Text

Proposed Tech Specs Re Instrumentation Sys
	ML20005F143
Person / Time
Site:	Yankee Rowe
Issue date:	01/05/1990
From:	; YANKEE ATOMIC ELECTRIC CO.
To:	;
Shared Package
ML20005F141	List: ML20005F140; ML20005F143;
References
	NUDOCS 9001120339
	Download: ML20005F143 (18)
	v • d • e

,

TARTY 3.3-1 3w

=*

REACTOR PROIECTIVE SYSTEN INSTRGENTATION

PFJ h g8-am-n

stS $

TOTAL NO.

CHANNELS CHANNELS APPLICABLE g,,oEi ITINCTIONAL UNIT OF CHANNELS To mP OPERABLE fEDES ACIEg 8

1.

Nnual Reactor Trip 3

1 3

1, 2, and

1 g

g ts l

y 2.

Power Range, Neutron Flux and 6

2 4

1(1), 2, and

2**

Intermediate Power Range, Neutron Flux 3.

Intermediate Range, Neutron Flux, 2

1 2

1(2), 2, and

3 High Startup Rate 4.

Source Range, Neutron Flux,

a. Startup 2

NA 2

28 and *(5) 4 N

[

b. Shutdown 2

NA 1

3, 4, and 5(5) 5 5.

Low k in Coolant Flow (SGAP) 4 2

3 1(3) 6**

6.

Iow Main Coolant Flow (MC Pump Current)

a. System A 4

2 3

1(3) 7*

${

b. System B 4

2 3

1(3) 7**

E 7.

High Main Coolant System Pressure 3

2 3

1 and 2(4) 6**

f 8.

Low Main Cools.c System Pressure 3

2 3

1 and 2(4) 6**

E 9.

Intentionally Blank

,E 10.

Low Steam Generator Water level 4

2 3

1(3) 6**

C w

TARTI 3.3-1 (Conti")

w

.h REACTOR PROTECTIVE SISTEM INSTRUMENTATIM m

l MINIMDM' 5

IUTAL NO.

CHANNE1S CHAMMIS AFFLICABLE l

N FUNCTIONAL UNIT OF CEANNELS TO TRIP OPERABLE unmc gggg I

11.

Turbine Trip 1

1 1

1(3)(6) g i

12.

Generator Trip 1-1 1

1(3)(7) 8 13.

Reactor Trip Breaker 2

1 2

1, 2, and

9 14.

Automatic Trip Logic 2

1 2

1, 2, and

24 15.

Main Steam Isolation Trip Iogie 2

1 2

1 and 2(')

25.

16. Nuclear Instrumentation Trip logic 2

1 2

1(1)(2), 2,

{

and

24 Y

w 8

a

BBLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

High voltage to detector is automatically energized prior to the Intermediate Range decreasing below 5 x 10-10 amperes.

Or when other activities might increase reactivity.

(1) Power Range Neutron Flux Low Setpoint Trip, which is associated only with the three Power Range Channels, may be manually bypassed at 215 MWe.

Bypass shall be manually removed prior to decreasing below 15 MWe.

l l

(2) Intermediate Range Neutron Flux High Startup Rate Trip is automatically bypassed 115 MWe.

Bypass is automatically removed prior to decreasing below 15 MWe.

(3) Trip may be manually bypassed 115 MWe.

Bypass is automatically removed prior to increasing above 15 MWe.

(4) Trip may be manually bypassed when the reactor is not critical.

(5) 'Startup rate alarm setpoint 11.1 decade / minute.

(6) Turbine shall be protected by at least the following protective trips:

rotor excessive axial movenent, low bearing oil pressure; low condenser vacuum; and overspeed.

(7) Generator shall be protected by at least the following protective trips overcurrent; differential; and loss of field.

ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

j YANKEE ROWE 3/4 3-4 Amendment No. 83

TARLE 3.3-1 (continued)

ACTION SIAIEtiENIS. (Corttinued

' ACTION 2 -

I l

a.

With two Power Range and/or Intermediate Power Range channels inoperable and with the THERMAL POWER 12% of RATED THERMLL j

POWER, set the power range high neutron level scram logic for single. channel operation for both the Power Range and Intermediate Power Range instrumentation.

j b.

With one Power Range or one Intermediate Power Range channel j

inoperable and with the THERMAL POWER level >2% of RATED THERMAL POWER, POWER OPERATION may continue at the existing j

THERMAL POWER level provided the power range high neutron 1cvel scram logic is set for single channel operation for the i

RPS instrumentation group containing the inoperable channel.

i c.

With two Power Range channels, or two Intermediate Power Range channels, or one Power Range and one Intermediate Power Range channels inoperable and with the THERMAL POWER level >21 of 4

RATED THERMAL POWER, POWER OPERATION may continue at the existing THERMAL POWER level provided the power range high neutron level scram logic is set for single c M nnel operation for both the Power Range and Intermediate Po ter Range instrumentation.

d.

One power range high neutron level scram logic may be reset for coincidence operation in a, b, and c above for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per channel for surveillance testing per l

Specification 4.3.1.1.

ACTION 3 - With the number of OPERABLE channels one less than the Total Number of Channels and with the power levelt a.

Less than or equal to 15 MWe, restore the inoperable channel to OPERABLE status withir. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless reactor power level has been increased to >15 MWet otherwise be in at least HOT STANDBY within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with the reactor trip breakers open.

b.

Above 15 MWe, POWER OPERATION may continue.

YANKEE ROWE 3/4 3-5

E f

l TABLE 3.3-1 (Continued)

ACTION S11TEMENTS (CDntinutd)

ACTION 4 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with thes a.

Reactor not critical, restore the inoperable channel to OPERABLE status prior to increasing reactor reactivity, b.

Reactor critical, operation may continue.

ACTION 5 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1.2 or l

3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfied a.

The inoperable channel is placed in the tripped condition l

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Mi.. mum Channels OPERABLE requirement is mett however, one l

additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

ACTION 7 -

a.

With the number of OPERABLE channels in either System A or B one less than the Total Number of Channels, operation may continue provided all channels in the other system are OPERABLE.

b.

With the number of OPERABLE channels in both Systems A and B l

one less than the Total Number of Channels in each system, STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfied

1) The inoperable channels are placed in the tripped l

condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2) The Minimum Channels OPERABLE requirement for each System l

is mett however, one additional channel in either system may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing d

per Specification 4.3.1.1.

1 l'

YANKEE ROWE 3/4 3-6 i

TABLE 3.3-1 (ContinutsO e

ACTION STATE *4ENTS (Continued)

ACTION 8 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 9 - With the number of channels OPERABLE one less than required by the Minimum Channels Operable requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with reactor trip breakers open.

ACTION 24 - a.

With the number of channels OPERABLE one less than required by the Minimum Channels Operable requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with reactor trip breakers open.

b.

With the Minimum Channels OPERABLE requirement met, one cnaunel a; a time may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of FUNCTIONAL UNIT 15 or 16 per Specification 4.3.1.1.

In this application CHANNEL refers to a train of trip logic.

ACTION 25 - a.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the Minimum Channels OPERABLE requirement met, one channel at a time may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of FUNCTIONAL UNIT 15 or 16 per Specification 4.3.1.1.

In this application CHANNEL refers to a train of trip logic.

YANKEE-ROWE 3/4 3-7

TARTE 4.3 1 g

Etm-REACTOR PROTECTIVE STSTEM INSTRUMENTATION SURVEILIANCE REQUIREMENTS M

CHANNEL MODES IN ifEICH N

CHANNEL CHANNEL FUNCTIONAL SURVEILIANCE IVNCTIONAL UNIT f1tF1T CALIBRATION TTRT REOUYarn 1.

Manual Reactor Trip NA NA S/U(1)

NA 2.

Power Range, Neutron Flux and S

D(2), q(5)

M 1, 2, and

l_

Intermediate Power Range, Neutron Flux 3.

Intermediate Range, Neutron Flux, S

R(5)

M 1, 2, and

High Startup Rate w

4.

Source Range, Neutron Flux S

R(5) s/g(1) 2,3,4,5, and *

[

5.

Low Nin Coolant Flow (SGAP)

S R(0)

M(3) 1 6.

Low N in Coolant Flow, Systems A S

R M

1 and B (MC Pump Current) l l

7.

High N in Coolant System Pressure S

R(4)

M i and 2 l

8.

Low N in Coolant System Pressure S

R(4)

M 1 and 2 a

{

9.

Intentionally Blank s

E 10.

Iow Steam Generator Water Level S

R(4)

M 1

E.

i E

l O

w

_y.

.c j.

TARLE 4.3-1 (Cont 4miad) -

REACTOR PROTECTIVE SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g

-Q-CHANNEL MODES IN WRICE c's CHANNEL CHANNEL FUNCTIONAL SURVEILIANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUT m c

M 11.

Turbine Trip.

NA NA S/U(1) 1 12.

Generator Trip

. ITA '

NA S/U(1) 1 13.

Reactor Trip Breaker NA NA S/U(13-1, 2, and

14.

Automatic Trip Icgic NA NA S/U(1) 1, 2, and *

)

15. Main Steam Isolation Trip Logic NA NA Q(6) 1.and 2

16. Nuclear Instrumentation Trip Logic NA NA

'Q(6) 1,.2, and

1

}

M z~

4 w

1 E

E e

5

. ~... - -.

TABLE 4.3-1 (Continued) j i

NOTATION With the reactor trip system breakers closed and the control' rod drive i

system capable of rod withdrawal.

'If not performed in the previous 7 days.

(1) lleat balance only, above 15% of RATED THERMAL POWER, at least 3 times (2) per week with a maximum time interval of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

e When shutdown longer than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , if not performed in the previous (3) 31 days.

(4)

Known prescure applied to sensor.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

Contacts or contact combinations in the logic circuit may be simulated (6) to operate relays in the trip logic circuit.

i 7

i e

YANKEE-ROWE 3/4 3-10 Amendment No. #f, 67, 105

. -. - - -,.. - -. - - -.,. -. - -..., - -. ~. -

TABM 3.3-2 (Contin==d)

E ENGINEERING SAFEGUARDS SYSTEM INSTRUMENTATION N"

MINIMUM TOTAL NO.

CHAMELS CHAMELS E

OF CHANNELS AND SENSORS AND SENSORS APPLICABLE FUNCTIONAL UNIT AND SENSORS TO TRIP OPERABM PE) del _,_

ACTIWf 2.

CONTAINMENT ISOLATION (Continued) c.

Actuation Channel B 1

1 1

1,2,3,4 10 1)

High Containment 1

1 1

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

Safety Injection (All Safety Injection Initiating Functions and Requirements)

R 3.

MAIN STEAM ISOLATION

[

a.

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

b.

Automatic Trip Logic 2

1 2

1, 2, 3(2) 26 c.

Manual Initiation 2

1 2

1, 2 26 d.

High Containment Pressure 2

1 2

1, 2 26 E

Trip Containment Isolation U

4.

LOSS OF POWER E

480 VOLT EMERGENCY BUS y

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

E b.

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

E

.M

IABLEA3-2 (Continued)

TABLE NOTATI.QN

- The provisions of Specification 3.0.4 are not applicable.

(1) Trip function may be bypassed in this MODE with main coolant pressure

<300 psig.

(2) Trip function may be bypassed 'in this MODE with main coolant pressure

<1800 psig and main coolant temperature <470'F.

-(3) Automatic initiation of Actuation Channel #1 may be bypassed in this MODE during functional test of the Main Coolant System Loop 1 pressure channel.

Automatic initiation of Actuation Channel #2 may be bypassed in this MODE during functional test of the Main Coolant System Loop 2 pressure channel.

ACTION STATEMERIS ACTION 10 - With the number of OPERABLE channels or sensors one less than the total number of channels or sensors, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one safety injection channel high containment pressure sensor may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

i

' ACTION 6 - With the number of OPERABLE channels one less than the total I

number of channels, STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfied 1

1.

The inoperable channel is placed in the tripped condition l

within one hour.

2.

The minimum channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

l ACTION 22 - With the number of OPERABLE channels one less than the total number of channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

i YANKEE-ROWE 3/4 3-13 Amendment No. 82, 83, 85, 112

4 ACTION SIATEMENTS l'

(Continued) i' ACTION 23 - With the number of OPERABLE channels or sensors one less than the total 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 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 26 - a.

With the number of channels-OPERABLE less than required by the Minimum Channels OPERABLE requirement, be in at least il0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the Minimum Channela OPERABLE requirement met, one channel at a tine may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

In this application CRANNEL refers to a train of trip logic.

YANKEE ROWE 3/4 3-13A Amendment No. 107

[

^

__p:_ _ & ;M j. ~.

5

~

=

x

-TABLE 4.3-2 (Continued)

- ENGINEEREDJAFEGUARDS SYSTEM INSTRtMENTATIO.E ~

g

$~JRVEII1ANCE REOUIREMQ[IS.

g CHANNEL MODES IN WHICH E

CHANNEL CHANNELS' WNCTIONAL

' SURVEILLANCE N

~ FUNCTIONAL UNIT CHECK CALIBRATIONS' TEST REOUIRED-2.

CONTAINMENT:ISOLATICN 4

(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 (All Safety Injection Surveillance Requirements)

R 3.

MAIN STEAM ISOI ATION a.

Low Steam Line Pressure S

R(3)

M(3) 1, 2 b.

Automatic Trip. Logic NA NA Q(5) 1, 2 j'

c.

Manual' Initiation

.NA NA-R 1,'2 d.

High, Containment Pressure

'NA NA R

1, 2 4.

LOSS OF POWER y

480 VOLT EMERGENCY BUS 2

a.

Loss of Voltage (First Level)

NA.

R R

1,2,3 h

E" b.

Degraded Voltage (Second Level)

NA R

M 1,2,3 E.

p.

C zr-*r_~s'er m

-:-e ri?

.h.?

..Wh._Bl.es.

-:mkhm.:n-ih*m__'M h w+"

em ei.-A

--Amm_.a.-

-=

u-e*

- - + -.

(

b i

IABLE_4.3-2 (Continuedl TABLE NOTATION (1) When shut down with main coolant pressure <1000 psig, if not performed within the previous 31 days.

(2) When shut down longer than 24 houra, if not performed in the previous 31 days.

.(3) The test shall include exercising the sensor by applying either a vacuum or pressure to the appropriate side of the sensor.

(4) When in COLD SilUTDOWN with main coolant pressure <300 psig, if not performed within the previous 31 days.

P (5). Contacts or contact combinations in the logic circuit may be simulated to operate relays in the trip logic circuit.

Not required in this MODE with main coolant pressure <300 psig.

Not required in this MODE with main coolant pressure <1700 psig.

l YANKEE R0WE 3/4 3-16 Amendment No. #f, I

85, 89 l-i

IABLL323:6 y ;-

IIRE DETECTION INSTRUMENTS INSIRIR$ENIAIIDH_LOCAILOH tilHit$UM INSTRUt1ENILDEEBABLE 1.

Control Room Above Dropped ceiling 9-Control Boards Main Control Board 3

SI Panels 1/Panci NI Panel 1

.l General' Area 9

2. -.

Cable Spreading.

Cable Tray llouse 2

Manhole No. 3 1

Switch ear Room 20 3.

C Battery Room No. 1 1

Battery Room No. 2 1

4.

' Diesel Generators No. 1 1

No. 2 1

No. 3 1

5.

Safety.' Injection Pumps and No. 3 Battery 5

6.

Charging Pump Cubicles

-No'.

1 1

No. 2 1

No. 3 1

.7.

1 & 2 Charcoal Filters 1/ Filter

- l 8.

Turbine Building Transformer Oil Cooler Area 2

Turbine I.ube Oil Reservoir 2

9.

Vapor Container 1

l l

10.

PICS Building 1

j

11. Non-Return Valve (NRV) Enclosure 2

1 i

YANKEE ROWE 3/4 3-28 Amendment No. #6, 6#, 83

g N

[

3/4.7 PLANT SYSTEMS:

3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 -All main steam line code safety valves associated with each steam generator of an unisolated main coolant loop shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3..

+

ACTION:

a.

With 4 main coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable:-

1.

Operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either:

-a) JThe inoperable valve (s) is restored to OPERABLE status, or b).The three Power Range and the three Intermediate Power Range Neutron Flux channels are OPERABLE ** with:

1) The Power Range and Intermediate Power Range Neutron Flux

- liigh Setpoint trips-reduced per Tabic 3.7-1.

~

2) The Power Range and Intermediate Power Range Scram logic.

set for single channel operation.**.

2.

Otherwise, be in at least 110T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SilUTD0ial within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE, with lif t settings and orifice sizes as shown in Table 4.7-1, in accordance with Section XI of the ASME Boiler and Pressure Vessel' Code, 1974 Edition, and Addenda through Summer, 1975.

- One Power Range or Intermediate power Range Neutron Flux channel may be made inoperable and its associated (Power Range or Intermediate Power Range) scram logic reset for coincidence operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (per channel) for required surveillance per Specification 4.3.1.1.

YANKEE-ROWE 3/4 7-1 Amendment No. 58, 83 4

p

-e 9

l gIgCIAL TEST EXCEPT10HS PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY LIMITING CONDITION FOR OPERATION o

3.10.3 = The minimum temperature and pressure conditions for reactor criticality of Specification 3.4.8.1 may be suspended during low temperature PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed 2 percent of RATED THERMAL POWER, b.

The reactor high setpoint trips on the three OPERABLE Power Range Nuclear Channels and the reactor high setpoint trips on the three

.0PERABLE Intermediate Power Range Nuclear Channels are set at 125% of RATED THERMAL POWER, and i

c.

The Main Coolant System temperature and pressure are maintained 1250'F and 1300 psig, respectively.

APPLICABILITY: MODE 2.

ACTION:

a.

With the THERMAL POWER >2 percent of RATED THERMAL POWER, immediately open the reactor trip breakers.

b.

With the Main Coolant System temperature and pressure <250'F or i

<300-psig, immediately open the reactor trip breakers and restore the temperature-pressure to within its limit within 30 minutes; perform the analysis required by Specification 3.4.8.1 prior to the next reactor _ criticality.

SURVEII.1ANCE REOUIREMENTS 4.10.3.1 The Main Coolant System temperature and pressure shall be verified to be 1250'F and 1300 psig at least once per hour.

4.10.3.2 The THERMAL POWER shall be determined to be 12% of RATED THERMAL POWER at least once per hour.

4 4.10 3.3 Each Power Range and Intermediate Power Range Nuclear Channel shall-j be subjected te a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating low temperature PHYSICS TESTS.

YANKEE-ROWE 3/4 10-3 Amendment No. #7, #f, 50

y-SPECIAL TEST EXCEPTIONS l.:

PHYSICS TESTS LIMI' TING CONDITION FOR OPERATION i

3.10.4 Th6 limitations of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.4, and L

3.1.3.5, may be suspended during the performance of PHYSICS TESTS provided l'

a.

The THERMAL POWER does not exceed 2% of RATED THERMAL POWER, and b.

The reactor high setpoint trips on the three OPERABLE Power Range Nuclear Channels and_the reactor high setpoint trips on the three OPERABLE Intermediate Power Range Nuclear Channels are set at 125% of RATED THERMAL POWER.

APPLICABILITY: MODE 2.

ACTION:

y With the THERMAL POWER >2% of RATED THERMAL POWER, inmediately open the reactor trip breakers.

SURVEILLANCE REOUIREMENTS 4.10.4.1-The THERMAL POWER shall be determined to be 12% of rated THERMAL POWER at least once per. hour during PHYSICS TESTS.

4.10.4.2 Each Power Range and Intermediate Power Range Nuclear Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating l

PHYSICS TESTS.-

l L

YANKEE-ROWE 3/4 10-4 Amendment No. #7

-

ML20005F143

Text

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