ML20062B734

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Amend 132 to License DPR-61,adding Footnote to Tech Spec Table 3.3-2,Item 3,Table 3.3-3,Item 2 & 4.3-2,Item 3
ML20062B734
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 10/22/1990
From: Boger B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062B733 List:
References
NUDOCS 9010260105
Download: ML20062B734 (6)


Text

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o, UNITED 8TATES i

NUCLEAR REGULATORY COMMISSION 1

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.t WASHINGT oN, D. C. 20656

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CONNECTICUT YANKEE ATONIC POWER COMPANY DOCKET NO. 50-213 f

i HADDAM NECK PLANT AMENDhENT TO FACILITY OPERATING LICENSE

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Amendment'No.132 License No. DPR-61 l

t 1.

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

A.

The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated August 25, 1990, and as supplemented in a letter dated August 29, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth -

in 10 CFR Chapter I; B.

The facility will operate in conformity with the appli-cation, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i)-that the activities authorized by this amendment can be conducted without i

endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with-the Commission's regulations; i

D.

The issuance of this amendment will-not be inimical to the u

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common defense and security or to the health and safety of l'

the public; and E.

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

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i

and paragraph 2.C.(2) of Facility Operating License No. OPR-21 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications _ contained in Appendix A, as revised through_ Amendment No.132, are hereby incorporated in the license.

The licensee shall operate the facility in i

accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be I

implemented within 30 days of issuance.

4 FOR THE NUCLEAR REGULATORY COMMISSION Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projects - I/II 5

Office of Nuclear Reactor Regulation

~

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 22, 1990 f

a 6

l ATTACHMENT TO LICENSE AMENDMENT NO.132 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET No. 50-213 l

Replace the following pages of the Appendix "A" Technical Specifications with

)

the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert J

1 3/4 3-15 3/4 3-15 3

l 3/4 3-19 3/4 3-19 l

i 3/4 3-21 3/4 3-21

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TABLE 3.3-2 (Continued)

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t l-g ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTAT;0N i

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-]

MINIMUM l

TOTAL NO.

CHANNELS CHANNELS-APPLICABLE FUNCTIONAL' UNIT OF CHANNELS TO ACTUATE OPERA 8LE MODES ACTION

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a 3.

~ Auxiliary Feedwa}er*

I I

a.

Wide Range Stm. Gen. Water Level--

Low

1) Four Loops 8

2 Channels 8

1(a)(b) 21

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Operating in any one train L

2)fThreeLoops 6

2 channels 6

1(a)(b) --

. 26 Operating in any one train R.

I *)

26 l

I b.

Trip of All Main 1/ pump 1 from each 1/ pump l.

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'Feedwater Pumps pump

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Emergency Bus Undervoltage

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1 a.?4.16 kV Bus Under-3/ bus 2/ bus 2/ bus.

1, 2,-3, 4 24 l

voltage-level 1:

'1 b..E4.16 kV Bus Undervoltage-

_2/ bus 2/ bus 1,-2,.3, 4 24-

.3 l Level 2.

3/ bus L

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'c.

4.16 kV'. Bus Undervoltage-

..3/ bus

'2/ bus 2/ bus 1, 2 24

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Level'3

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For Cycle 16 operation only, OPERA 8ILITY of automatic initiation of auxiliary feedwater. (AFW) is defined as

~O including (1) credit for. operator action:to adjust AFW to full required flow following automatic initiation and 5

(2)' reliance on the control air system to ensure. successful automatic AFW initiation. Modifications will be

implemented by the end of the Cycle 16 refueling ~ outage, prior to startup for Cycle 17, to remove reliance on:

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operator action and the control air system for successful automatic initiation of AFW.

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i TABLE 3.3-3

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B EtlGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS

.o E

l M-FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE n

I

.x

. Safety Injection (Reactor Trip, 1.

Start Diesel Generators, l

Containment Isolation).

I a.

Manual Initiation M.A.

N.A.

b.

Containment Pressure--High 54.7 psig

$5.0 psig c.

_ Pressurizer Pressure--Low 21720 psig 11700 psig 2.

Steam Line: Isolation i

R a.

Steam Flow in Two Steam-

$108% of full *

<110% of full

  • Lines--High steam flow.

steam flow.

V l!

g 3.

- Auxiliary Feedwater**

-a.-

. Steam Generator Water-247% of wide.

245% of wide Level--Low range instrument range instrument span.

span.

b.

Trip of All Main Feedwater Pumps N.A.

N.A.

4j

. For Cycle 16 operation only, OPERABILITY of automatic initiation of auxiliary feedwater (AFW)~ is defined as including (1) credit for operator action to adjust AFW to full required flow following automatic initiation and a

(2) reliance on the control air system to ensure successful automatic AFW initiation. Modifications will be

' implemented by the end.of the Cycle 16 refueling outage, prior to startup for Cycle 17, to remove reliance on g

. operator action:and the control-air' system for.suc;essful automatic initiation of AFW.

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+ + ~ - - - - - - - - - - - - - - - - - - - - - - - - - -

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TABLE 4.3-2 b'

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g

SURVEILLANCE REQUIRENENTS MiR TRIP ANALOG ACTUATING MODES FGR CHANNEL

-DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL SURVEILLANCE CHANNEL CHECK CALIBRATION TEST TEST IS REQUIRED FUNCTIONAL UNIT 1.

Safety Injection (Reactor Trip, Start Diesel-Generators, Containment Isolation) a.

Manual Initiation N.A.

N.A.

N.A.

R 1,2,3 b.

Containment Pressure-D R

SW.

N.A.

1, 2, 3 R

. iligh Y-c.

Pressurizer Pressure-S

'R SW N.A.

1, 2, 3 5

Low 2.

Steam Line Isolation a.

Steam Flow in Two S

R R

'N.A.

1, 2, 3 Steam Lines-High 7

.3.

Auxill'ary Feedwater*

l g.

-a.

Steam Generator Water-

-S R-iM N.A.

1

Level-Low F
b. ' Trip of All Main:

N.A.-

N.A..

N.A.

R-1 Feedwater Pumps R;'

For Cycle 16 operation only, OPERABILITY of automatic initiation of auxiliary feedwater (AFW) is defined as

=~

including (1) credit: for operator' action to adjust AFW to full. required flow following automatic initiation and C

(2)-reliance on the control' air system.to ensure successful automatic AFW initiation.. Modifications will be implemented-by-the end of the Cycle 16 refueling outage, prior to startup for Cycle 17, to remove reliance on

- operator ~ action 'and the control air system for successful automatic initiation of AFW.

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