Text

Proposed Tech Specs,Relocating TS Requirements for Containment Purge Exhaust & Supply Valves from Radiation Monitoring Instrumentation TS Table to ESF Actuation Sys TS Table
	ML20086A344
Person / Time
Site:	Millstone
Issue date:	06/27/1995
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20086A337	List: B15236, Application for Amend to License NPF-49,relocating TS Requirements for Containment Purge Exhaust & Supply Valves from Radiation Monitoring Instrumentation TS Table to ESF Actuation Sys TS Table; ML20086A344;
References
	NUDOCS 9507030175
	Download: ML20086A344 (27)
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Docket No. 50-423 B15236 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Engineered Safety Features Actuation System Instrumentation Marked-Up Pages i

i June 1995 9507030175 950627 PDR ADOCK 05000423 P

PDR

~

TABLE 3 3'kContinued) 12/22/92

ylg, j

..n i

de REACTOR TRIP SYSTEN INSTRUNENTATION kg;

. p;;

MINIMUM g

TOTAL NO.

CHANNELS CHANNELS APPLICABLE r '"

i if, FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES

~

ACT10ll

12. Reactor Coolant Flow--Low a.

Single Loop (Above P-8) 3/ loop in 2/ loop in 2/ loop in 1

6 each oper-any oper-each oper-ating loop ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop in 2/ loop in 2/ loop 1

6 below P-8) each oper-two oper-each oper-t ating loop ating loops ating loop

13. Steam Generator Water 4/sta. gen.

2/sta. gen.

3/sta. gen.

1, 2 6(1)

Level--Low-Low in each oper-in any oper-each oper-ating sta.

ating sta.

ating sim.

w gen.

gen.

C

14. Low Shaft Speed--Reactor 4,

Coolant Pumps a.

Four loop operation 4-1/ pump 2

3 1**

6 b.

Three loop operation 3-1/ pump 2

2 1**

6

15. Turbine Trip a.

Low Fluid Oil Pressure 3

2 2

1***

12 b.

Turbine Stop Valve Closure 4

4 4

1***

6 D

~~3arety Injection Input

~~

~ '

from ESF 2

1 2

1, 2 134 5

~~~ -

E

17. Reactor Trip System interlocks-

_ _..___ _ _ _., _ _ _ - - ~ _

5 a.

Intemediate Range Neutron Flux, P-6 2

1 2

2ff 4

i M

b.

Low Power Reactor

-y Trips Block, P-7 o

s P-10 Input 4

2 3

1 8

i or j

P-13 Input 2

1 2

1 8

i 1

a

=

M v

s-M-+-----w-T 2-te

+ w---i+4me w

-4 m - -

M*d--

m-e

-- a

- g..

Id,

t, TABLE 4.3-1 (Continuedl i

4 REACTOR TRIP SYSTEN IE_TATION SERVEILLME RF8HlangfT3 NJ TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WICH CHAMEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATI0ff TEST TEST LOGIC TEST IS REOUUEIL 4

13. Steam Generator Water Level-- S R

Q(18)

N.A.

M.A.

1, 2 l

Low-Low

14. Low Shaft Speed - Reactor N.A.

R(13)

Q N.A.

N.A.

I Coolant Pumps

15. Turbine Trip a.

Low Fluid 011 Pressure N.A.

R.

N.A.

S/U(1,10)****N.A.

I Gk@ b.

Turbine Stop Valve N.A.

R N.A.

S/U(1,10)****N.A.

1 Closure

16. SafetyInjection]Inputfrom N-A.

N.A.

n.A.

R N.A.

y E

O 17.

Reactor Trip System Interlocks a.

Intermediate Range Neutron Flux, tor P-6 N.A.

R(4)

R N.A.

N.A.

2**

l b.

Low Power Reac Trips Block, Neutron P-7 N.A.

R(4)

R N.A.

N.A.

I Power Range c.

Flux P-8 N.A.

R(4)

R N.A.

N.A.

I d.

Power, Range Neutron Flux P-9 N.A.

R(4)

R N.A.

N.A.

1 e.

Power, Rance Neutron Flux P-10 N.A.

R(4)

R N.A.

N.A.

1, 2 C

l f.

TurbineImpulseChamber j

Pressure, P-13 N.A.

R R

N.A.

I l

-g

.I G8 l

=

8

12/22/92 78 1

TABLE 3.3-3 fContinued) 4-M25

)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

"\\s MININUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF. CHANNELS TO TRIP _

OPERABLE MODES _

ACTION 5

w 3.

Containment Isolation (Continued) 3)

Containment 4

2 3

1, 2, 3, 4 17 Pressure--High-3 Steam Line Isolation a.

Manual Initiation

1) Individual 1/ steam line 1/ steam line 1/ operating 1,2,3,4 24 R{

steam line whI

2) System 2

1 2

1,2,3,4 23 b.

Automatic Actuation 2

1 2

1, 2, 3, 4 22 Logic and Actuation Relays I

c.

Contairrent Pressure--

3 2

2 1, 2, 3, 4 20 g

High-2 3

g.

d.

Steam Line Pressure--

3/ steam line 2/steamline 2/ steam line 1, 2, 38 20 g

Low in each in any in each operating operating operating g

loop loop loop g

e.

Steam Line Pressure -

3/ steam line 2/steamline 2/steamline 3****

h6 Negative Rate--High in each in any in each t

operating operating operating loop loop loop y

}J s

, t.

.' I 03/24/94 TABLE 3.3-3 (Continued) 1 TABLE NOTATIONS l

Mhe Steam 11ne Isolation Logic and Safety Injection Logic for this trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

I

- - - Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

ACTION STATEMENTS ACTION 14 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to l

OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 - (not used).

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CNANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

ACTION 18 - With less than the Minimum Channels OPERABLE recuirement, within I hour initiate and maintain operation of tie Control Room Emergency Ventilation System in the recirculation mode of operation.

l Eriva cces h=os c,r-nome,hc krudad3 GL wiu i

& coa %>weok.

rue woaws ce swe mee,& 2.cs.2 a.re,x+

JJJJ W e

M.ILLSTONE - UNIT 3 3/43-24 Amendment No. J/, 7A 89, n

[6 9 l

(;. '

',Yb 12/22/92 TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 19 - With the number of OPERABLE channels one less than !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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 20 - With the number of OPERABLE channels one less than the Total-Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

b. the Minimum Channels OPERABLE' requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 21 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 22 - With the number of OPERABLE channels one less than the Minimum -

Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 -hours for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 23 - With the number of OPERABLE channels one less than the - Total Number of Channels, 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, 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 declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

'OM Ac% %-

Scz Arr""G*

W MILLSTONE - UNIT 3 3/43-25 Amendment No. 70 N!!3 87

s

\\

gsseer ",3-2.s

.p Y 37

. wy >Q,

' AC.n g n -

H.%

len L 1ke in n.,,.sm - Ckuoveh ofEMBLE rey ;nmen+,

o o

+4e. con % in eJ rna,a 1a + eJ e to,acf A m.; w~k.<a; Fa' ~ ~.

unu ans eduvs+

+1ve.s

,t purge CoAa'.omenf

<sd.uf,on eso.,.4ar,njciocca gya. red for pa p and eik.w {

, sciqW c ce. ec+

Cunhu'. w.e.d area r

r cPa u sts dn9 & ' pu hre.8nce. of reys. red h. k Tye W unin..,me.d Ieu k8ye.

ra h k h.

)

e i

i i

4 4

I I

i

'l l

.~. -

TABLE 3.3-4 (Continued)

2. I' 3

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS p)..,_i '.0 SENSOR R

TOTAL ERROR rtniCTIONAL UNIT ALLOWANCE (TA) 1 (S)

TRIP SETPOINT Att0WABLE~VALUE 3.

Containment Isolatinn (Continued)

C

2) Automatic Actuation logic N.A.

N.A.

and Actuation Relays

3) Safety injection See item 1. above for all Safety Injection Trip Setpoints anA Allowable Values.

b.

Phase "B" Isolation

1) Manual Initiation N.A.

N.A.

2) Automatic Actuation N.A.

N.A.

y logic and Actuation g

Relays

__8 0_ps_tg

< 8.8 psig i

3) Containmed c

L 01].75 j

4

& liigh-3 g,4 gg

,3.A g t glh

3. g g/g

( U team line Isolatto w

% m n k %,

dp c.

4 syggs sssw s a.

Manual Initiation N.A.

N.A.

{

b.

Automatic Actuation logic N.A.

N.A.

g and Actuation Relays 3g c.

Containment Pressure--liigh-2 3.3 1.01 1.75 s 3.0 psig i r 3.8 psig y

d.

Steam line Pressure--low 17.7 15.6 2.2 2 658.6 psig*

2 648.3 psig*

O Steam line Pressure -

5.0 0.5 0

s 100 psi /s**

s 122.7 pst/s**

c.

Negative Rate--liigh u

m

w-2

. m

\\s-TABLE 4.3-2 (Continued)

'i 5)[5 ENGINEERED SAFETY _ FEATURES ACTURTION SYSTEN INSTNUMENTATIM 4

$URVEILLANCE REQUIREMENT 5 l

TRIP ANALOG ACTUATING MODES CHANNEL DEVICE NRSTER SLAVE FOR WHICH E

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE' 4

FUNCTIONAL UNIT CHECK-CAllBRATION TEST TEST LOGIC TEST JISI IESL IS REQUIREQ w

3. Containment Isolation

a. Phase "A" Isolation

1) Hanual Initiation M.A.

N.A.

iJ. A.

R N.A.

N.A.

N.A 1, 2, 3, 4 l

2) Automatic Actuation M.A.

N.A.

N(1)

N(I)

Q 1, 2, 3, 4 Logic and Actuation Relays 5

3) Safety Injection See Item 1. above for all Safety injection Surveillance Requirements.

l

b. Phase '8" Isolation

1) Manual Initiation N.A.

N.A.

R N.A.

M.A.

N.A 1, 2, 3, 4 l

2) Automatic Actuation M.A.

N.A.

N(1)

Q 1, 2, 3, 4 -

Logic Actuation Relays

3) Containment S

R Q

N.A.

1, 2, 3, 4, Pressure-High-3 C.

Puwr rs s

g m

N4-y

4. Steam Line Isola % % %

N.o,

ni. A m. r1 Fc3 tion y

a. Manual Initiation

1) Individual N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

2) System N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 l '

1 M

~

8 j

~

. ?,

anuay 3,1995 TABLE 4.3-2 (Continued)

IABLE_M0TATIDH (1)

Each train shall be tasted at least every 62 days on a STAGGERED TEST BASIS.

(2)

This surveillance may be performed continuously by the emergency generator load sequencer auto test system as long as the EGLS auto test system is demonstrated operable by the performance of an ACTUATION LOGIC TEST at least once per 92 days.

(3)

On a monthly basis, a loss of voltage condition will be initiated at each undervoltage monitoring relay to verify individual relay operation.

Setpoint verification and actuation of the associated logic and alarm relays will be performed as part of the 'hannel calibration required once per 18 months.

C"'

'd**""3

""'#*~*"'

'k " ~"#" d"~d p

D oi"5

@ d u.> M w

-ha._ LMww%b. h p.s e m 5, d~

gne c.p., h m 3 o-3 a x n e rg b c..M +-

N LLSTONE - UNIT 3 3/43-41 Amendment No. (J. 7J. 77,100 ce,a

C TA!LLL 3.3-6 A

gg3 RADif M P' ADNITORING INSTRUNENTATION FOR PLANT OPERATIONS y ::p c

ge MINIMUM A

CHANNELS CHANNELS APPLICABLE ALARM / TRIP FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE N00ES SETPOINT ACTION e5 1.

Containme G-ciele &nt w

E. Certet;-..t Ares Nige 1

2 5, 5 1 1 "/h 25 er.d Exteust-Iselitiew-p)r'RCSLeakageDetection

1) Particulate Radioactivity N.A.

I 1, 2, 3, 4 M.A.

29

2) Gaseous *Radfoactivity N.A.

I 1, 2, 3, 4 M.A.

29-2.

Fuel Storage Pool Area Monitors f.

h N

}

a. Radiation level 1

2 1 15 mR/h 28

)

L in s'

n

=

b 0.

H b

~

w M

.e...

. <r

,~w m

m

.m

_ -,. _ _. _ _. _ _.-__.m_

E-February 21, 1990 TABLE 3.3-6 (Continued)

TABLE NOTATIONS

'o With fuel in the fuel storage pool areas.

ACTION STATEMENTS f - g ": 4 p elste-ACTION 26 -

With less than the Minimus Channels OPERABLE requirement, t

fuel movement may continue provided the containment purge and I

exhaust valves are maintained closed.

The containment radia-tion monitoring channels required for containment area purge and exhaust isolation are not required to be OPERABLE during the performance of Type A containment leakage rate tests.

ACTION 27 -

Not used.

ACTION 28 -

With less than the Minimum Channels OPERABLE requirement, fuel movement 'may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel storage pool area.

Restore the inoperable monitnrs to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel storage pool areas.

ACTION 29 -

With the number of OPERABLE Channels less than the Minimum i

Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

1 f

MILLSTONE - UNIT 3 3/4 3 44 Amendment No.46

, n, :;

i

e TABLE.4.3-3 s

a

$E RADIATION NOMIV0 RIM INSTRUNENTATION FOR PUF

'g OPERATIONS SURVEILLANCE REQUIREMENTS M

k ANALOG 4

CHANNEL MODES FOR WHICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE g

FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REOUIRED

-4 1.

Containment ggf a.

tainment Area Purge and Exhaust Isolation S

R Q

5, i

g b.

RCS Leakage Detection

1) Particulate Radio-S R

Q 1, 2, 3, 4 g

activity

,)

2) Gaseous Radioactivity 5

R Q

1, 2, 3, 4 l

2.

Fuel Storage Pool Area Nonitors a.

Radiation level S

R Q

I TABLE NOTATIONS E

With fuel-in the fal storage pool area.

g I

fo

~

3 8

=

g O

r j INSTRdMENTATION JAN 31 1986 BASES REACTOR TRIP SYSTEM INSTRUMENTATION and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T,yg below Setpoint, prevents the opening of the main feedwater valves which were closed by a Safety Injection or High Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.

Reactor not tripped prevents manual block of Safety Injection.

P-11 On increasing pressurizer pressure, P-11 automatically reinstates Safety Injection actuation on low pressurizer pressure and low steam line pressure.

On decreasing pressure, P-11 allows the manual block of Safety Injection actuation on low pressurizer pressure and low steam line pressure.

P-12 On increasing reactor coolant loop temperature, P-12 automatically provides an arming signal to the Steam Dump System.

On decreasing reactor coolant loop tempe:ature, P-12 automatically removes the arming signal from the Steam Dump System.

P-14 On increasing steam generator' water level, P-14 automatically trips all feedwater isolation valves, main feed pumps and main turbine, and inhibits feedwater control valve modulation.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:

(1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance.

The radiation monitors for plant operations senses radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions.

Once the required logic combination is j

completed, the system sends actuation signals to initiate alarms.cr : & --tic

-4;;1stion :: tion and ;;tuatica of Erergency Ed.;ust er "antiletien Systeas.

I

\\

MILLSTONE - UNIT 3 8 3/4 3-3 dl

p-.

~j y '

,e Docket No. 50-423 B15236 l

I f

i l

l Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Engineered Safety Features Actuation System Instrumentation Retyped Pages i

i i

P I

I June 1995 i

y Millstone Nuclear Power Station, Unit No. 3 Prop 00ed Revision to Technical Specifications ESFAS Instrumentation Page and Section Title Amendment No.

Table 3.3-1 RTS Instrumentation 3/4 3-3, Amendment 70 Table 4.3-1 RTS Instrumentation 3/4 3-11, Amendment 100 Surveillance Requirements Table 3.3-3 ESFAS Instrumentation 3/4 3-19, 3-25, Amendment 70 3/4 3-24, Amendment 89 Table 3.3-4 ESFAS Instrumentation 3/4 3-27, Amendment 67 Trip Setpoints Table 4.3-2 ESFAS Instrumentation 3/4 3-37, 3-41, Surveillance Requirements Amendment 1C0 Table 3.3-6 Radiation Monitoring 3/4 3-43, Amendment 65 Instrumentation for Plant 3/4 3-44, Amendment 46 Operations Table 4.3-3 Radiation Monitoring 3/4 3-45, Amendment 100 Instrumentation for Plant Operations Surveillance Requirements Bases Radiation Monitoring for B3/4 3-3, Jan. 1986 3/4.3.3.1 Plant Operations i

4

.._y.

TABLE 3.3-1 (Continuedl REACTOR TRIP SYSTEM INSTRUMENTATION u3 MINIMUM m

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

%q

12. Reactor Coolant Flow--Low a.

Single Loop (Above P-8) 3/ loop in 2/ loop in 2/ loop in 1

6 w

each oper-any oper-each oper-ating loop ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop in 2/ loop in 2/ loop 1

6 below P-8) each oper-two oper-each oper-ating loop ating loops ating loop

13. Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1,.:

6 (1)

Level--Low-Low in each oper-in any oper-each oper-ating stm.

ating stm.

w1 gen.

gen.

w 14.

Low Shaft Speed--Reactor Coolant Pumps a.

Four loop operation 4-1/ pump 2

3 1**

6 b.

Three loop operation 3-1/ pump 2

2 1**

6

15. Turbine Trip a.

Low Fluid Oil Pressure 3

2 2

1***

12 b.

Turbine Stop Valve Closure 4

4 4

1***

6 Deleted g

16.

$. 17. Reactor Trip System Interlocks 5

a.

Intermediate Range E

Neutron Flux, P-6 2

1 2

2ff 8

x

?

b.

Low Power Reactor Trips Block, P-7 w5 P-10 Input 4

2 3

1 8

N or P-13 Input

.2 1

2 1

8

Ff L

TABLE 4.3-1 (Continued 1

~

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREIENTS

'g TRIP ANALOG ACTUATING CHANNEL DEVICE

' MODES FOR.:

WHICH w

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED

13. Steam Generator Water Level--

S R

- Q(18)

N.A.

N.A.-

1,-2 Low-Low

14. Low Shaft Speed - Reactor N.A.

R(13)

Q N.A.

N.A.

. 1 Coolant Pumps

15. Turbine Trip a.

Low Fluid 011 Pressure N.A.

R N.A.

S/U(1,-10)****N.A.

- 1

- b.

Turbine Stop Valve N.A.

R N.A.

S/U(1,10)****N.A.

- 1 g

Closure

16. Deleted w.

O

17. Reactor Trip System Interlocks a.

Intermediate Range Neutron Flux, P-6 N.A.

-R(4)

R N.A.

N.A.

2**

-l b.

Low Power Reactor P-7 N.A.

R(4)

R N.A.

N.A.

- I Trips Block, Neutron Power Range c.

P-8 N.A.

R(4)

R N.A.

N.A.

I Flux, Range Neutron d.

Power Flux, P-9 N.A.

R(4)

R N.A.

N.A.

I e.

Power Range f

Neutron Flux P-10 N.A.

R(4)'

R N.A.

M.A.

1, 2

' "I TurbineI)uiseChamber f.

Pressure,

-13 N.A.

R R

N.A.

1 5-

.F

...-e..

..,..-.e,

..w=

<w.

..m

.,c,

. - - -.. -y,

...,m

-..-..i

--.m,:

TABLE 3.3-3 (Continued 1 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION G

w E

MINIMUM 7

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

!ii 3.

Containment Isolation (Continued)

3) Containment 4

2 3

1, 2, 3, 4 17 j

Pressure--High-3 c.

Purge Isolation 2

1 2

5, 6t 26 4.

Steam Line Isolation a.

Manual Initiation

1) Individual 1/ steam line 1/steamline 1/ operating 1, 2, 3, 4 24 y

steam line

2) System 2

1 2

1,2,3,4 23 b.

Automatic Actuation 2

1 2

1,2,3,4 22 Logic and Actuation Relays c.

Centainment Pressure--

3 2

2 1,2,3,4 20 High-2 a.

55 d.

Steam Line Pressure--

3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

20 m:

Low in each in any in each operating operating operating g

loop loop loop w

e.

Steam Line Pressure -

3/ steam line 2/ steam line 2/steamline 3****

20

?

Negative Rate--High in each in any in each g

operating operating operating loop loop loop

, 3" l

t J

TABLE 3.3-3 (Continued)

TABLE NOTATIONS

The Steamline Isolation Logic and Safety Injection Logic for this trip function may be blocked in this MODE below ' the P-11 (Pressurizer

. ressure Interlock) Setpoint.

- - - Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

a

During core alterations or movement of irradiated fuel within the.

l containment. The provisions of Specification 3.0.3 are not applicable.

ACTION STATEMENTS i

ACTION 14 - With the number of OPERABLE channels one less than the Minimum i

Channels OPERABLE requirement, restore the inoperable channel to j

OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 - (not used).

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed.in the tripped condition within I hour.

ACTION 17 - With the number of OPERABLE channels one. less than the Total Number of Channels, operation may proceed provided the inoperable i

channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met.

One additional 4

channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing par Specification 4.3.2.1.

ACTION 18 - With less than the Minimum Channels OPERABLE requirement, within I hour initiate and maintain operation of the Control Room Emergency.

Ventilation Systera in the recirculation mode of operation.

ACTION 19 - With the number of OPERABLE channels one less than the hinimum 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MILLSTONE - UNIT 3 3/4 3-24 Amendment No. 77, 77. M.

0379

.+.yy+,,,a s

8

+

waa a

u

.m-n -

a.. g (

f

..g x

4 TABLE 3.3-3 (Continued 1 ACTION STATEMENTS (Continued 1 j

ACTION 20 - With the number of' OPERABLE channels one less than :the Total Number of - Channels,. STARTUP and/or POWER-OPERATION reay proceed provided the following conditions are satisfied:

a.-

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and-b.

the-Minimum Channels OPERABLE requirement ' is met; however, j

the inoperable channel may be bypassed:for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.

t ACTION 21 - With less than-the Minimus Number of Channels OPERABLE, within I hour determine by observation' of the associated permissive-annunciator window (s) that the interlock is in its required state for. the existing plant condition, or apply Specification 3.0.3.-

ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to, OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 in at least HOT SHUTDOWN.within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to i

4. hours for surveillance testing per Specification 4.3.2.1 l

provided the other channel is OPERABLE.

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

j ACTION 24 - With the number of OPERABLE. channels one less than the Total Number of Channels, 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 declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

i ACTION 25 - With the number of OPERABLE channels one less than the Minimum 1

Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 ; however, one channel may be bypassed for j

up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 26 - With less than the Minimum Channels OPERABLE requirement, the containment purge and exhaust valves shall be maintained closed.

Fuel movement and CORE ALTERATIONS may continue.

The containment radiation monitoring channels required for containment area purge and' exhaust isolation are not required to be OPERABLE during the performance of Type A containment leakage rate tests.

MILLSTONE - UNIT 3 3/4 3-25 Amendment No. 77

.m

.~.

J

,7f TABLE 3.3-4

_h ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION TRIP.SETPOINTS c;

SENSOR k

TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA)

I fS)

TRIP SETPOINT ALLOWABLE VALUE 3.

Containment Isolation (Continued)

2) Automatic Actuation Logic N.A.

N.A.

'd and Actuation Relays

3) Safety Injection-See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

b. Phase "B" Isolation

1) Nanual Initiation N.A.

N.A.

R

2) Automatic Actuation N.A.

N.A.

Y Logic and Actuation t*,

Relays

3) Containment Pressure--

3.3 1.01 1.75 s 8.0 psig s 8.8 psig High-3

c. Purge Isolation N.A N. A -

N.A.

1 i R/h 1 1 R/h 4.

Steam Line Isolation

a. Nanual Initiation N.A.-

N.A.

b. Automatic Actuation Logic N.A.

N.A.

g-and Actuation Relays E

c. Containment Pressure--High-2 3.3 1.01 1.75 1 3.0 psig 5 3.8 psig I

d. Steam Line Pressure--Low 17.7 15.6 2.2 2 658.6 psig*

1 648.3 psig*

4

e. Steam Line Pressure -

5.0 0.5

.O s 100 psi /s**

1 122.7 psi /s**

~

Negative Rate--High

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION ox I%

SURVEILLANCE REQUIRENENTS U

TRIP k

ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEIL!ANCE

! FUNCTIONAL UNIT CHECK CALIBRATION TEST IEST LOGIC TEST JLSI TEST IS REQUIRED w

3. Containment Isolation

a. Phase "A" Isolation

1) Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

2) Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2, 3, 4 Logic and Actuation Relays D

3) Safety Injection See Item 1. above for all Safety Injection Surveil'ance Requirements.

Y

b. Phase "B" Isolation

1) Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3,'4 k

2) Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2, 3, 4 E.

Logic Actuation R

Relays E

z

3) Containment S

R Q

N.A.

1, 2, 3, 4 P

Pressure-High-3

c. Purge Isolation a

R M

N.A.

5, 6f N?

4. Steam Line Isolation N?

a. Manual Initiation

1) Individual N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

2) System N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

TABLE-4.3-2 (Continued)

TABLE NOTATION k

(1)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2)

This surveillance 'may be performed continuously by the emergency generator load sequencer auto test system as long as the EGLS auto test:

system is demonstrated operable by the performance of an ACTUATION LOGIC TEST at least once per 92 days.

(3)

On a monthly basis, a loss of voltage condition will be initiated at each undervoltage monitoring relay to. verify individual relay operation.

Setpoint verification and actuation of the associated logic and alarm relays will be performed as part of the channel calibration required once per 18 months.

During core alterations or movement of irradiated fuel within the i

containment. The provisions of Specification 3.0.3 are not applicable.

i

, l l

1 i

l MILLSTONE - UNIT 3 3/4 3-41 Amendment No. JJ, 7J. 7J Jpp, 0383

~.

.,. o :.

TABLE 3.3-6 lh RADIATION NONITORING INSTRUMENTATION FOR PUNT OPERATIONS G

w l

MINIMUM CHANNELS CHANNELS APPLICABLE ALARfyTRIP FUiitTIONAL UNIT TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION I

E E

1.

Containment

a. Deleted

b. RCS Leakage Detection

1) Particulate T,adioactivity N.A.

I 1, 2, 3, 4 N.A.

29

2) Gaseous Radioactivity N.A.

I 1, 2, 3, 4 N.A.

29 2.

Fuel Storage Pool Area Monitors

a. Radiation Level 1

2 1 15 mR/h 28 Y

0 1

E E

3 y

=.

. ?.

TABLE 3.3-3 (Continued)

TABLE NOTATIONS With fuel in the fuel storage pool areas.

ACTION STATEMENTS ACTION 27 -

Not used.

ACTION 28 -

With less than the Minimum Channels OPERABLE requirement, fuel movement may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel storage pool area. Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel storage pool areas.

ACTION 29 -

With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.I.

r I

i NILLSTONE - UNIT 3 3/4 3-44 Amendment No. #,

osu

..y.

,s.

TABLE 4.3-3 l3 RADIATION NOMITORING INSTRUMENTATION FOR PLANT

{

OPERATIONS SURVEILLANCE REQUIREMENTS E

ANALOG CHANNEL MODES FOR WHICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED w

w 1.

Containment a.

Deleted l

b.

RCS Leakage Detection

1) Particulate Radio-S R

Q 1, 2, 3, 4 activity

2) Gaseous Radioactivity S

R Q

1, 2, 3, 4 2.

Fuel Storage Pool Area Monitors h-a.

Radiation level S

R Q

TABLE NOTATIONS E

' With fuel in the fuel storage pool area.

Ea

?

M Y

v,

)

f}:

i.,-

e INSTRUMENTATION BASES REACTOR TRIP SYSTEM INSTRUMENTATION and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T below retpoint, prevents the opening of the main feedwater valves which were closed by a Safety Injection or High Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.

Reactor not tripped - prevents manual block of Safety Injection.

P-11 On increasing pressurizer pressure, P-11 automatically reinstates Safety Injection actuation on low pressurizer pressure and low steam line pressure. On decreasing pressure, P-11 allows the manual block of Safety Injection actuation on low pressurizer pressure and low steam line pressure.

P-12 On increasing reactor coclant loop temparature, P-12 automatically provides an arming signal to the Steam Dump System. On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the Steam Dump System.

P-14 On increasing steam generator water level, P-14 automatically trips all feedwater isolation valves, main feed pumps and main turbine, and inhibits feedwater control valve modulation.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:

(1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance. The radiation monitors for plant operations senses radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms.

NILLSTONE - UNIT 3 8 3/4 3-3 Amendment No.

0386

ML20086A344

Text

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