ML20065B699

Proposed Tech Specs Re Standby Gas Treatment Sys Initiation Instumentation

ML20065B699
Person / Time
Site:	Monticello
Issue date:	03/28/1994
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20065B690	List: ML20065B685 ML20065B699 ML20065B985
References
NUDOCS 9404040094
Download: ML20065B699 (9)

Text

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O Exhibit B Monticello Nuclear Generating Plant Liggnse Amendment Recuest dated March-28, 1994 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:

Pace 59 62 63a (no changes, for information only) 70 I

j l

9404040094 940328 l PDR ADOCK 05000263 l

p PDR l

l l

g m Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation Isolation -

And Standby Gas Treatment System Initiation Min. No. of Operable Total No. of Instru- or Operating Instrument ment Channels Per Trip Channels Per Trip Required Function Trip Settings System System (Notes 1. 2) Conditions

• L ow Lo v'

l. Lew Reactor Water 210'5" chovc 2 2 A. or B.

Level (Note 3) the tcp cf-the

. . a ..- r,

2. High Drywell Pres-k $2 S psig V ((o'-l$' 2 2 A. or B.

sure (Note 3)

3. Reactor Building $100 mR/hr 1 1 (Note 4) A. or B.

Plenum Radiation Monitors

4. Refueling Floor $100 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 required conditions using normal operating procedures.

l (3) Need not be operable when primary containment integrity is not requiredg' (4) One of the two monitors may be bypassed for maintenance and/or testing.

• 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 REV 124 0/5/00

[ ,

~

I Table 4.2.1 - Continusd -

Minimum Test and Calibration Freqcc.raj for Core Cooling j Rod Block and Isolation Instrumentation

, Instrument Channel Test (3) Calibration (3) Sensor Check (3) l

3. Steam Line Low 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

?nce/3 months - Trip Unit CONTAINMENT ISOIATION (CROUPS 2 & 3) t

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

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

HPCI (CROUP 4) ISOLATION

1. ' Steam Line High Flow Once/mont'- Once/3 months None

2. Steam Line liigh Temperature Once/ month Once/3 months None RCIC (CROUP 5) IS01ATION ,

1. Steam Line liigh Flow Once/ month once/3 months None

2. Steam Line liigh Temperature ~Once/ month Once/3 months None REACTOR BUILDING VENTIIATION / srAN61 GAS 7/EMMenr 3Y. Radiation Monitors (Plenum) -Once/ month once/3 months YZ. Radiation Monitors (Refueling Floor) once/ day ,

Once/ month Once/3 months Note 4 t RECIRCULATION PUMP TRIP AND ALTERNATE ROD INJECTION

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

2. Reactor Low Low Water Level  !

Once/ month (Note 5) Once/ Operating Cycle- Once/ shift Transmitter Once/3 Months-Trip Unit SHUTDOWN COOLING SUPPLY ISOLATION i

1. Reactor Pressure Interlock Once/ month once/3 Months- None i . Rw.% kow Lo w O m u / % e o ,6 %s(rko k.5) E very Operekia} Lyck.- O nu./Sk A+

WbeLet l Tewas.a-fk <- '

3.2/4.2 ~

62 -

, D.ywe Il flig.b Pnss% (4.4c lo) ~ -

REV 133 0/12/^^ *

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Table 4.2.1 - Continued Minimum Test and Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation NOTES:

(1) (Deleted)

(2) Calibrate prior to normal shutdown and start-up and thereafter check once per shift and test once per week until no longer required. Calibration of this instrument prior to normal shutdown means adjustment of channel trips so that they correspond, within acceptable range and accuracy, to a simulated signal injected into the instrument (not primary sensor). In addition, IRM gain adjustment will be performed, as necessary, in the APRM/IRM overlap region.

(3) Functional tests, calibrations and sensor checks 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 4

operable status.

(4) Whenever fuel handling is in process, a sensor check shall be performed once per shift.

(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.

(6) (Deleted)

(7) (Deleted)

(8) Once/ shutdown if not tested during previous 3 month period.

(9) Testing of the SRM Not-Full-In rod block is not required if the SRM detectors are secured in the full-in position.

(10) Uses contacts from scram system. Tested and calibrated in accordance with Tables 4.1.1 and 4.1.2.

3.2/4.2 REV 133 8/18/92

Trip Function Deviation Reactor Building Ventilation Isolation and Reactor Building Vent +5 mR/hr Standby Cas Treatment System Initiation Plenum Monitors Specification 3.2.E.3 and Table 3.2.4 Refueling Floor +5 mR/hr Radiation Monitors t -3

% o a sa w4.ow. Reactor Water Level 4 inches l High Drywell Pressure +1 psi Primary Containment Isolation Functions

• Low Low Water Level -3 inches Table 3.2.1 -

High Flow in Main Steam Line +2%

High Temp. in Main Steam +10*F Line Tunnel Low Pressure in Main Steam -10 psi Line High Drywell Pressure +1 psi

• Low Reactor Water Level -6 inches HPCI High Steam Flow +7,500 lb/hr HPCI Steam Line Area High +2*F Temp.

RCIC High Steam Flow +2250 lb/hr RCIC Steam Line Area High Temp +2*F Shutdown Cooling Supply ISO +7 psi 3.2 BASES 70 REV 116 3/3G/5^~

1 a

i l

Exhibit C l

Monticello Nuclear Generating Plant License Amendment Recuest dated March 28, 1994 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:

Pace 59 62 70 l

I l

l l

I i

l

r l - l Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation Isolation And Standby Gas Treatment System Initiation i Min. No. of Operable Total No. of Instru- or Operating Instrument ment Channels Per Trip Channels Per Trip Required Function Trio Settinzs System System (Notes 1. 2) Conditions *

1. Low Low Reactor 26'-6", $6'-10" 2 2 A. or B.

Water Level (Note 3)

2. High Drywell Pres- 52 psig 2 2 A. or B.

sure (Note 3)

3. Reactor Building s100 mR/hr 1 1 (Note 4) A. or B.

Plenum Radiation Monitors

4. Refueling Floor 5100 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 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.

• 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 REV

_ +_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ m - u-_s -___ __m_ _-__ ________________

. Table 4.2.1 Continued Minieum Test and Calibration Frequency For-Core Cooling Rod Block and Isolation Instrumentation - -,*

l Instrument Channel Test (3) . Calibration (3) Sensor Check (3) ,

I

3. Steam Line Low Pressure Once/3 months Once/3 months None Every Operating Cycle-

4. Reactor Low Low Water Level Once/3 months (Note 5) Once/ shift Transmitter Once/3 Months-Trip Unit CONTAINMENT ISOLATION (CROUPS 2 & 3)

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

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

HPCI (GROUP 4) ISOLATION

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

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

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

2. Steam Line High Temperature Once/ month Once/3 months None REACTOR BUILDING VENTILATION & STANDBY GAS TREATMENT

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

2. Drywell High Pressure (Note 10) -

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

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

RECIRCULATION PUMP TR1P AND ALTERNATE ROD INJECTION

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

2. Reactor Low Low Water Level Once/ month'(Note.5) . Once/ Operating Cycle- Once/ shift Transmitter Once/3 Months-Trip Unit ,

SHUTDOWN COOLING SUPPLY ISOIATION

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

-REV 4

, 'e Trio Function Deviation Reactor Building Ventilation Isolation and Reactor Building Vent +5 mR/hr Standby Gas Treatment System Initiation Plenum Monitors Specification 3.2.E.3 and Table 3.2.4 Refueling Floor +5 mR/hr Radiation Monitors

• Low Low Reactor Water Level -3 inches l High Drywell Pressure +1 psi Primary Containment Isolation Functions

• Low Low Water Level -3 inches Table 3.2.1 High Flow in Main Steam Line +2%

High Temp. in Main Steam +10*F Line Tunnel Low Pressure in Main Steam -10 psi Line High Dryvell Pressure +1 psi

• Low Reactor Water Level -6 inches HPCI High Steam Flow +7,500 lb/hr HPCI Steam Line Area High +2*F Temp.

RCIC High Steam Flow +2250 lb/hr RCIC Steam Line Area High Temp +2*F Shutdown Cooling Supply ISO +7 psi 3.2 BASES 70 REV

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