Text

Amend 130 to License DPR-3,allowing Utilization of New Neutron Flux Instrumentation Sys,Including Ability for Enhanced Testing at Power & Mods to Clarify Specs
	ML20033E979
Person / Time
Site:	Yankee Rowe
Issue date:	03/06/1990
From:	Wessman R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20033E976	List: ML20033E975; ML20033E979; ML20033E981;
References
	NUDOCS 9003150203
	Download: ML20033E979 (21)
	v • d • e

@y 4, _

s,+. y

. pR ht Cp

'o

UNITED STATES l

z.

lY c f 'k #Nj/[,i NUCLE AR REGULATORY COMMISSION 4

rp 1i

/.I WASHINGTON, D. C. 205b5 KE 'f V

4......

i YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO.50-029 p

YANKEF NUCLEAR: POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 130-License No. DPR-3 1.

The Nuclear Pegulatory Comission (the Comission or the n,',C) has found that:

A.

~ The application for amendment filed by Yankee Atomic Electric 1

Company (the licensee) dated January 5,1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as j

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; C.

.There is reasonable assurance: (1)'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 Comission'.s regulations set forth in 10 CFR -

Chapter I; 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.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions 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:

(?) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.130, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical. Specifications.

?$$

ffK05000029 3 900306 !

P PNug

'El. a y:

+

1 ;

,p,a j :, ' ',,.

3.

This license amendment is effective as of August 1, 1990.

FOR THE NUCLEAR REGULATORY COMMISSION

-(O 4

'S7 ct&m/i h va

/<b' Richard H. Wessman, Director i

{'.

Proiect. Directorate 1-3

-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

i Changes to the Technical Specifications Date of Issuance: MAR 0 6 1918 i

I

'l o

i 1

i i

7

< 'e

..,m

'i ATTACHPEt:T TO LICENSE AMENDMEllT 110. 130 FACILITY OPERATING LICEtiSE NO. DPR-3 s

DOCKET NO.50-029 i-L Replace the following pages of the Appendix'A Technical Specifications with

-the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/43-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3 4 3/4 3-4 1

3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 1

'3/4 3-8 3/4 3-8 l

3/4,3-9 3/4 3-9 3/4 3-10 3/4 3 10 3/4 3-12A 3/4 3-12A

'3/4 3 3/4 3-13 l

3/4 3-13A 3/4 3-13A 3/4 3-15A 3/4 3-15A 3/4 3-16 3/4 3-16 l

3/4 3-28 3/4 3-28 3/4 7-1 3/4 7-1 3/4 10-3 3/4 10-3 l

3/4 10-4 3/4 10-4 l

ll

/r

s 4

TABLE 3.3-1 REACTOR PROTECTIVE SYSTEM INSTRUMENTATION M'

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE N FUNCTIONAL UNIT OF CHANNELS TO~ TRIP OPERABLE' MODES

6CJJDf!

1.

Manual Reactor Trip 3

1

.3 1, 2, and

1 2.

Power Range, Neutron Flux and 6

2-4 1(1), 2, and *

'2**

-l 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#E 2

NA 2

2I and *(5)

.a to 4

b. Shutdown.

2 NA

'1 3

., and 5(5) 5 5.

Low Main Coolant Flow (SGAP) 4 2

3 1(3) 6**

6.

Low Main Coolant Flow (MC Pump Current)

a. System A 4

2 3

1(3) 7a*-

{

b. System B 4

2 3

1(3) 733 a

7.

High Main Coolant System Pressure 3

2 3

1 and 2(4) 6**

f 8.

Low Main Coolant System Pressure 3

2 3

1 and 2(4) 6**

y 9.

Intentionally Blank

[

10.

Lew Steam Generator Water Level 4

2 3

1(3) 64*

.c 7_.

- ;.c_

-t N

9-TABLE 3.3-1 (Continued)

-REACTOR PROTECTIVE SYSTEM INSTRUMENTATION

.. m MINIMUM TOTAL NO.-

CHANNELS' CHANNELS APPLICABLE 5

FUNCTIONAL UNIT

-OF CHANNELS-

' TO TRIP OfERABLE MODE 5_-

' ACIl0N.

11.

Turbine Trip 1

'l 1'

1(3)(6).

3

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 Logic 2

1 2

1 and 2(4)

-25 O

16.

Nuclear' Instrumentation Trip Logic 2

1 2

1(1)(2), 2, and

24 Y

t.e3 8

a,,

M L

t"~

,:_:_.-___.______.__._-__-.1a_.-_

x c a

u

.e-

.m.u a

t I6BLE 3.3-1 (Continuedl TABLE NOTATION With the reactor trip' system breakers in-the closed. position and the control rod drive system capable of rod withdrawal.

The previsions of Specification 3.0.4 are not applicable.

High voltage to detector is automatically energized prior to the Intermediate Rar.ge.' 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 115 MWe.

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

(2) Intermediate Range Neutron Flux High Startup Rate Trip is automatically bypassed 215 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 movement, 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 within 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.

YANKEE R0WE 3/4 3-4 Amendment No. 23,130

.l

s. ~,

i I6BLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 2 -

"a.

With two Power Range and/or Intermediate Power Range channels inoperable and with the THERMAL POWER 12% of: RATED THERMAL POWER, set the power' range high neutron level scram logic for single' channel operation for both the Power Range and r

Intermediate Power Range instrumentation.

b.

With one Power Range ~or one Intermediate' Power Range channel inoperable and with the THERMAL POWER level >2% of RATED 1

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 channel operation for the RPS instrumentation group containing the inoperable channel.

l c.

With two Power Range channels, or two Intermediate Power Range channels, or one Power Range and one Intermediate Power Range L

channels inoperable and with the THERMAL POWER level >2% of 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 channel operation for both the Power Range and Intermediate Power 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

1 Specification 4.3.1.1.

b ACTION.3 - With the number of OPERABLE channels one less than the Total Number of Channels and with the power level:

a.

Less-than or equal to 15 MWe, restore the inoperable channel to OPERABLE status within 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 MWe; otherwise-be in at least HOT p,

STANDBY within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with the.'eactor trip y

breakers open.

l-l b.

Above 15 MWe, POWER OPERATION may continue.

L L

l l

YANKEE ROWE 3/4 3-5 Amendment No. 130

' ~ -

.w.

e.:

1_

k

.IABLE 3.3-1 (Continued)

ACII01LSIATEMENTS (coneinued)

ACTION 4 - With the number of channels OPERABLE one less than required'by the Minimum Channels OPERABLE requirement and with the:

)

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 i hour and at least once per i

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 , t

l.

b.

The Minimum Channels OPERABLE requirement is met; 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 I'

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 one less than the Total Number of Channels in each system.

SIARTUF 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-hour.

2) The Minimum Channels OPERABLE requirement for each System l

18 met; 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 per Specification 4.3.1.1.

YANKEE R0WE 3/4 3-6 Amendment No. 130

,f-o b

TABLE 3.3-1 (Centinued)

ACTION STATLMENTS (Centincjil ACTION S - 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 M1nimum 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 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 CRANNEL ref ers 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 FUNCTIOFAL 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 Amendment No.130 I

s 5-TABLE 4.3-1 M

REACTOR PROTECTIVE SYSTEM INSTRUMENTATION SURVEIll.AECE_REqqlERLENTS m

"o

t CHANNEL MODES IN k*iiIC3 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

[

ERiCIlONAL UNIT

_ CHECK _

CALIZEAIION E

REQUJRED 1.

Manual Reactor Trip NA NA S/U(I)

NA 2.

Power Range, Neutron Flux and S

D(2), g(5)

M 1, 2, and

l Intermediate Power Range, Neutron Flux 3.

Intermediater Range, Neutron Flux, S

R(5)

M 1, 2, an I

High Startup Rate.

g Source Range, Neutron Flux S

R(5)

S/UCI) 2,3,4,5,

~

4.

s an6

5.

Low Main Coolant Flow (SGSP)

S R(4)

M(3) 1 6.

Low Main Coolant Flow, Systems A S

R_

M 1

and B (MC Pump Current) f 7.

High Main Coolant Syster Pressure S

R(4)

M 1 and 2 8.

Low Main Coolant System Pressure S

R(')

M 1 and 2

(

9.

Intentionally Blank 8

" A 10.

Low Steam Generator Water Level S

R(0)

M 1

2

?

'.O.

.. ~.

.--~.w

IABLE 4.3-1 (Centinued)

REACTOR PROTECTIVE SYSTEM INSTRUMENTATION SUEVEILTWICE REOUIREMEES g.g.

N CHANNEL MODES 174 v~Iiitti CHANNEL CHANNEL FUNCTIONAL SURVEILIE;CZ FUNCTIONAL UNIT CHECTm CitLIBRATION

_. TEST.. _

RERRIEED -

N 11.

Turbine Trip NA NA S/U(I) 1 12.

Generator Trip NA NA O/U(l) 1 13.

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

14.

Automatic Trip Logic 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

R.

B N

?.

~

l?"

t-C.Q.

?.

f TABLE 4.3-1 (continued)

.p.

e y

NOTATION-With the reactor trip system breakers closed and the control rod drive o

system capable of rod withdrawal.

(1)

If not performed in the previous 7 days.

F' (2)

Heat balance only. 'above 15% of RATED THERMAL POWER, at least 3 times l :,

per week with a maximum time interval of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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 -

i

. (3) l-31 days.

Known pressure applied to sensor.

I (4) h 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.

1 t

t l

4 YANKEE-ROWE 3/4 3-10 Amendment No. #f, (p, idi,130

.1 IABLE __3.3-2 (Continug.d.)

EN.G._INEERING SAFEGUARDS sisleri INSTRUMENTATION

.m MINIMUM E

TOTAL NO.

CHANNELS CHANNELS M

OF CHANNELS AND SENSORS AND SENSORS APPLICABLE BINCTIONAL UNII AND SENS0ES TO TRIP OPER&B_LFm

_. PODES_

4CIJF 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)

M 3.

MAIN STEAM ISOLATION

~ 3/ Steam Line 1,

?., 3(2) 6**

1 a.

Low Steam Line Pressure 3/ Steam Line 2/ Steam Line b.

Automatic Trip Logic 2

1 2

1, 2, 3(2) 26 l

c.

Manual Initiation 2

1 2

1, 2 25 d.

High Containment Pressure 2

1 2

1, 2 26

- wE Trip Containment Isolation

! E 's 4.

LOSS OF POWER

~*

$ 'd 480 VOLT EMERGENCY BUS 4

E a.

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

b.

Degraded Voltage (Second Level) 2/ Bus 2/ Bus 2/ Bus 1, 2, 3 2 2 ' --

.E

.M y

- - -,~,

..w

)

C.

l IAL1,E 3.3-2 (Centinntdj 3

IALLE NOTATIQH

- The provisions of Specification 3.0.4 are not applicable.

j (1) Trip function may be bypassed in this MODE vith main coolant pressure l

<300 psig.

(2) Trip function may be bypassed 'in this MODE with main coolant pressure (1800 psig and main coolant temperature (470'F.

I (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 Che 1 #2 may be bypassed in this MODE during functional test of the Main C#c. ant System Loop 2 pressure channel.

i ACTION STATEMEl{IS 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.

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 1.

The inoperable channel is placed in the tripped condition 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 perfonnance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

7 YANKEE-ROWE 3/4 3-13 Amendment No. 81, 83, 85,JJA, 130

y ACTION STATEMENTS I

(Continued)

ACTION 23 - With the number of OPERABLE channels or sensors one less than the I

total number of channels or sensues, 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 vithin 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 HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i b.

With the Minimum Channels OPERABLE requirement net, 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 per Specification 4.3.1.1.

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

i

-YANKEE ROWE 3/4 3-13A Amendment No. 101, 130

y TABLE 4.3-2 (Continued)

ENGINEERED SAFEGUARDS SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMDITS E-A CHANNEL MODES IN WHICI!

E CHANNEL CHANNELS FUNCTIONAL SURVEILI/JJCE N

BTNCTIONAL UNIT JUECK.

CALIIEATIONS TEST.

REQUlRED 2.

CONTAINMDiT 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 (All Safety Injection Surveillance Requirements)

R o

3.

MAIN STEAM ISOLATION a.

Low Steam Line Pressure S

R(3)

M(3) 1, 2 b.

Automatic Trip Logic NA NA Q(5) 1, 2

)

c.

Manual Initiation NA NA R

1, 2 d.

High, Containment Pressure NA NA R

1, 2 4

LOSS OF POWER 480 VOLT EMERGENCY BUS 9

Loss of Voltage (First Level)

NA R

R 1, 2, 3 g

a.

b.

Degraded Voltage (Second Level)

NA R

M 1, 2, 3 5

y.

%WW W

=

i IAt1E 4.3-2 (certinued)

TAtl.E 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 SliUTDOWN with main coolant pressure <300 psig, if not j

performed within the previous 31 days.

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

l

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

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

1

)

l 1

l YANKEE ROWE 3/4 3-16 Amendment No. if, gi, 59, 130

a C '

l.

IABLE 3.3-6 FIRE DETECTION INSTRtNENTS I

i JIiSTRLMDfTAllflLLQ.QAI103 MINIMLN INSTRtNENTS OPEPA!}1E 1.

Control Room i

Above Dropped Ceiling 9

Control Boards Main Control Board 3

SI Panels 1/ Panel NI Panel 1

l General Area 9

t i

2.

Cable Spreading Cable Tray llouse 2

Manhole No. 3 1

3.

Switchgear Room 20 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.

CharginC Pump Cubicles No. 1 1

No. 2 1

No. 3 1

7.

1 & 2 Charcoal Filters 1/ Filter 8.

Turbine Building Transformer Oil Cooler Area 2

Turbine Lube Oil Reservoir 2

9.

Vapor Container 1

10.

PICS Building 1

11. Non-Return Valve (NRV) Enclosure 2

YANKEE R0WE 3/4 3-28 Amendment No. 46, 6e. if,130

PE l

i 3/4.7 PIN?T SYSTEMS 3/4.7.1 TUREINE CYCLE SAFETY t.'ALVIS LIMITING CONDITION FOR OPER'. TION 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.

APPLICAh1LITY: MODES 1, 2, and 3.

j l

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, an'd 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either:

a) The 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

- High Setpoint trips reduced per Table 3.7-1.

2) The Power Range and Intermediate Power Range Scram logic set for single channel operation.**

l 2.

Otherwise, be in at least HOT STANDBY within the next 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 .

]

b.

The provisions of Specification _3.0.4 are not applicable.

SURVEILLANCE RFOUIREMENTS I

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, J

1974 Edition, and Addenda through Summer, 1975.

l 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.

l YANKEE-ROWE 3/4 7-1 Amendment No. 58, #1, 130

SPECIAL EST EXCEPTIOES PRESSURE /TEMPEEATURE LIMITATION - REACTOR CRITICALITY LIMITING CONDITION FOR OPERATION I

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 OPERABLE Intermediate Power Range Nuclear Channels are set at 125% of RATED THERMAL POWER, and c.

The Main Coolant System temperature and pressure are maintained 2250'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

<300 psig, immediately open the reactor trip breakers and restore the temperature-pressure to within its limit within 30 minutes; perform l

the analysis required by Specification 3.4.8.1 prior to the next reactor criticclity.

SURVEILLANCE REOUIREMENTS 4.10.3.1 The Main Coolant System temperature and pressure shall be verified to be 2250'F and 2300 psig at least once per hour.

4.10.3.2 The THERMAL POWER shall be determined to be 42% of RATED THERMAL POWER at least once per hour.

4.10.3.3 Each Power Range and Intermediate Power Range Nuclear Channel shall l

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 low temperature PHYSICS TESTS.

l-l t

l YANKEE-ROWE 3/4 10-3 Amendment No. 47, #f, 66,130 l

l

SIECIll TEST EXCEPTIONS EllISICS TESTS 1IMITING CONDITION FOR OPFRATION 3.10.4 The limitations of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.4, and 3.1.3.5, may be suspended during the performance of PHYSICS TESTS provided:

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 P0'4ER.

APPLICABILITY: MODE 2.

ACTION:

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

SURVEII,IANCE 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.

1 4.10.4.2 Each Power Range and Intermediate Power Range Nuclear Channel shall be subjected to a CIIANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating PilYSICS TESTS.

YANKEE-ROWE 3/4 10-4 Amendment No. 47.130

ML20033E979

Text

Attachment:

Navigation menu

Search