ML20086D801

Proposed Tech Specs Extending Surveillance Test Intervals & Allowable out-of-svc Times for Selected Instrumentation

ML20086D801
Person / Time
Site:	Monticello
Issue date:	07/05/1995
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20086D796	List: ML20086D794 ML20086D798 ML20086D801
References
NUDOCS 9507100390
Download: ML20086D801 (35)

Text

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E Exhibit B ,

Monticello Nuclear Generating Plant '  !

License Amendment Reauest dated July 5.1995 .l l

Proposed Changes Marked Up on Existing .

Technical Specification Pages.  !

' Exhibit B consists of the existing Technical Specification pages with the proposed changes marked up on those pages. Existing pages affected by this change are listed below-EaQE  !

23  !

32 33 34 i 42- l 1- 50- f

51. I 52* i 53* .[

54*  ;

i 55*

59 ,

60d*-

61 i 62 l These pages reflect proposed changes due to " Revised Core Spray Pump Flow I

and Other Editirial Corrections" submitted to the NRC by letter dated February l 12,1993.  ;

i

.I 95o710o39o 95o7o5 i PDR ADDCK 05ooo263 p .. PDR.

i-3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS B. Upon discovery that the requirements for the B. (DELETED) number of operable or operating trip systems or-instrument channels are not satisfied, action shall be initiated as follows: *

1. With one required instrument channel q inoperable in one or more trip functions, ./ p .

place the inoperable channel (s) or trip system in the tripped condition within 12 i

Q.

O d d hours, or ,

i

2. With more than one instrument channel \ bl ku C Of ( Oh N)'/

inoperable for one or more trip functions, immediately satisfy the minimum requirements I by placing appropriate channel (s), or trip bO bM%D-system (s) in the tripped condition, or U

3. Place and maintain the plant under the specified required conditions using normal operating procedures.

\

b 3.1/4.1 27 REV 131 4/16/92

~

\ " r TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT REQUIREMENTS Modes in which tunc- Total No. of Min. ho. of Operable /

M tion must be Oper- - Instrument' or Operating Instru-Limiting able or Operating ** Channels per ment Channels Per. Required Trip Function Trip Settings Refuel.(3) Startup Run Trip System Trip System (1) Condition

1. Mode Switch in .

Shutdown X X -X 1- 1 'A

2. _ Manual Scram X X X- 1 1 A-

3. Neutron Flux IRM s 120/125 (See Note 2) of full scale X X 4 3. A

a. High-High .

b. Inoperative i

4. Flow Referenced See Specifi-Neutron Flux APRM cations (See Note 5) 2.3A.1 X 3- 2 A or B

, a. High-High

b. In erative

c. Hi Flow Clamp $ 120 %

5. High Reactor Pressure s 1075 psig X X(f) X(f) 2 2 i .A (See Note 9) *

6. High Drywell Pressure s.2 psig X X(e.f) X(e.f) 2 2 A (See Note 4)

7. Reactor Low Water Level a 7 in.(6) X~ X(f) X(f) --

2 2 A

8. Scram Discharge Volume High Level

a. East s 56~ gal.(8) X(a) X(f) X(f) 2 2 A

b. West s 56 gal.(8) X(a) X(f) X(f) .2 2 A-

9. Turbine Condenser Low Vacuum- 2 23 in. Hg X(b) X(b,f) X(f) 2 -2 A or C-~

3.1/4'.1 28 .

REV 134 1/27/93 4

_ _ _ _ _ u____m. ---m-_m---ma- ____-___v-__ei.-3 ire wgr wa'em-W wamuwm auwt-hWte w w w' er e= mre edw W 1Dww- -To rur -eaem T-e oursup M--we'e e'-Ew yt - ,t-tWe>-44 dr m'h46 e veW t w$Tr e >-w eyw.+-swgy*.us ow-rw w ee w 7-Yi.sy- -

->ergr^4e-wm--hew _tw- wr--

Table 3.1.1 - Continued 6.

Seven inches on the water level instrumentation is 10'6" above the top of the active fuel at rated power

7. .

Trips upon loss of oil pressure to the acceleration relay.

8.

Limited the volume trip in setting the lines refers to the to the volume level of water in the discharge volume receiver tank and does not include switches.

9.

High reactor pressure is not required to be operable when the reactor v el ueaa r ud Reauired Conditions when minimum conditione for operation are not satisfie [fti.3.). h A. All operable control rods fully inserce e6 "

B.

Power on IRM range or below and reactor in 5Gu uup,,etue t -

r Shutdown mode.

C.

t Reactor in Startup or Refuel mode and pressure below 600 psig.

D. 4 Reactor power less than 45% (751.5 MWt.).

• • Allowable Bvoass Conditions h

It is permissible to bypass:

a.

The scram discharge volume High Water Level scram function in the refuel mod system reset.

A rod block shall be applied while the bypass is in effect. to allow reactor protection b.

TheLowCondenservacuumandMSlVclosurescramfunctio(

is below 600 psig. a1 and cartup modes if reactor pressure

c. Deleted. Typo adh $ ce. i I

d. ,

The is s 45% turbine (751.5 stop MWt). valve closure and fast control valve closure scram functions when the reactor thermal powe 3.1/4.1 30 ___ _ _ _ _

~ . ~ . , . . , ~

4u TABLE 4.1.1 SCRAM INSTRUMENT FUNCTIONAL TES R MINIMUM FUNCTIONAL TEST FREOUENCIES FOR SAFETY INSTRUMENTAt ON AND CQGR0_L._CIRCUITE INSTRUMENTATION CHANNEL FUNCTIONAL TEST MINIMUM FREOUENCY (4) liigh Reactor Pressure Trip Channel and Alarm Quarterly I!igh Drywell Pressure Trip Channel and Alarm Quarter)y Low Reactor Water Level (2, 5) Trip Channel and Alarm Quarterly liigh Water Level in Scram Discharge Volume Trip Channel and Alarm Quarterly Condenser Low Vac Trip Channel and Alarm Once each wonth Main Steam Line Isolation Valve Trip Channel and Alarm Closure Quarterly Turbine Stop Valve Closure Trip Channel and Alarm Quarterly a, Manual Scram Trip Channel and Alarm Weekly Turbine Control Valve Fast Closure '

Trip Channel and Alarm Quarterly APRM/ Flow Reference (5) Trip Output Relays Quarterly IRM (5) Trip Channel and Alarm ~4 Mode Switch in Shutdown 3  !

Place mode switch in -

E::P::_p:lingcutogsO erdiaq Cycle shutdown 1

I l

3.1/4.1

,32 , , , , , _

-. - . , . . , ~

g.-

4. .

TABLE 4.1.1 (Continued) g6

\gu Note 1: Deleted.

Note 2: performed on low re A sensor N -_ iint ch_eck dei ___ sp:n : a water level once per da ;: ' e- 5';;':

Note 3:

channels overlap at least 1/2 decade prior to every normal shutdown.e prior to every startup, and de Note 4:

Functional are tripped.tests are not required when the systems are not required to be operable or If tests are systems to an operable missed, they shall be performed prior to returning the status.

Note 5:

, A functional test of this instrument means the injection of a simulated signal into the instrument and/or initiating action.(not primary sensor) to verify the proper instrument channel response, alarm, t

3.1/4.1 33

. ne'? 12: /10/n

TABLE 4.1.2 SCRAM INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREOUEJCES FOR REACTOR PROTECTION INSTRUMENT CHANNELS INSTRUMENT CHANNEL GROUP CALIBRATION METHOD MINIMUM FREOUENCY (2)

AP2M IRM B Heat Balance Once every 3 days (4)

High Reactor Pressure B Heat Balance See Note 1 A Pressure Standard Every 3 months High Drywell Pressure A Low Reactor Water Pressure Standard Every 3 months B Pressure Standard Every Operating Cycle -

, Transmitter High Water Level in Scram Discharge Every 3 months - Trip Unit Condenser Low Vacuum '

A or B Water Level Every 3 months A Vacuum Standard Every 3 months Main Steamline Isolation Valve Closure A Observation l Turbine Control Valve Fast Closure A Every Operating Cycle Turbine Stop Valve Closure Pressure Standard Every 3 months A Observation Recirculation Flow Meters & .Every 0 erating Cycle Flow Instrumentation Pressure Standard Ever - acnt..; -

ed c3de[f Notes:

^

1. Perform calibration test during every startup and normal shutdown.

2. \

Calibration tests are not required when the systems are not required to be operable or are tripped. I

3. If(Deleted).

tests are missed, they shall be performed prior to returning the systems to an operable status.

4.

This calibration is performed by taking a heat balance and adjusting the APRM to agree with the heat balance. Alarms and trips will be verified and calibrated if necessary during functional testing.

6.

d Sen4or che<M shd he. f erbmd o n

• CROUPS: Of8 M reOrtd:T'ico b dpd3 once per b y, k

l A.

B.

Passive type devices. o Vacuum tube or semiconductor devices and detectors that drift or lose sensitivity. Y

! 3.1/4.1

! 34 A LE AdJ i %T{ L Ul J L l

l

M* ,

Bases:

4.1 The instrumentation in this section will be functionally tested and calibrated at regularly.

scheduled intervals. Specific surveillance intervals and' surveillance and maintenance outage times have been determined in accordance with NEDC-30851P, " Technical Specification Improvement Analysis for BWR Reactor Protection System," as approved by the NRC and documented in the SER dated July 15, 1987 (letter to T A Pickens'from.A Thadani).

Calibration frequency of the instrument channel is divided into two groups as defined on Table 4.1.2.

Experience with passive type instruments indicates that a yearly calibration is adequate. Wh eg T possible, however, quarterly calibration is performed. For those devices which employ amplif etc., drift specifications call for drift to be less than 0.St/ month; i.e., in the period of a month a drift of 0.5% would occur and thus provide for adequate margin. For the APRM system drift of electronic apparatus is not the only consideration in determining a calibration frequency.

Change in power distribution and loss of chamber sensitivity dictate a calibration every three days.

Calibration on this frequency assures plant operation at or below thermal limits.

a 4.1 BASES 42 NEXT PAGE IS 45 "Z'1 131 '

. /10/^2

. _ - - . - - - . . , _ _ _ - _ . - - .._.._.._.__.__...___,ua_-a_.,, . _ _ , - v,s, , .m e, ., e.,, ,, , , ,.~m-ww-~wr,c - - , - m e-w -r m m,,, e.w_ m wa=nr -- -. e-s m e m - r-- .,--e.,%---c -

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TABLE 3.2.1 - Continued Hin. No. of Operable Total No. of Instru- or Opareting Instru-ment Channels Per ment Chantals' Per Trip -Required Function Trip Settings Trip System' System-(1,2) __ Conditions

b. High Drywell Pressure $2 psig 2 .2 D' (5)

3. Reactor Cleanup System (Group 3)

a. Low Reactor Water >10'6" above 2 2 E-

-t'he top of the

~

Level active fuel

b. High Drywel re u $2 psig 2 2 E-

4. HPCI Steam Line Cstowi$ h.

a. HPCI High Steam 1 $150,000 lb/hr 2(4) 2 F.

with <60 second CNAph time lelay

b. HPCI High Steam Flow. $300,000 lb/hr 2(4) 2 F

c. HPCI Steam Line $200*F 16(4) 16 .F Area High Te t

5. RCIC Steam Line. ((3.tcupSh ,

i a. RCIC High Steam F1

$45,000 lb/hr 2(4) 2. C with 5 i 2 see time delay

b. RCIC Steam Line Area $200*F- 16(4) 16 C

6. Shutdown Cooling

-Supolv Isolation-

a. Reactor' Pressure $75 psig 2(4) 2 C Interlock, at pump suction.

4

. 3.2/4.2 50 r; 07 1/22/00 ,

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i (a s 6 u l h eA is .

N6 con AAeted one. choned Table 3.2.1 - Continued l

OT S "a C u p., 1, 2 ..2 3 e ere shall be two operable or tripped trip systems for each function. A channel may be p a eu zu mi mugeriute status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip. system is monitoring that parameter. _

p:rch': er tripp:d trip 27:t:::

Fer Cr gp: ':, 5 :nd ?::tter Pr:::ur: Interlech: th:r : hell he t":

f:= = t i ... . - _

._ f:r :].:5 N (2)1 er C_ccup: 1, 2 =;-d 3, on discovery that minimum requirements for the number of operable or operating trip l ystems or inscniiinmt7 annels are not satisfied action shall be initiated as follows:

l (a) With one required instrument channel inoperable in one or more trip or- functions, place the inoperable channel (s) or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, (b) With more than one instrument channel inoperable for one or more trip functions, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or <

(c) Place the plant under the specified required conditions using normal operating procedures. _

For Cro s 4, 5 and Reac r Pre ure Int loc s on dis Aery at a num r utre nts f the aber f ope le or op ating ip syst s or strument hannel are n sati ed a ion s be niti d to:

l Sat fy the quire nts by acing propri e cha els o syste in t tri ed co tio (a

ace th lant der the pecifie requi d con tions sing rmal erati g proc dures

)

(3) Low pressure in main steam line only need to be available in the RUN positioit.  ;

(4) All instrument channels are shared by both trip systems.

(5) May be bypassed when necessary only by closin6 the manual containment isolation valves during purging for containment'inerting or de-inerting. Vers.fication of the bypass condition shall be noted in the control room log.. Also, need not be operable when primary containment integrity is not required.

• Required conditions when minimum conditions for operation are not satisfied.

A. Group 1 isolation valves' closed.

B. Reactor Power on'IRM range or.below and reactor in startup, refuel, or shutdown mode.

C. Isolation Valves closed for: Shutdown Cooling System, and Reactor llead Cooling Line.

D. Comply with Condition C. above.

E. Isolation Valves closed for: Reactor Cleanup System.

, F. IIPCI steam line _ isolated. (See specification 3.5 for additional requirements.) .

C. RCIC steam line isolated.

' 51 3.2/4.2 RE7 i40 0 / 7 /0 ',  !

/\

Table 3.2.2 Instrumentation That Initiates Emergency Cor Cooling Systems Minimum NA of Oper-Minimum No. of able or Op4 ting Operabl Operati /{r al No. of Instru- Instrume ent Channels Per PerTripSy/te nnels Required

-l' Function Trio Settinz Systems O")(G Trio System / (&L 3) Conditions

• A. Core Sorav and LPCI

1. Pump Start

a. Low Low Reactor 26'6"s6'10" 2 4(4) 4 A.

Water Level and

b. i. Reactor Iow 2450 psig 2 2(4) 2 A.

Pressure Permissive or

11. Reactor Low 20i1 min 2 1 1 B.

Pressure Permissive Bypass Timer

c. High Drywell 52 psig 2 4(4) 4 A.

Pressure (1)

2. Low Reactor Pressure 2450 psig 2 2(a) 2 A.

(Valve Permissive)

3. Loss of Auxiliary -----

2 2(2) 2 A.

Power d changes due This page reflects y Pump propose Flow and" submitted to the to" Revised Core Spra y 12,1993

] 2/4.2

/

/ OtherEditorialCorrectionsNRC byletter dated 32

D g

y/x Table 3.2.2 Instrumentation That Initiates Emergency ore Cooling Syste

/

Minimum Wo. of Oper-Minimum No. of able or erating Operable .

Total No. of Instru- Instrumen Ch els OperatingjTrip ment Channels Per Per Trip S Required Function Trio Settine Systems (B)(LS Trio System 3) Conditions

• B. HPCI System

1. High Drywell $2 psig 1 4 4 A.

Pressure (1)

2. Low-Iow Reactor 26'6"s6'10" 1 4 4 A.

Water Level C. Automatic Deores-surization

1. Low-Low Reactor 26'6"s6'10" 2 2 2 B.

Water Level and

2. Auto Blowdown 5120 seconds 2 1 1 B.

Timer and

3. Low Pressure Core 5100 psig 2 12(4) 12(4) B.

Cooling Pumps Dis-Charge Pressure Interlock dos ged cpa M

g # p\o88,odgoibe teged5fpts8 o M CJ93' i y?"ggyf.?sn*

3.2/4.2 I O\D cg\et8 53 es

0 1

Table 3.2.2 - Continued Instrumentation That Initiates Emergency Core Cooline Syst.m

~

Min. No. of Ope -

Min. No. able or Operatin of Operable Tota o. of Instru- Instrument Chan is or Operating [ Channels Per Per Trip System Required Function Trio Settine Trio Systems (3 hlb rio System ( IthYonditions*

D. Diesel Generator

1. Degraded or Loss of Voltage Essential Bus (5)

2. Low Low Reactor ;t6 ' 6"s6 ' 10" 2 4(4) 4 C.

Water Level

3. High Drywell Press 52 psig 2 4(4) 4 C.

NOTES:

1. High drywell pressure may be bypassed when necessary only by closing the manual containment isolation valves during purging for containment inerting or de-inerting. Verification of the bypass condition shall be noted in the contros room log. Also need not be operable when primary containment integrity is not required.

2. One instrument channel is a circuit breaker contact and the other is an undervoltage relay.

60

,# *'#6 e S

te e

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. .oN.'h vo**

S 3.2/4.2 0 69 54

, p L - _ . .

s p ., M s. n .f_-7 m -

c. With one required instnament channel inoperable per trip function, place the .

' inoperable channel or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or .

g C, . .

b. With more than one instrument channel per trip system inoperable, immediately :.

[ Notes-Table 3.2.2 - Continued

3. Upon . discovery that minimum requirements for the number of operable or operating trip systems, or instrument channels are not satisfied action shall be initiated 4e+ n .{ 6 g fe) Sfatisfy the requirements by placing. appropriate channels or systems in the tripped condition, or C. M Place the plant under the specified required conditions using normal operating procedures.

4. All instrument channels are shared by both trip systems.

5. See table 3.2.6.

• Required conditions when minimum conditions for operation are not satisfied.

A. Comply with Specification 3.5.A.

B. Reactor pressure 5150 psig.

C. Comply with' Specification 3.9.B.

4[ 6.tee ,do s-em in ,- tdp,.d

~

A channel (a shared channel is considered one channel) may be p_

dc .egpe,placed a_ ,heinsame an inoperable t, s,ste statusngfor ,h.t up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required g pcr y

gd$. w . +

/

. m, , Ways O 8 3 3.2/4.2 W 55

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Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation Isolation And Standby Gas Treatuent System Initiation

- Min. No. of Operable Total No. of Instru- or Operating Instrument ment Channels Per Trip Channels Per Trip Required Function Trin Settines System System Gh,Lc s 1. 21 Conditions *

1. Low Low Reactor 26'-6", 56'-10" 2 2[ Note 5k,3,kh A. or B.

Water Level ("viu 3)

2. liigh Drywell Pres- $2 psig 2 2heresl[5,4 A. or B.

sure wv ue ,

3. Reactor Building $100 mR/hr 1 1(Not[4) A. or B.

Plenum Radiation Monitors

4. Refueling Floor s100 mR/hr 1 1(Note [4) A. or B.

Radiation Monitors Notes:

(1) There shall be two operable or tripped trip systems for each function with two instrument channels per trip system and there shall be one operable or tripped trip system for each function with one instrument channel per trip system.

(2) Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated to:

(a) Satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (b) Place the plant under the specified requir:cd conditions using normal operating procedures.

(3) Need not be operable when primary containment integrity is not required.

-(4.)Alag ot theutwireenitors_atayde -bytrash intenance and/or testing.

Fog poM T*J V SEE ons 61TAcHEb SHEGT

-. wr.ditions'for operation are not satisfied.

A. The reactor building ventilation system isolated and the standby gas treatment system operating.

B. Establish conditions where secondary containment is not required.

59 3.2/4.2 RC'.' 1!,1 0/0/9'-

(5) Upon discovery that minimum requirements for the number of oper3ble or operating trip systems or instrument channels are not satisfied -

action shall be initiated as follows:

(a) With one required instrument channel inoperable per trip function, place the inoperable channel or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or -

(b)- With more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures.

(6) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

A A gr ohr gwuTe oh p(g e I9.

[Vd' c. With one required instrument channel inoperable per trip function, place the inoperable channel or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or

(/ 0,6 L N

b. With more than one instrument channel per trip system inoperable, immediately I

,/ ' ~ - f_e M- -- -

Table 3.2.8 Other Instrumentation Minimum No. of Minimum No. of Oper- 1 I

Operable or Total No. of Instru- able or Operating Required

! Function Trip Setting Operating Trip ment Channels Per Instrument Channels Conditions

• System (1)M) Trio System Per Trio System (I M f

A. RCIC Initiation ,

1. Low-Low Reactor Level 26'6"& 56'10" above top of 1

[9 / 'l B active fuel I

B. HPCI/RCIC Turbine (

Shutdown * -

4'

a. High Reactor Level $14'6" above 1 2 2 A top of active fuel C. HPCI/RCIC Turbine , 8ged&

\*

Suction Transfer 1 9

'I

a. Condensate Storage 22'0" above 1 M \0 2 2 C Tank Low Level tank bottom

\

E9Il:

1. Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied, action shall be initiated -t*+ as -fo\\ o w s '

,+r statisfy the requirements by placing the appropriate channels or aystems in the tripped condition, or (Turbine /Ferireter Trip enly), er C, 6. Place the plant under the specified required condition using normal operating procedures. I e '?-

• Required conditions when minimum conditions for operation are not satisfied:

A. h. _". _f_ N..' b. _ b ,*'k _h1 ., "M k.. _b b_* u. _m .

B. Comply with Specification 3.5.D.

C. Align HPCI and RCIC suction to the suppression pool. Restore channels to operable status within 30 days or place the plant in Required Condition A. 4oc R pc.I, o, & _(o r RC.tC.

3.2/4.2 _ _ -.

cj ~2. A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition ~)

q provided at least onegperable channel in the same trip system is monitoring that parameter. ,/

w

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m-

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Table 4.2.1 Minimum Test and Calibration Frequency for Core Cooling Rod Block and Isolation Instrumentation-Instrument Channel Test (3) Calibration (3) Sensor Check (3Y ECCS INSTRUMENTATION

1. v 9

Reactor Low-Low Water Level Once/ month $ ote 5) Every Operating Cycle - Transmitter Once/3 months -

g Trip Unit Once/ Shift

2. Drywell High Pressure V

3. Reactor Low Pressure (Pump Start) Once/ nth 5 Once/3 months None

4. Once nth 5 Reactor Low Pressure (Valve Permissive) nth 5 Once/3 months None 1

5. Undervoltage Emergency Bus I Q nce Once/3 months None-

6. Low Pressure Core Cooling Pumps Ketue n Outage Refueling Outage None-Discharge Pressure Interlock

7. Loss of Auxiliary Power Once/m}onths Once/3 months 'None

8. eu ng Outage Condensate Storage Tank Level Refueline Outage Refueling Outage None

9. Reactor High Water Level Refueling Outage None M / month 5(Note Every Operating Cycle - Transmitter Every 3' months -

Trip. Unit ROD BLOCKS Once/ Shift

1. APRM Downscale 3

2. APRM Flow Variable Once/hnthfNote5) Once/3 months None

3. IRM Upscale Once/Konthf Note 5) Once/3 months None

4. IRM Downscale -Lu -fB TS Note 2 Note 2

5. No 5 Note 2 RBM Upscale Note 2

6. RBM Downscale ce/ynt Note 5) Once/3 months- None

7. SRM Upscale nee /monthf Note 5) Once/3 months None

8. No 2 Note 2 SRM Detector Not-Full-In Position Notes (2,9) Note 2

9. Scram Discharge Volume-High4 Level Note 2 None Once/3 months Refueling outage None MAIN STEAM LINE (CROUP I) ISOLATION

1. Steam Tunnel High Temperature

2. Steam Line High Flow Refueling Outage Refueling Outage None Once/3 months Once/3 Months 'Once/ Shift 7

3.2/4.2 61

""' 131 t/lf/^2

f\&Yv{ 6 Table 4.2.1 - Dontinuzd Minimum Test and Calibration Frequency For Core Cooling Rod Block and Isolation Instrumentation Instrument Channel Test (3) Calibration (3) Sensor Check (3)

3. Steam Line Low Pressure Once/3 months once/3 months -None t

4. Reactor Low Low Water 1.evel Once/3 months (Note 5) Every Operating Cycle- Once/ shift Transmitter -

Once/3 Months-Trip Unit CONTATNMENT IS01ATION (CROUPS 2 & 3)

Reactor Low Water Level (Note 10)

1. - -

Drywell liigh Pressure (Note 10)

2. - -

IIPCI (CROUP 4) IS0TATION 3 v r Steam Line liigh Flow Once/ month 5 Once/3 months None

1. None

2. Steam Line liigh Temperature once/ onth<, Once/3 months i

RCIC (CROUP 5) IS01ATION 3 i

' t-Steam Line liigh Flow Once/ month s once/3 months None

1. None

2. Steam Line liigh Temperature Once/gonth> Once/3 months REACTOR BUILDING VENTIIATION & STANDBY CAS TREATMENT

1. Reactor Low Low Water Level Once/3 months (Note 5) Every Operating Cycle -

Once/ shift Transmitter Once/3 months - Trip Unit-2.

3.

Drywell liigh Pressure (Note 10)

Radiation Monitors (Plenum)

-h Once/monthf Once/3 months once/ day )

Radiation Monitors (Refueling Floor) Once/ month , Once/3 months Note 4 4.

RECIRCUIATION PUMP TRIP AND ALTERNATE ROD INJECTION $

Once/Ionth> Note 5) Once/ Operating Cycle- Once/ Day

1. Reactor liigh Pressure Transmitter Once/3 Months-Trip Unit

2. Reactor Iow Low Water Level Once/mont (Note 5)- Once/ Operating Cycle- Once/ shift Transmitter Once/3 Months-Trip Unit SilUTDOWN COOLING SUPPIN IS01ATION v$ None

1. Reactor Pressure Interlock Once/ months Once/3 Months 3' /b' b..,,,

-. . . . n, ,,n, ,in ,.-.

l Exhibit C Monticello Nuclear Generating Plant i

License Amendment Reauest dated July 5.1995  ;

4 i

Revised Technical Specification Pages Exhibit C consists of the Technical Specification pages with the proposed changes incorporated. Existing pages affected by this change are listed below:

1 r

Eagg l 30 32 33 34 42 50 51 ,

52*

53* ,

54*  !

55*

59  ;

60d*

61  ;

62 i These pages reflect proposed changes due to " Revised Core Spray Pump Flow .

and Other Editirial Corrections" submitted to the NRC by letter dated February .

12,1993.  !

Table 3.1.1 - Continued

6. Seven inches on the water level instrumentation is 10'6" above the top of the active fuel at rated power.

7. Trips upon loss of oil pressure to the acceleration relay.

8. Limited trip setting refers to the volume of water in the discharge volume receiver tank and does not include the volume in the lines to the level switches.

9. High reactor pressure is not required to be operable when the reactor vessel head is unbolted.

~-

• Requi anditions when minimum conditions for operation are not satisfied. (ref. 3.1.B) 1 A. All operable control rods fully inserted.

B. Power on IRM range or below and reactor in Startup, Refuel, or Shutdown mode.

C. Reactor in Startup or Refuel mode and pressure below 600 psig.

D. Reactor power less than 45% (751.5 MWt.).

• • Allowable Bypass Conditiens It is permissible to bypass:

a. The scram discharge volume High Water Level scram function in the refuel mode to allow reactor protection system reset. A rod block shall be applied while the bypass is in effect.

b. The Low Condenser vacuum and MSIV closure scram functions in the Refuel and Startup modes if reactor pressure l is below 600 psig.

c. Deleted.

d. The turbine stop valve closure and fast control valve closure scram functions when the reactor thermal power is s 45% (751.5 MWt).

3.1/4.1 30

s TABLE 4.1.1 SCRAM INSTRUMENT Fl]NCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREOUENCIES FOR SAFETY INSTRUMENTATION AND CONTROL CIRCUITS INSTRUMENTATION CHANNEL FUNCTIONAL TEST MINIMUM FREOUENCY (4)

High Reactor Pressure Trip Channel and Alarm Quarterly High Drywell Pressure Trip Channel and Alarm Quarterly Imv Reactor Water Level (2, 5) Trip Channel and Alarm Quarterly High Water Level in Scram Discharge Volume Trip Channel and Alarm Quarterly-Condenser low Vac Trip Channel and Alarm Once each month Main Steam Line Isolation Valve Trip Channel and Alarm Quarterly Closure Turbine Stop Valve Closure Trip Channel and Alarm Quarterly Manual Scram Trip Channel and Alarm Weekly Turbine Control Valve Fast Closure Trip Channel and Alarm Quarterly APRM/ Flow Reference (5) Trip Output Relays Quarterly IRM (5) Trip Channel and Alarm Note 3 Mode Switch in Shutdown Place mode switch in Every Operating Cycle j sbv.edown 3.1/4.1 32

TABLE 4.1.1 (Continued)

Note 1: Deleted.

l-Note 2: A sensor check shall be performed on low reactor water level once per day.

Note 3: Perform functional test prior to every startup, and demonstrate that the-IRM and APRM channels overlap at least 1/2 decade prior to every normal shutdown.

Note 4: Functional tests are not required when the systems are not required to be operable or-are tripped. If tests are missed, they shall be performed prior to returning the systems to an operable status.

Note 5: A functional test of this instrument means the injection of a simulated signal into the instrument (not primary sensor) to verify-the proper instrument channel response, alarm, and/or' initiating action.

3.1/4.1 '33

- - . - . _ - . - _ . . - - , . .- - . .-_.a -. . . - . . - . . . _ - - - - - . _ . _ _ - - - - - - _ - _ ,

TABLE 4.1.2 SCRAM INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREOUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS INSTRUMENT CHANNEL GROUP CALIBRATION METHOD MINIMUM FREOUENCY (2)

APRM B Heat Balance Once every 3 days (4)

IRM B Heat Balance See Note 1 High Reactor Pressure A Pressure Standard Every 3 months High Drywell Pressure A Pressure Standard Every 3 months Low Reactor Water B Pressure Standard Every Operating Cycle -

Transmitter Every 3 months -

Trip Unit High Water Level in Scram Discharge A or B Water Level Every 3 months Condenser Low Vacuum A Vacuum Standard Every 3 months Main Steamline Isolation Valve Closure A Observation Every Operating Cycle Turbine Control Valve Fast Closure A Pressure Standard Every 3 months Turbine Stop Valve Closure A Observation Every Operating Cycle Recirculation Flow Meters & -

Pressure Standard Every Operating Cycle (5) l Flow Instrumentation Notes:

1. Perform calibration test during every startup and normal shutdown.

2. Calibration tests are not required when the systems are not required to be operable or are tripped.

If tests are missed, they shall be performed prior to returning the systems to an operable status.

3. (Deleted).

4. This calibration is performed by taking a heat balance and adjusting the APRM to agree with the heat balance. Alarms and trips will be verified and calibrated if necessary during functional testing.

5. A sensor check shall be performed on APRM recirculation flow signals once per day. l1

• CROUPS:

A. Passive type devices.

B. Vacuum tube or semiconductor devices and detectors that drift or lose sensitivity.

3.1/4.1 34

Bases:

4.1 The instrumentation in this'section will ba functionally tested and calibrated at regularly scheduled-intervals. Specific surveillance intervals and surveillance and maintenance outage times have been determined in accordance with dEDC-30851P, " Technical Specification Improvement Analysis i

for BWR Reactor Protection System," as approved by the NRC and documented in the SER dated July 15, 1987 (letter to T A Pickens from A Thadani).

Calibration frequency of the instrument channel is divided into two groups as defined on Table 4.1.2.

Experienen with passive type instruments indicates that a yearly calibration is adequate. Where possible, however, quarterly calibration is performed. For those devices which employ amplifiers l etc., drift specifications call for drift to be less than 0.5%/ month; i.e., in the period of a month a drift of 0.5% would occur and thus provide for adequate margin. For the APRM system,.

drift of electronic apparatus is not the only consideration in determining a calibration frequency.

Change in pewer distribution and loss of chamber sensitivity dictate a calibration every.three days.

Calibration on this frequency assures plant operation at or below thermal limits.

4.1 BASES 42 NEXT PAGE IS 45

TABLE 3.2.1 - Continued Min. No. of Operable l

Total No. of Instru- or Operating Instru-ment Channels Per ment Channels Per Trip Required Function Trio Settinas Trio System System (1.2) Conditions

b. High Drywell Pressure 52 psig 2 2 D (5)

3. Reactor Cleanup System (Group 3)

a. Low Reactor Water ;t10'6" above 2 2 E Level the top of the active fuel

b. High Drywell Pressure 52 psig 2 2 E

4. HPCI Steam Lines (Groun 4)

a. HPCI High Steam Flow $150,000 lb/hr 2(4) 2 F with 560 second time delay

b. HPCI High Steam Flow s300,000 lb/hr 2(4) 2 F

c. HPCI Steam Line s200*F 16(4) 16 F l Area High Temp. l S. RCIC Steam Lines (Group 5)

a. RCIC High Steam Flow $45,000 lb/hr 2(4) 2 G with 5 1 2 see time delay

b. RCIC Steam Line Area s200*F 16(4) 16 G

6. Shutdown Cooling Supolv Isolation

a. Reactor Pressure 575 psig 2(4) 2 C Interlock at pump suction 3.2/4.2 50 REV

lable 3.2.1 - Continued NOTES:

(1) There shall be two operable or tripped trip systems for each function. A channel (a shared channel is considered I one channel) may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.

(2) Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated as follows:

(a) With one required instrument channel inoperable in one or more trip functions, place the inoperable channel (s) or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (b) With more than one instrument channel inoperable for one or more trip functions, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures.

1 (3) Low pressure in main steam line only need to be available in the RUN position.

(4) All instrument channels are shared by both trip systems.

(5) May be bypassed when necessary only by closing the manual containment. isolation valves during purging for containment inerting or de-inerting. Verification of the bypass condition shall be noted in the control room log. Also, need not be operable when primary containment integrity is not required.

• Required conditions when minimum conditions for operation are not satisfied.

A. Group 1 isolation valves closed.

B. Reactor Power on IRM range or below and reactor in startup, refuel, or shutdown mode.

C. Isolation Valves closed for: Shutdown Cooling System, and Reactor Head Cooling Line.

D. Comply with Condition C. above.

E. Isolation Valves closed for: Reactor Cleanup System.

F. HPCI steam line isolated. (See specification 3.5 for additional requirements.)

G. RCIC steam line isolated.

3.2/4.2 51

Table 3.2.2 Instrumentation That Initiates Emergency Core Cooling Systems -

Minimum No. of Oper-Minimum No. of able or Operating Operable or Total No. of Instru- Instrument Channels Operating Trip ment Channels Per Per Trip System Required Function Trio Settinz Systems (3.6) Trio System (3.6) Conditions

• l-A. Core Sorav and LPCI

1. Pump Start

a. Low Low Reacter 26'6"s6'10" 2 4(4) 4 A.

Water Level and

b. 1. Reactor Low 2450 psig 2 2(4) 2 A.

Pressure Permissive or

11. Reactor Low 2011 min 2 1 1 B.

Pressure Permissive Bypass Timer

c. High Drywell 52 psig 2 4(4) 4 A.

Pressure (1)

2. Low Reactor Pressure 2450 psig 2 2(4) 2 A.

(Valve Permissive)

3. Loss of Auxiliary ----- 2 2(2) 2 A.

Power 3.2/4.2 52

Table 3.2.2 Instrumentation That Initiates Emergency Core Cooling Systems ,

1 Minimum No. of Oper-Minimum No. of able or Operating j Operable or Total No. of Instru- Instrument Channels i Operating Trip ment Channels Per Per Trip System Required '

Function Trio Settinn Systems (3.6) Trio System (3.6) Conditions

• l B. HPCI System 1

i 1. High Drywell s2 psig 1 4 4 A.

I Pressure (1)

2. Low-Iow Reactor 26'6"s6'10" 1 4 4 A.

Water Level {

C. Automatic Deores-surization

1. Low-Low Reactor 26'6"s6'10" 2 2 2 B.

Water Level and

2. Auto Blowdown 5120 seconds 2 1 1 B.

Timer and

3. Low Pressure Core $100 psig 2 12(4) 12(4) B.

Cooling Pumps Dis-Charge Pressure Interlock 3.2/4.2 53

Table 3.2.2 - Continued Instrumentation That Initiates Emergency Core Cooline System Min. No. of Oper-Min. No. of able or Operating Operable or Total No. of Instru- Instrument Channels Operating Trip ment Channels Per Per Trip System Required Function Trio Settine Systems (3.6) Trio System (3.6) Conditions

• l D. Diesel Cenerator

1. Degraded or Loss of Voltage Essential Bus (5)

2. Low Low Reactor 26'6"s6'10" 2~ 4(4) 4 C.

Water Level

3. High Drywell Press 52 psig 2 4(4) 4 C.

NOTES:

1. High drywell pressure may be bypassed when necessary only by closing the manual containment isolation valves during purging for containment inerting or de-inerting. Verification of the bypass condition shall be noted in the control room log. Also need not be operable when primary containment integrity is not required.

2. One instrument channel is a circuit breaker contact and the other is an undervoltage relay.

3.2/4.2 54

____.-a. _-_.___m.. ______m______s.___ _ _ , _ry ______

Table 3.2.2 - Continued Notes:

3. Upon discovery that minimum requirements for-the number of operable or operating trip systems, or instrument channels are not satisfied action shall be initiated as follows:

(a) With one required instrument channel inoperable per trip function, place the inoperable channel or trip system.

in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (b) With more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing a',,propriate channels cr systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures..

4. All instrument channels are shared by both trip systems.

5. See table 3.2.6.

6. A channel (a shared channel is considered one channel) may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.

O Required conditions when minimum conditions for operation are not satisfied.

A. Comply with Specification 3.5.A.

B. . Reactor pressure s150 psig.

C. Comply with Specification 3.9.B.

3.'2/4.21 55

T&blo 3.2.4 In=trumentation Th:t Initiates R;cetor Building Ventilstion Iscicticn And Standby Gas Trestrent Systea Initiation Min. No. of Operable Total No. of Instru- or Operating Instrument ment Channels Per Trip Channels Per Trip Required Function Trio Settines System System Conditions

• j 1. Low Low Reactor 26'-6", s6'-10" 2 2 (Notes 1,3,5,6) A. or B.

Water Level

2. High Drywell Pres- 52 psig 2 2 (Notes 1,3,5,6) A. or B.

, sure 1

3. Reactor Building s100 mR/hr 1 1 (Notes 1,2,4) A. or B.

Plenum Radiation Monitors

4. Refueling Floor $100 mR/hr 1 1 (Notes 1,2,4) A, or B.

Radiation Monitors Notes:

(1) There shall be two operable or tripped trip systems for each function with two instrument channels per trip system and there shall be one operable or tripped trip system for each function with one instrument channel per trip system.

(2) Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated to:

(a) Satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (b) Place the plant under the specified required conditions using normal operating procedures.

(3) Need not be operable when primary containment integrity is not required.

(4) One of the two monitors may be bypassed for maintenance and/or testing.

(5) Upon discovery that minimum requirements for the number of operable trip systems or instrument channels are not l satisfied action shall be initiated as follows:

(a) With one required instrument channel inoperable per trip function, place the inoperable channel or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (b) With more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures.

(6) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip  !

system in the tripped condition provided that at least one other operable channel in the same trip system is '

monitoring that parameter.

• Required Conditions when minimum conditions for operation are not satisfied.

A. The reactor building ventilation system isolated and the standby gas treatment system operating.

B. Establish conditions where secondary containment is not required.

3.2/4.2 59

. Table-3.2.8 Other Instrumentation Minimum No. of Minimum No. of Oper- . .

Operable or Total No. of Instru- able or Operating- Required'.

Function Trip Setting Operating Trip ment Channels Per Instrument Channels Conditions

• i-System (1.2) Trio System Per Trio System (1.2) -l A. RCIC Initiation

1. Low-Low Reactor Level 26'6"& s6'10" 1 4 4 B ;l above top of active fuel B. HPCI/RCIC Turbine Shutdown

a. High Reactor level sl4'6" above 1 2 2 A top of active fuel C. HPCI/RCIC Turbine Suction Transfer

a. Condensate Storage 22'0" above- 1 2 2 C Tank Low Level tank botton HQIg:

1. Upon discovery that minimum requirements for- the number of operable or operating trip systems or instrument channels are not satisfied, action shall be-initiated as follows:

a. With one required instrument channel inoperable per trip function, place the inoperable channel or trip system'in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or-

b. With more than one instrument' channel per trip system inoperable, immediately satisfy the requirements by placing  !

the appropriate channels or systems in the tripped condition, or

c. Place the plant under the specified required condition using normal operating procedures.

2. A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing-the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.

• Required conditions when minimum conditions for operation are'not satisfied:

A. Comply with Specification 3.5.A. '

~B. Comply with Specification 3.5.D.

C. Align HPCI and RCIC suction to the suppression pool. Restore channels to operable status'within 30 days or place the:

plant in Required Condition A for HPCI, or B for RCIC. g.

3.2/4.2 60d

___ _ ___x-____--____- - _ _ _ _

g 1

-Table 4.2.1 Minimum Test and Calibration Frequency for Core Cooling Rod Block and Isolation Instrumentation Instrument Channel Test (3) Calibration (3) Sensor Check (3)

ECCS INSTRUMENTATION

1. Reactor low-Low Water Level Once/3 months (Note 5) Every Operatir.g l- l

, Cycle - Transmitter once/3 mon:.hs -

Trip Unit Once/ Shift

2. Drywell High Pressure Once/3 months once/3 months None

3. Reactor Low Pressure (Pump Start) Once/3 months Once/3 months None

4. Reactor. Low Pressure (Valve Permissive) Once/3 months Once/3 months None

5. Undervoltage Emergency Bus Refueling Outage Refueling Outage None

6. Low Pressure Core Cooling Pumps l Discharge Pressure Interlock Once/3 months Once/3 months None. l l 7. Loss of Auxiliary Power Refueling Outage Refueling Outage Note l 8. Condensate Storage Tank Level Refueling Outage Refueling Outage None

9. Reactor High Water Level Once/3 months (Note 5) Every Operating l Cycle - Transmitter Every 3 months -

Trip Unit Once/ Shift ROD BIDCKS

1. APRM Downscale Once/3 months (Note 5) Once/3 months None

2. APRM Flow Variable Once/3 months (Note 5) Once/3 months None

3. IRM Upscale Notes (2,5) Note 2 Note 2

4. IRM Downscale Notes (2,5) Note 2 Note 2

5. RBM Upscale Once/3 months (Note 5) Once/3 months None

6. RBM Downscale Once/3 months (Note 5) Once/3 months None

7. SRM Upscale Notes (2,5) Note 2 Note 2

8. SRM Detector Not-Full-In Position Notes-(2,9) Note'2 None

9. Scram Discharge Volume-High Level Once/3 months Refueling outage None MAIN STEAM LINE (CROUP I) ISOIATION

1. Steam Tunnel High Temperature Refueling Outage Refueling Outage None

2. Steam Line High Flow Once/3 months Once/3 Months Once/ Shift 3.2/4.2 61 REV

-h_-________ - _ _ - - _ _ - _ _ _ . - - - .- - _ .

-r-- ,,

Table 4.2.1 - Continued Mini:ntun Test and Calibration Frequency For Core Cooling Rod Block and Isolation Instrumentation bst.went Channel Test (3) Calibration (3) Sensor Check (3)

3. Steam Line Loi Pressure Once/3 months Once/3 months None

4. Reactor Low Low Water Level Once/3 months (Note 5) Every Operating Cycle- Once/ shift Transmitter Once/3 Months-Trip Unit CONTAINMENT IS01ATION (GROUPS 2 6 3)

1. Reactor Low Water Level (Note 10) - - -

2. Drywell High Pressure (Note 10) - - -

HPCI (CROUP 4) ISOLATION

1. Steam Line High Flow Once/3 months Once/3 months None

2. Steam Line High Temperature Once/3 months Once/3 months None RCIC (CROUP 5) ISOLATION

1. Steam Line High Flow Once/3 months once/3 months lione

2. Steam Line High Temperature Once/3 months Once/3 months hine RFACTOR BUILDING VENTIIATION & STANDBY CAS ' TREATMENT

1. Reactor Low Low Water Level Once/3 months (Noto 5) Every Operating Cycle - Onca/ shift Transmitter Once/3 months - Trip Unit

2. Drywell High Pressure (Note 10) - - -

3. Radiation Monitors (Plenum) Once/3 months Once/3 months Pace / day

4. Radiation Monitors (Refueling Floor) Once/3 months Once/3 months Note 4 RECIRCUIATION PUMP TRIP AND ALTERNATE ROD INJECTION

1. Reactor High Pressure Once/3 months (Note 5) Once/ Operating Cycle- Once/ Day l Transmitter Once/3 Months-Trip Unit

2. Reactor Low Low Water Level Once/3 months (Nete 5) Once/ Operating Cycle- Once/ shift l Transmitter Once/3 N eths-Trip Unft SHUTDOWN COOLING SUPPLY ISOIATION

1. Reactor Pressure Interlock Once/3 months Once/3 Months None l 3.2/4.2 62

. . . - . . . - - _ _ - _ _ _ _ _ _ _ - - _ _ .