ML20154J762

Amend 107 to License DPR-3,adding Surveillance Requirements to Tech Specs Re 480-volt Emergency Buses

ML20154J762
Person / Time
Site:	Yankee Rowe
Issue date:	05/18/1988
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154J758	List: ML20154J753 ML20154J762 ML20154J766
References
NUDOCS 8805270124
Download: ML20154J762 (7)

Text

),h UNITED STATES NUCLEAR REGULATORY COMMISSION 5

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l W ASmNGTON, D. C. 20555

%, ~ f YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO.50-029 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. DPR-3 1.

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

A.

The application for amendment by Yankee Atomic Electric Company (the licensee) dated January 5, 1988 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 (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 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 Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:

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2

(?) Technical Specifications The Technical Specifications contained in Aprendix A as revised through Amandment No.107. are hereby incorporated in the licer e.

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

3.

This license amandment is effective as of the date of its issuanc?.

FOR THE NUCLEAR REGULATORY COMv!SSION C

Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 18, 1988 i

i

ATTACHMENT TO LICENSE AMENDMENT N0.107 FACILITY OPERATING LICENSE NO. OPR-3 00CKET NO.50-029 Revise Aprendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendmer' number and contains marginal lines indicating the area of change.

REMOVE INSERT 3/4 3-12A 3/4 3-12A 3/4 3-13A 3/4 3-14A 3/4 3-14A 3/4 3-15A 3/4 3-15A t

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TABLE 3.3-2 (CONTINUED)

ENGINEE' RING SAFEGt!ARDS SYSTEM INSTRUMENTATION re E

TOTAL NUMBER CHANNELS filNIMUM CllANNELS OF CllANNELS AND SENSORS AND SENSORS APPLICAHLE

o FUNCTIONAL UNIT AND SENSORS TO TRIP OPERABLE MODES ACTION E"

2.

CONTAINMENT ISOLATION (Continued) c.

Actuation Channel B 1

1 1

1, 2, 3, 4, 5(l) 10 (1) High Containment I

i 1

1, 2, 3, 4, 5(1) 10 Pressure Sensor (2) Safety Injection (All Safety Injection Initiating Functions and Requirements) uY 3.

MAIN STEAM ISOLATION a.

Low Steam Line Pressure 3/ Steam Line 2/ Steam Line 3/ Steam Line 1, 2, 3(2) 6**

1 b.

Automatic Trip Imgic 2

1 2

1, 2, 3(2) 8 c.

Manual Initiation 2

1 2

1, 2 8

2 1

2 1, 2 8

d.

Nigh Centetsument Pressure Trip Centeinnent Isoletten o" >

",3 4.

LOSS OF POWER 480 VOLT EMERCENCY BUS S

Loss of Voltage (First Level) 1/ Bus 1/ Bus 1/ Bus 1, 2, 3 23 a.

1 b.

Degraded Voltage (Second Level) 2/ Bus 2/ Bus 2/ Bus 1, 2, 3 22**

k..

9 x

i ACTION STATEMENTS (continued) 23.

With t.he number of OPERABLE channels or sensors one less than the total i

number of channels or sensors, restore the inoperable bus to operable status within eight hours or be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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i YA102E ROWE 3/4 3-13A Amendment No.107 8

TABLE 3.3-3 (Continuod)

~

ENGINEERED SAFEGUARDS SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT 4

LOSS OF POWER 480 Volt Emergency Bus (a) Loss of Voltage (First Level) 1.8 1 0.20 seconds after Emergency Bus No. 1, 2, 3 voltage drops to ZERO volts from 1420 volts 3.0 ! 0.33 seconds after voltage decreases to 276 volts (b) Degraded Voltage (Second Level) 2 5 Volts 4

1.

480 V Bus 4-1, Bus 5-2, Bus 6-3 429 Time Dela-j 10 il Seconds 2 5 Volts 2.

480 V Emergency Bus No. 1, Emergency 421 4

Bus No. 2. Emergency Bus No. 3 Time Delay 10 il Seconds t

i 4

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1 YANKEE ROWE 3/4 3-14A Amendment No. #4,107 l

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TABLE 4.3-2 (CONTINUED) y ENGINEERED SAFECUARDS SYSTEM INSTRilMFNTATION SURVEIL 1)NCE REQUIREMENTS

's CilANNEL MODES IN WilICll

n 2

CllANNEL CilANNEL FUNCTIONAL SURVEILLANCE (8

FUNCTIONAL UNIT CilECK _

CAI.IBRATION TEST REQUIRED 2.

CONTAINMENT ISOLATION l

(Continued) c.

Actuation Channel B S

NA M(4) 1,2,3,4,5*

(1) High Containment S

R(3)

M(3) 1, 2, 3, 4, S*

Pressure Sensor (2) Safety Injection (All Safety Injection Surveillance Requirements)

U 3.

MAIN STEAM ISOLATION Y

1, 2 G

a.

Low Steam Line Pressure S

R(3)

M(3) b.

Automatic Trip Logic NA NA Q

1, 2 c.

Manual Initiation NA NA R

1, 2 d.

High Containment NA NA R

1, 2 Pressure 3e 4.

LOSS OF POWER N*

480 VOLT EMERCENCY BUS W

a.

Loss of Voltage (First Level)

NA R

R 1, 2, 3 y

b.

Degraded Voltage (Second Level)

NA R

M 1, 2, 3

.R 2

.