTaT trip.
Modification of the reactor low pressurizer pressure trip to provide more margin between the lower operating pressure and this trip also requires justification that the applicable criteria for transient and accident anslyses are still satisfied.
DUPLICATE DOCUMENT Entire document previ ously 1,761 343 enterea into system under:
,J O
O ANO v
No. of pages:
/
r