ML20058L028

Amend 133 to License DPR-3,incorporating Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4

ML20058L028
Person / Time
Site:	Yankee Rowe
Issue date:	08/02/1990
From:	Nerses V Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058L026	List: ML20058L024 ML20058L028 ML20058L032
References
NUDOCS 9008060062
Download: ML20058L028 (5)

Text

!

• +[ prion *\\,

UNITED STATES 8 *, ',

'g NUCLEAR REGULATORY COMMISSION

.-l.

w Ass NG TON, D. C. 20$55 g.'

8

%,, s,.....,o YANrEE ATOMIC ELECTRIC COMPANY DOCKET NO.50-029 YANKEE NUCLEAR POWER STATION AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 133 License No. DPR-3 1.

The Nuclear Regulatory Comission (the Comission or the NRC) has found that:

A.

The applie: tion for amendment filed by Yankee Atomic Electric Company (the licensee) dated May 31, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance: (1) that the activities authorized by this amendment can be conductec without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifice-tions as indicated in the ettachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.133, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

+008060062 900a02

{DN ADOCK 050000p9 FDC

c,

{c 2

3.

This license amendment is effective as of August 2, 1990.

FOR THE NUCLEAR REGULATORY COMMISSION 4 Victor Herses, Acting Director 3

Project Directorate 1-3 I

Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 2, 1990 s

e t

t o

ATTACHP.ENT TO LICENSE AMENDMENT NO. 133 FACILITY OPERATING LICENSE NO. OPR-3 DOCKET NO.50-029 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4 10-3 3/4 10-3 3/4 10-4 3/4 10-4 4

~

?

SPECIAL TEST EXCEPTIONS PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.10.3 The minimum temperature and pressure conditions for reactor criticality of Specification 3.4.8.1 may be suspended during low temperature PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed 2 percent of RATED THERMAL POWER, b.

The resctor high setpoint trips on the OPERABLE Power Range Nuclear Channels and the reactor high setpoint trips on the OPERABLE Intermediate Power P.ange Nuclear Channels are set at 125% of RATED THERMAL POWER, and c.

The Main Coolant System temperature and pressure are maintained 1250*F and 1300 psig, respectively.

APPLICABILITY: MODE 2.

ACTION:

a.

With the THERMAL POWER >2 percent of RATED THERMAL POWER, immediately

• open the reactor trip breakers.

b.

With the Main Coolant System temperature and pressure <250'F or

<300 psig, immediately open the reactor trip breakers and restore the temperature-pressure to within its limit within 30 minutes; perform the analysis required by Specification 3.4.8.1 prior to the next reactor criticality.

SURVEILLANCE REOUIREMENTS 4.10.3.1 The Main Coolant System temperature and pressure shall be verified to be 1250'F and 1300 psig at least once per hour.

4.10.3.2 The THERMAL POWER shall be determined to be 12% of RATED THERMAL POWER at least once per hour.

4.10.3.3 Each Power Range and Intermediate Power Range Nuclear Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating low temperature PHYSICS TESTS.

YANKEE-RCWE 3/4 10-3 Amendment No. #7, #7, 50, 130, 133

a SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITINO CONDITION FOR OPERATION 3.10.4 The limitations of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.4, and 3.1.3.5, may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed 2% of RATED THERMAL POWER, and b.

The reactor high setpoint trips on the OPERABLE Power Range Nuclear Channels and the reactor high setpoint trips on the OPERABLE Intermediate Power Range Nuclear Channels are set at 125% of PATED THERMAL POWER.

APPLICABILITY: MODE 2.

ACTION:

With the THERMAL POWER >2% of RATED THERMAL POWER, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be 12% of rated THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.4.2 Each Power Range and Intermediate Power Range Nuclear Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

YANKEE-ROWE 3/4 10-4 Amendment No. 47, if6, 133

.