ML20203A977

Proposed Tech Specs Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer

ML20203A977
Person / Time
Site:	Monticello
Issue date:	11/25/1997
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20203A940	List: ML20203A933 ML20203A953 ML20203A977
References
NUDOCS 9712120282
Download: ML20203A977 (8)

Text

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l Exhibit B Monticello Nuclear Generating Plant License Amendment Request Dated November 25,1997 Technical Specification Pages Marked Up With Proposed Working Changes Exhibit B consists of the existing Technical Specification pages marked up with the proposed changes. Existing pages affected by this change are listed below:

Pages Sb 60d 71a d

4 4

B1 9712120292 971125 3 DR ADOCK O

AQ. Core Operatina 1.fmtrs Report The. Core Operating 1.iraits Report is the unit specific docurnent-that provides

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core operating liraits for ,the. current operating reload cycle. These cycle necific operating limits shall be

- detersnined for each reload cycle in accordance with Specification 6.7.A.7. riant operation within'these operating lisaits is~ addressed in individual specifications.

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A11DWdblR._Value The Allowable Value is the limiting value of the sensed process variable at tf.nich the trip setpoint-may be found~during instrument surveillance.

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Table 3.2.8 Other Ins t.t ument a ti on . ,

flinimura lio, of flininnum flo. of Oper-Operable or Total llo. of Instru- able or Operating Required Function Trip Setting Operating Trip ment Channels Per Instruinent Charmels Conditions

• S y s t ern (1) lilo System Per Trio System (1)

A. RCIC Initiation

1. l.ou - l.ow Reactor I.evel 26'6"6 56'10" 1 2 2 n above top of active fuel 11 . IIPCI/RCIC Turhine Shutdown

a. liigh Iteactor I.evel 514'6" above 1 2 2 A top of active fuel C. IIPCI/RCIC Tuthine Suction Transfer ar-Gemienen ee-S L,i ar,c - W ft" above- 1 2 2 C Tanb4m-L- . e l p-et+ ssg' 'h e -- "

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60 pst Discharge Pipe Pressure 110 psid Inhibit Timer Inhibit -3 sec

<10 sec Other Instrumentation *lligh Heactor Water Level +6 inches

• lew-Low Reactor Water Level -3 inches

- t a, - C.,nd c n - t e S ta agc Lcvc1 5 inche

• This indication is reactor coolant temperature sensitive. The calibration is thus inade for rated conditions. The level error at low pressures and temperatures is bounded by the safety analysis uhich reflects the weight-of-coolant above the lower tap, amt not the indicated level.

A violation of this specification is assumed to occur only when a device is knowingly set outside of the limiting trip settings, or, when a sufficient number of devices have been affected by any means such that ths automatic function is incapable of operating within the allowable deviation while in a reactor mode in which the specified function must be operable or when actions specified are not initiated as specified.

3. 2 11AS ES Ila

Exhibit C Monticello Nuclear Generating Plant License Amendment Request Dated November 25,1997 Revised Technical Specification Pages Exhib t C consists of revised Technical Specification pages that incorporate the proposed changes. The pages included in the exhibit are as ii.'ed below:

. Pages 5b '

60d 71a E

C-1

AQ. Core coeratina Limits The Core Operating Limits Report is the unit' specific document.that provides core operating.

limits for the current operating reload cycle. These cycle-specific' operating limits shall be determined for eads reload cycle'in accordance with Specification 6.7.A.7. . Plant operation'within these operating limits is addressed in individual specifications.

AR. Allowable Value- The Allowable value.is the limiting value of the sensed process variable at which the trip setpoint may be found during instrument surveillance.

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1.0 Sb-y- .gi>+ ^-y=.r .a - e .p ....r

l Table 3.2.8 -

Other Instrumentation .

Minimum No. of Minimum No. of Oper-Ope % 1e or Total No. of Instru- able or Operating Required Function Trip Setting Operating Trio ment Channels Per Instrument Channels Conditions

• System (1) Trip System Per Trip System (1)

A. RCIC Initiation

1. Low-Low Reactor Level 26'6*& 56*10* 1 2 2 B above top of active fuel B. HPCI/RCIC Turbine Shutdown

a. High Reactor Level 514'6" above 1 2 2 A top of active fuel C. HPCI/RCIC Turbine Suction Transfer

a. Condensate Storage 22'3" above 1 2 2 C Tank Low Level tank bottom Allowable Values (Two Tank Operation) 26'9" above 1 2 2 C tank bottom (One Tank Operation)

UQIE:

1. Upon discovery that minimum requirements for the number of ope able or operating trip systems or instrument channels are not Satisfied, action shall be initiated to:

a. Satisfy the requirements by placing the appropriate channels or systems in the tripped condition Turbine /Feedwater Trip only), or

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

Required conditions when minimum conditions for operation are not satisfied:

A. Reactor in Startup, Refuel, or Shutdown Mode.

B. Comply with Specification 3.5.D.

C. Align HPCI and RCIC suction to the suppression pool.

3.2/4.2 60d

b Trip Function Deviation'-

- Instrumentation for Safety / Relief Valve Reactor Coolant System 120 psig

- Low Low. Set Logic' Pressure for Opening / Closing Opening-Closing Pressure 260 psi Discharge Pipe Pressure ilO psid Inhibit Timer Inhibit -3 sec

+10 see Other Instrumentation *High Reactor Water Level +6 inches

• Low-Low ' Reactor Water Level -3 inches 4

• This indication is reactor coolant temperature sensitive. The calibration is'thus made for rated conditions. The level error at low pressures and temperatures is bounded by the safety analysis which reflects the weight-of-coolant above the lower tap, and not the indicated level.

A violation of this specification is assumed to occur only when a device is knowingly set outside of'the limiting trip settings, or, when a sufficient number of devices have been affected by any means such that the automatic function is incapable of operating within the allowable deviation while in a reactor mode in which the specified function must be operable or when actions specified are not' initiated as specified.

3.2 BASES 71a L

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