ML20106F803

Amend 80 to License DPR-16,changing Tech Specs Re Station Electric Distribution Sys Voltages

ML20106F803
Person / Time
Site:	Oyster Creek
Issue date:	02/11/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20106F805	List: ML20106F803 ML20106F811
References
NUDOCS 8502140100
Download: ML20106F803 (9)

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r GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER AND LIGHT COMPANY OYSTER CREEK NUCLEAR GEhERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 80 License No. DPR-16 1.

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

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A.

The appli, cation for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the71censees) dated

. August 11, 1980 and supplemented October 18, 1982, December 5, 1983 February 9 and March 23, 1984 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 l

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;

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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 Cosmission'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 1

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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8502140100 850211 PDR ADOCK 05000219

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Accordingli,thelicenseisamendedbychangestotheTechnical Specifications as indicated in the attachment to this license amendment and. Paragraph 2.C(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:

(2) Technical Specifications 4.

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

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

FOR TH NUCLEAR REGULAT 1Y 0 MISSION

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L' John Zwolinski, Chief Opera ing Reactors Branch #5 Divis n of Licensing

Attachment:

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Changes to the Technical Specifications Date of Issuance: February 11, 1985.

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O-O ATTACHMENT TO LICENSE AMENDPENT NO. 80 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-206 Replace the following pages of the Appe'ndix A Technical Specifications with

'the enclosed page. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area. of change.

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Remove Page Replace Pa e

~2.3-3 2.3-3 2.3-8 2.3-8 3.1-11b 3.1-14 3.1-14 3.7-1 3.7-1

-4.1-6a 4.1-6a I

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2.3-3 FUNCTION LIMITING SAFETY SYSTEM SETTINGS

'C.

Reactor High,

<1060 psig Pressur,e, Scram D.

Reactor High Pressure.

2 a < 1070 psig Relief Valves Initiation 39[1090psig E.

Reactor High Pressure,

<1060 psig with time delay

. Isolation Condenser 3 seconds

' 'Initia' tion F.

Reactor High Pressure, 4 9 1212 psig

.,afety Valve Initiation 4 9 1221 psig.-

i 12 psi 4 9 1230 psig 4 9 1239 psig y

Line, MSIV Closure

->825 psia (initiated in IRM range 10)

G.

Low Pressure Main Steam H.

Main Steam Line Isolation

<10% Valve Closure from Valve Closure, Scram fiill open I.

Reactor Low Water Level,

>11'5" above the top of the Scram active fuel as indicated under nomal operating conditions J.

Reactor Low-Low Water

>7'2" above the top of the.

Level, Main Steam Line active fuel as indicated Isolation Valve Closure under normal operating conditions K.

Reactor Low-Low Water

>7'2" above tt e top of the l

Level, Core Spray active fuel Initiation

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Reactor Low-Low Water

>7'2" above the top of the Level, Isolation Con-Tctive fuel with time denser Initiation dela.y 1 3 seconds M.

Turbine Trip, 10 percent turbine stop Scram valvesfs) closure from full open M.

Generator Load Rejection, Initiate upon loss of oil Scram pressure from turbine acceleration relay O.

Recirculation Flow,

< 71.4 M1b/hr (117% of rated. flow)

Scran P.

Loss of Power

1) 4.16 KV Emergenc/ Bus 0 volts with 3 seconds !

Undervoltage (Loss of Voltage) 0.5 seconds time delay

2) 4.16 KV Emergency Bus 3671i1%(36.7) volts Undervoltage(DegradedVoltage) 10 10%(1,0)secondtime.

delay AmendmentNo./I,[.80 -

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_= _ - -

O-O 2.3 8 During periods when the reactor is shut down, decay heat is present and adequate water level must be maintained to provide core cooling. Thus, the low-low level trip point of 7'2" above the core is provided to actuate the core spray system to provide cooling water should the level drop to this point. In addition, the normal reactor feedwater system and control rod drive hydraulic syste;n provide protection for the water i

level safety limit bath when 'the reactor is operating at power and in the shutdown condition.

The turbine st'op' valve (s) scram is' provided to anticipate the pressure, neutron flux, and heat flux increase caused by the rapid closure of the turbine stop valve (s) and failure of the turbine bypass system.

The generator load rejection scram is provided to antic ~ip te the rapid increase in pressure and neutron flux resulting from fast closure of the 4

turbine control valves to a load rejection and failure of the turbine bypass system. This scran is initiated by the loss of turbine acceleration relay oil pressure. The timing for this scram is almost identical to the i

turbine trip.

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The total recirculation flow scram is provided to terminate a flow increase

, transient. Flow transients are normally protected against by employing the k, factor and using mechanical stops on the recirculation pumps. Oyster Cfeek does not have mechanical stops on its recirculation pumps and i

4 maximum flow is beyond the limit for which the k factor provides f

i protection. -Yhe recirculation flow s' cram is set to the maximum flow level correspq.nding to the k curvetobeused({ection3.10).

f The undervoltage protection system is a 2 out of 3 coincident logic relay system designated to shift emergency buses C and D to on site power should normal power be lost or degraded to an unacceptable level. The 4

trip points and time delay settings have been selected to assure an adequate power source to emergency safeguards systems in the event of a total loss of normal power or degraded conditions' which would adversely affect the functioning of engineered safety features connected to the plant emergency power distribution system.'

l References I

(1) FDSAR, Volume I, Section VII-4.2.4.2 -

l (2) FDSAR, Amendment 28 Item III.A-12 (3) FDSAR, Amendment 32, Question 13 (4) Letters, Peter A. Morris, Director, Division of Reactor Licensing, USAEC to' John E. Legen, Vice '

President, Jersey Central Power and Light Company, dated November 22, 1967 and January 9, 1968 (5) FDSAR, Amendment 65 Section B.XI.

(6) FDSAR, Amendment 65, Section R.IX.

w AmendmentNo.J!f,80 g

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1 TABLE 3.1.1 PROTECTIVE INSTRIBENTATIrH REQUIREllENTS (C0;gp) o llin.No.of i

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Min. No. of Operable 3

Reactor Modes Operable or Instrument

. _, in which Function Operating Channels Per Must bu Operable (Tripped) Trip operable

' Function Trip Setting _

Shutdowa Refuel Startup Run Syt,tems Trip Systems Action Required

• N.

Loss of Power

a. 4.16KV Emergency 1(ff)

X(ff)

X (ff) X(ff) 2 1

Bus Undervoltage i,

(Loss of Voltage)

.6 X(ffl X( ff) x (ff) x (ff]

2 3'

See, Note eh

b. 4.16 KV Emergency Bus undervoltage i

I (Degraded Voltage)

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j TABLE 3.1.1 (Cont'd) v.

These functions not required to be operable when the ADS is not required to be operable.

These functions must be operable only when irradiated fuel is in the fuel pool or reactor vessel w.

j and secondary containment integrity is required per specification 3.5.B.

y.

The number of operable channels may,be reduced to 2 per Specification 3.9-E and F.

The bypass function to permit scram reset in the shutdown or refuel mode with control' rod block z.

j must be operable in this mode.

aa. Pump circuit breakers will be. tripped in 10 seconds + 15% during a LOCA by relays SK7A and SK8A.

h bb. Pump circuit breakers will trip instantaneously during a LOCA.

cc. Only applicable during startup mode while operating in IRM range 10.

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i dd.

If'an isolation condenser inlet (steam side) isolation valve becomes or is made inoperable in the open position during the run mode comply with Specification 3.8.E.

If an AC motor-operated outlet (condensate return) isolation valve becomes.or is made, inoperable in the open position during the run mode comply with Specification 3.6.F.

ee. With the number of operable channels one less than the Min. No. of Operable Instrument Channels per Operable Trip; Systems, operation may proceed until perfomance of the next required Channel j..-

Functional Test provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ff. This function is not required to be operable when be associated safety bus is not required to be energized or fully operable as per applicable sections of these technical specifications.

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3. 7-1 3.7 Aux t t t :RY ' ELECTRICAL 80WER Aeolica:Ility:

Applies to the operating status of the auxilary electrical power supply.

Ob _iect i v e:

To assure tne operab ility' of the auxil iary electrical power supply.

Soec i f ication:

A.. The reactor snali not be made critical unless all of the following requiresepts are satistioc:

-mc 1.

The following buses or panels energized.

a.

4160 vcit buses 1C and ID in the turbine building switchgear room.

b.

460 volt buses 1A2,182,1A21,1821 vital MCC 1A2 anc 182 in tne reactor building switchgear room: 1 A3 and 183 at the intake structure; 1A21A, 1321A, I A213, and 1S218 and vital MCC 1AB2 en 23*6" elevation in the reactor building; 1A24 anc 1824.at the ' stack.

c. 208/120 voit panel s 3, 4, 4A, 48, 4C and V ACP-1 la tnd reacter nulleing switengear room,

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d. 120 volt protection panel I anc 2 in tne caole

room,

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e.125 voit DC distribution centers C and 3, anc

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panel 0, Panel DC-F, isolation valve motor control center DC-l and 125V DC motor control center DC-2.

f. 24 voit D.C. power panel s A and 3 En the cable room.

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2. One 230 KV line is. fully coerational and switen gear and both startup transformers are energizec to carry power to the station 4160 voit AC buses ene carry power to or away frds tne plant.

3. An accitional scurce of power consisting of one of the following is in service connectec To f eed the appropriate plan? 4160 V Dus or cuses:

a.

A second 230 KV line fully operational.

D.

Cne 34.5 KV line ful ly operational.

4 The station matteries 3 anc C are availacle f or normal service anc a. battery energar is in service for each oat *ery.

5. Bus tie breakers ED and EC are in the open position.

knendment No..Ad; JHI, 80

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.c Instrument Channel Check Calibrato Test I;emarks (Applies to Test 6 Calibration) 19.

Manual Scram Duttons NA NA 1/3 no 20.

liigh Temperature Main NA Each refuel-Each refuel-Using heat source box

.. Steamline Tunnel f

ing outage ing outage 1

4 21.

SRH ilsing built-in calibration equipment j

22.

Isolation Condenser liigh NA 1/3 no 1/3 mo j

FlowAP (Steam and k'ater)

By application of test pressure 23.

Turbine Trip Scram NA Eyery 3 mariths a

24.

Generator 1.oad Rejection NA Every Every Scram 3 months 3 months 25.

Recirculation 1.oop Flow NA Each Refuel-NA

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By application of test pressure ing Outage 26.

Low Reactor Pressure

,NA Every Every By application of test press,ure Cole Spray Valve 3 months 3 months Permissive 27.

Scram Discharge Volume' (Rod Block) e a) Water level high NA Each Refuel-Every 3 By varylag level in switch column.

W ing Outage months b) Scram trl'p bypass NA

• NA

' Ba' h refuel-c

'ing outage Loss of Power gg28.

EE a) 4.16 KV Emergency Daily 1/18 mos.

1/mo.

2*

Bus Undervoltage-

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(Loss of voltage) s P

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b) 4.16 KV Emeroency Daily 1/18 mos.

1/mo.

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• Calibrat prior to startt,p and nortnal shutdown and thereafter. check 1/s and test l'/wk until no longer E

required, i

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