ML20148J486

Amend 13 to License DPR-3,including Change 118 to Tech Specs Re Addition of Provisions in Tech Specs for Trip Setpoints of Existing loss-of-flow Instrumentation & Addition of Effective Date for Meeting Original Delta P Requirements

ML20148J486
Person / Time
Site:	Yankee Rowe
Issue date:	07/16/1975
From:	Purple R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19291D047	List: ML20148J476 ML20148J486 ML20148J492 ML20148J496
References
NUDOCS 8011240153
Download: ML20148J486 (6)

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UNITED STATES.

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NUCLEAR REGULATORY COMMISSION

'W ASHIN GTON, D. C. 20Ss5

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YANKEEATOMICELECTRIdCOMPANY '

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DOCKET NO. 50-29

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YANKEE NUCLEAR POWER STATION (YANKEE-ROWE) 7:::

h-j AMENDMENT TO FACILITY OPERATING LICENSE p

q f=lE Amendment No. G j;t :lll License No. DPR-3 E:5 4EB Ec::M 1.

The Nuc1 car Regulatory Commission (the Commission) has found that:

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The application for amendment by Yankee Atomic Electric Company

.1 (the licensee) dated January 13, 1975, and supplemental letters

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dated February 19 and April 17, 1975, complies with the standards i

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and requirements of the Atomic Energy Act of 1954, as amended,

,0;;,,,, j (the Act), and the Commission's rules and regulations set forth if~~ j in 10 CFR Chapter I; j

s B.

The facility will operate in conformity with the application, (i

"E the provisions of the Act, and the rules and regulations of the Ce'nmission;

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C.

There is. reasonabic 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 Commission's regulations; and E

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.

2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3. A. (2) of Facility License No. DPR-3 is hereby amended to read as follows:

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(2) Technical Specifications r~

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The Technical Specifications contained in Appendix A, as revised, are hereby incorporated in the license.

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The. licensee shall operate the facility in acco; dance with the Technical Specifications, as revised by issued g:

.=t changes thereto through Change No.llB."

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' 3.

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

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4 FOR THE NUCLEAR REGULATORY C0bMISSION i.i E?

Origtnal signed by R. A. Purple E...

..,jg Robert A. Purple, Chief

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i Operating Reactors Branch #1 i"=

Division of Reactor Licensing EE #

Attachment

• Change No. !!@ to the

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Technical Specifications

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Date of Issuance: JUL 1 6 1975 4

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,."lll ATTACHMENT TO LICENSE AMENDMENT NO.13 E

-CHANGE NO.l $ TO THE TECHNICAL SPECIFICATIONS

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FACILITY OPERATING LICENSE NO. DPR-3

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Revise Appendix A as follows:

1.

Remove page 6 and insert attached revised page 6.

t 2.

Remove Table 1 and insert attached revised Table 1.

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TAB E 1 REACTOR PROTECTION CETPOINTS REMARKS NO. OF CHANNELS

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FUNCTION REQUIRED TO TRIP BYPASSES SET POINT LIMITS Minimum restart instrumen-HigA Startup Rate -

1 out of 2 Auto bypass 5.2 doc / min - max.

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cation 3

Above 15 MWe Reactor Scram 2 source range channels 2 intermediate range' channel t

High Neutron 2 out of 5 or 6 None Neutron flux corresponds to 108%

Minimum of 4 operable rated power - max.

channels required for

[ Flux Level -

reactor operation

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Reactor Scram 1 cf 4 (single)

Lov ?!ain Coolant 1 out of 2 None 1800 psig - min.

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& Pressurizer Pressure -

Reac' tor Scrams l Lou Main Coolant Not more than Manual bypass 80% of normal main cooland flow To be offective as of date og iFlow -

2 out of 4 Below 15 MWe in any loop - min.

startup with Core XII iReactor Scram 1 out of 3

liigh Pres'surizer 1 out of 1 Manual 200 inches - max.

In servit.e before in critical

Water Level -

! Reactor Scram fManual-Not applicable None Available any. time Reactor Scram '

! Turbine Trip -

Not applicable Manual bypass Usual Turbine Trip se't points Turbine-trip acrama redctor and trips ger.erator above Below 15 MWe

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! Reactor Scram 15 MWe Cencra tor Trip --

Not applicable Manual bypass Usual Generator Trip set points Generator trip _ scrams A.

reactor.and trips tur-

~Resctor Scram Below 15 MWe

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'bine above 15 MWe

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Steam Generrlor 2 out of 4' tfanual bypass Not lower than 15 inches below '

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Lou Water Level 2 out of 3 Below 1511We normal water level

Reactor Scram "Hanual Turbine Not applicable Manual bypass Available any time above 15 MWe

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Cenerator Trip -

Below 15 HWe

Reactor Scram Safety Injection 1 out of 3 or 4 Manusl 1700 psig on main coolant system.

Safety injection may b's min.; 5 psig vapor container initiated manually at.

0peration prennure, mix.

any time

! Pressurizer Not applicable None 24fl5 psig. No. 1 valve - max.

4Safet.y-Valve 25M pyin,No. 2 valve - max.

.JUL 161975 I,

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TABLE al(cent)

' ' 2' REACTOR PROTECTION SETPOINTS NO. OF CHANNELS FUNCTION REQUIRED TO TRIP BYPASSES SET POINT LIMITS-REPAIRS.

vapor Container 1 out of 2 None 5 psig vapor container pressure --

Closes trip valves.lin out-going lines in vapor.

max.

Outgoing Line Trip -

Valve Operation Hain Coolant Valve Not applicable None 30*F temperature differential -

Prevents any isolated loop from being-placed'into max.

Interlock

' operation if the loop _

temperature is more than 30*F lover than hir. hest cold leg temperature,.in the remaining loops i

1 Low Main Coolant 2 out of 4 Manual bypass Not less than 240 Amperes or more Flow -

1 out of 3 Below 15 MNe

~.han 360 Amperps-to the unin cool-Reactor Scram ant pump motors.

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e-JUL 7 o 197

_(1) At rated pswer, tha esiculated tempa(. ura of ths_ ccolagt '

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ct thsi,:1c sof the hoccast channsi shul not excesd 624 T. 3 a

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-(3) Ac rated pawse,. tha cciculetsd maximum clad-surfzca m

.' tem'gerature in the' hottest channal shall not exceed

'* 647 F."

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Main doolant' System

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(1)

The reactor shall be scrammed automatically above 15 s electric by a low main coolan,s pressure signal set at'a minimum of 1800 psig.

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(2) The reactor shall be scrammed, automatically above 15 MW s

electric by low main coolant flow' signals derived from 118 AP across the steam generators and main coolant' pump current.

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Low flow scram will be initiated by low flow in two of

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four loops.

When the plant is' operating with three

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loops, the low flow trip will be initiated by low flow-in any one 'of the1 three operating loops.

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-(3)' The reactor shall be scrammed autc=stically by high presi, surizer water level signal seu at a maximum of 200 inches before the reactor is critical.

(4)

The reactor shall not _ be brought to'eritica.11ty at a cUin coolant system temperature lower than 250 F cnd system pressura lower than 200 psig except for scheduled low powcr physics testing which shal'1 be performed in accordance with s

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written procedures."

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During normal plant startup boric acid dilutton shall not be commenced until the main coolant system temperature has reached ccuiltbrium at 250 ?.

-(6)

At zero power, except during physics testing, the moderator temperature coefficient shall not be positive.

M rated s teady s cate, power, the moderator tc=perature coef ficient shall be core

'egative thcn -0.5 x 10-4 b k/k.per *F."

n (7)

Tne main coolant synten pressure must not e.xeces 500 pssg until the temperature of the main coolant is at. least.600F above the. nil dacttiny temperature of the reactor vessel.

Pressures in excess of this at low temperatures may be injurious to the reactor vessel.

(8)

The main coolant syr. tom hcatup and cooldfown rate twst not exceed $00F/hr.

The pressurazer heatup and cooldo,tn rato must not exceed 2000F/hr.

(9) W'.cnever a main coolant loo.o is isolated from the system, it shall be borated at full shutdodn concentrations before it's temperature is reduced,3007 below the highest co;d 1cc j

temperature of the operating loops.

. "Following isolation of a main coolant i

loop,'when the loop

'. isolation valve and main coolant pump controls have been

.. removed from,scrvice and mechanically prevented from operation by lock and key,, the boron concentration in the isolated loc.p.

I may be reduced to that, existing in t,he c'ain coolant s pte.a at that time."

Not'6: The underlined requirement in D.2.d(2) to be effective as of date of startup with Core XII.

JUL 161975

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