ML20195C511

Amend 109 to License DPR-3,deleting Refs to Mode 5 in Tech Spec Tables 3.3-2 & 4.3-2

ML20195C511
Person / Time
Site:	Yankee Rowe
Issue date:	06/13/1988
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195C489	List: ML20195C483 ML20195C511 ML20195C585
References
NUDOCS 8806220217
Download: ML20195C511 (7)

Text

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UNITED STATES E n NUCLEAR REGULATORY COMMISSION 7,; E WASHINGTON, 0. C. 20555

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YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO.50-029 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. OPR-3

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

A. The application for amendment by Yankee Atomic Electric Company (the licensee) dated March 25, 1988 complies with the standards l

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; l

l 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 Connission's regulations; D. The issuance of this amendment will not be inimical to the common 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, f 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:

8806220217 880613 PDR ADOCK 05000029 P PDR

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(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 109 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Richard H. Wessman, Director Project Directorate I-3 Division of Reactor-Projects 1/II

Attachment:

Changes to the Technical Specifications Date of Issuance: June 13,1988 I

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i-ATTACHMENT TO LICENSE AMENDMENT NO.109 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO.50-029 Revise Appendix A Technical Specifications by remcving the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4 3-12 3/4 3-12 3/4 3-12A 3/4 3-12A 3/4 3-15 3/4 3-15 3/4 3-15A 3/4 3-15A l

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TAB LE 3.3-2

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ENGINEERED SAFEGUARDS SYSTEN INSTRUMENTATION I

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MINIMUM

! CilANNELS CalANNELS TOTAL NO. APPLICABLE -

AND SENSORS AND SENSORS OF CllANNELS ff0 DES ACTION TO TRIP . OPERAHLE AND SENSORS FUNCTIONAL UNIT

1. SAFETY INJECTION 1 1 1(3), 2(3), 3(2)(3) 10 I

a. Actuation Channel #1 .

1) RPS Low Main Coolant - 1 1 1(3), 2(3), 3(2)(3) 10 1

Loop 1 Pressure Channel .

2) liigh Containment 1 1 1(3), 2(3), 3(2)(3) 10 1

Pressure Sensor 1 1 1, 2, 3, 4, 5(l) 10 1

, 3) Manual Initiation (

1 1 1(3) , 2(3), 3 10 1

b. Actuation Channel #2 I, 1) RPS Low Main Coolant - 1 1 1(3), 2(3), 3(2)(3) 10

• • Loop 2 Pressure Channel 1

2) liigh Containment '

1 1 1(3), 2(3), 3(2)(3) 10 1

Pressure Sensor 1 1 1 1, 2, 3, 4, 5(1) 10

3) Manual Initiation

2. CONTAlfCfENT ISOLATION 1 1,2,3,4 10 2 1 2'y a. Manual Initiation og 1,2,3,4 10 1 1 1

Q b. Actuation Channel A .

g 1) liigh Containment 1,2,3,4 10 1 1 1

" Pressure Sensor 5

2) Safety Injection

( All S.sf ety Injection Initiating Functions and Requiremento)

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TABLE 3.3-2 (Continued)

E ENCINEERING SAFECUARDS SYSTER INSTRUMENTATION 2

MINIMUM TOTAL NO. CilANNELS CitANNELS OF CIIANNELS AND SENSORS AND SENSORS APPLICABLE FUNCTIONAt. UNIT AND SENSORS, TO TRIP OPERABLE MODF.S ACTION

2. CONTAINNENT ISOLATION (continued)

c. Actuation Channel B 1 1 1 1.2.3.4 10

1) liigh Containment ,

I 1 1 1.2.3.4 10 Pressure Sensor

2) Safety Injection (All Safety injection Initiating Functions and Requirements)

3. MAIN STEAM ISOLATION Y Low Steam Line Pressure 3/ Steam Line 2/ Steam Line 3/ Steam Liste 1. 2. 3(2) 6**

- n.

b. Automatic Trip Logic 2 1 2 1. 2. 3(2) 8

c. Manual Initiation 2 1 2 1. 2 8

d. High Containment Pressure 2 1 2 1. 2 8 TrlP Containment Isolation 8$ 4. LOSS OF POWER g 480 VOLT EMERCENCY BUS 1, 2. 3 23 h a. Lona of Voltage (First Level) 1/ Bus 1/ Bus 1/ Bus

,,na

=c Degraded Voltage (Second Level) 2/ Bus 2/ Bus 2/ Bus 1. 2, 3 "

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D- tan!.E- 4. 3 - 2 Ei rn ENGINEERED SAFECl!ARDS SYSTEM ItFgTRUMEt!TATION y

SURVEll.l.ANCE REQUlill0lEllr$

9 ed CilANNEL MODES IN WilICit CilANNEL FU NCTIONAL SURVEILLANCE CllANNEL -

CilECK UALIBRATION TEST REQUIRED FUNCTIONAL UNIT

1. SAFETY INJECTION N.A. M(1) 1, 2, 34 S

a. Actuation Channel il

1) RPS low Kiin Coolant - S R(3) M 1, 2, 3,#

Loop 1 Pressure Channel .

2) liigh Containment 1, 2, 34 S R(3) M(3)

Pressure Sensor N.A. R 1, 2, 3, 4, 5*

N.A.

3) Kinual Initiation u N.A. M(1) 1, 2, 3#

S O b. Actuation Channel #2

1) RPS low Main Coolant - S R(3) M 1, 2, 37 loop 2 Pressure Channel .

2) liigh Containment 1, 2, 3&

S R(3) M(3)

Pressure, Sensor N.A. N.A. R 1, 2, 3, 4, 5*

3) Minual Initiatton A 2. CONTAltMENT ISOLATION 2 R 1,2,3,4 N.A.

5 *

a. Manual Initiation N.A.

S N.A. M(4) 1, 2, 3, 4

b. Actuation Channel A og 1) litgh Containment 1, 2, 3, 4

- Pressure Sensor S N.A. M(3)

$ 2) Safety Injection ( All Safety Injection Surveillance Regulrements)

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$ TABLE 4.3-2 (Continued) x r.,

ENGINEERED SAFECUARDS SYSTEM INSTRUMENTATION

$ SURVEILLANCE REQUIREMENTS si CHANNEL MODES IN WHICH CHANNEt, CHANNEL FUNCTIONAL UNIT FUNCTIONAL SURVEILLANCE CHECK CALIBRATION ,

TEST REQUIRED

2. CONTAINMENT ISOLATION (Continued)

c. Actuation Channel B S NA M(4) 1, 2, 3, 4

1) High Containment S R(3) M(3) 1, 2, 3, 4 Pressure Sensor .

}' 2) Safety Injection i

M* (All Safety Injection Surveillance Requirements) -

3. MAIN STEAM ISOLATION Y

a. Low Steam Line Pressure S 1.

R(3) M(3) 1, 2

b. Automatic Trip Logic NA NA Q 1, 2

c. Manual Initiation NA NA R 1, 2 j d, High Containment Pressure NA NA R 1, 2 4*

LOSS OF POWER De 480 VOLT EMERGENCY BUS e{

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. a. Loss of Voltage (First Level) NA R R I , 2, 3 i

b. Degraded Voltage (Second Level)

. N NA R H 3. 2. 3

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