ML20236X561

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Proposed Tech Specs,Changing Source & Intermediate Range Monitors Loss of Negative Voltage indications,post-accident Monitoring Instrumentation & Main Steam Line high-flow Isolation Setpoint
ML20236X561
Person / Time
Site: Cooper Entergy icon.png
Issue date: 12/01/1987
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20236X525 List:
References
NUDOCS 8712090285
Download: ML20236X561 (4)


Text

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y NOTESiFOR'TABLEF3.2.A-  :

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.h"['!'$1hIWheneverjPrialarf Containment integrityJis required there shall: bel two' l' Voperable7 or; tripped trip. systems-forneach function. M p

i 2.- If the minimum, number'offo,erable b instrument ~channelsDper trip, system

, requirementicannot be' met by a trip. system, that trip system shall be

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!trippe'd'.:'If'thefrequirements cannot'be m'et by both trip systems, .the"

,l appropriate. action listed below shall be taken.-

'A.L .In'1hiate-aniorderly:shutdownLand'have the reactor'in a cold shutdown " 6 3 condition in 24: hours.

B. . Initiate an orderly load reduction and have the Main' Steam Isolation-

- Valves shut within-8 hours;

.C2 . Isolate the' R'eactor' Water. ' Cleanup. S'ystem. ,

D. IsolatetheShutdownCooling]ystem. ,

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, , ' 3. : Two required lfor each steam line.

' 5 4 .~ These. signals also start the: Standby Gas Treatment Sy. stem and' initiate

" . Secondary Containment isolation .

Not' required'in the refuel, shutdown,.and-startup/ hot standby modes _

5.

(interlocked:with.the1 mode switch).

[6. ' Requires oneichannel from each physical location for each trip system.

7. . Low vacuum isolation.is bypassed when the turbine stop.is not full open, manual' bypass switches..are.in bypass'and mode: switch is not in RUN.
8. The' instruments on this. cable produce: primary containment and system isolations. .The following listing groups the system signals and the system isolated.

Group'1 Isolation Signals: ,

1. Reactor Low Low Low Water-Level (>-145.5 in.) -
2. Main Steam Line High Radiation (3 times full power background)
3.  : Main Steam Line Low Pressure (>825 psig in the RUN mode) 4.- Main Steam Line Leak Detection (<200'F)
5. Condenser Low Vacuum (>7" Hg vacuum) I
6. Main ~ Steam Line High Flow ($150% of rated flow) 1 Iso 1'ations :  ;

-1. MSIV's

2. Main Steam.Line Drains L

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(WOTES'FOR TABLE 3.2.C

.. 9 . - { 1. For the startup.and run positions' of'the. Reactor Mode Selector Switch, the

- Controi Pod Withdrawal'Blo'ck Instrumentation trip system shall-be-operable

- for'each function. The'SRM and'IRM blocks need not-be operable in "Run" mode., and the LAPRM (flow biased);and RBM rod blocks need not be operable 'in

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'.'S t art up n.od e .' The Control Rod Withdrawal Block Insert (entation trip  ;

system <is a one outz of "n" trip system, andias such requires that only.~one

' instrument' channel specified in the function' column must exceed-the Trip Level Setting.co cause a rod block. By utilizing the'RPS bypass logic-(see

- note' 5 below and note 1 of Table 3.1.1) ' for, the Control Rod Withdrawal' Block Instrumentation, a sufficient number of instrument channels will' always;be operable.to provide' redundant rod withdrawal block protection.

2; W is the,two-loop recirculation flow. rate in percent'of rated. Trip level setting is-in: percent of rated power (2381 MWt). N is the RBM setpoint' '

selected (in' percent) and is' calculated in accordance with the' methodology s

- of the. latest NRC approved version of NEDE-24011-P-A.,

3. IRM downscale it, bypassed when it is on its lowest range.

'4. This fur, tion is bypassed when the count is > 100 cps and IRM above range 2.

~ 5. By design one instrument channel; i.e., one APRM or IRM per RPS trip. system-may be bypassed. .For the.APRM's and IBM's, the minimum number of channels specified is..that, minimum number required in each RPS channel and_does not refer to a' minimum number required by'the control rod block instrumentation trip. function. By, design only one of two RBM's or one of four 3RM's may be bypassed. :For the SRM's, the minimum number of channels specified is the

- minimum number required in each of the twa circuit. loops of the Control Rod

' Block Instrumentation Trip System. For the'RBM's,'the minimum' number ofL channels specified is the minimum' number required by the Control Rod Block

- Instrumentation. Trip System as a whole (except when a limiting control rod pattern exists and the requirements of Specification 3.3.B.5 apply).

6 '. IRM channels A.E C G all in range'8 or higher bypasses SRM channels A6C functions.

IRM channels B F,D H all in range 8 or higher bypasses SRM channels B&D functions.

This function is bypassed when IRM is above range 2. 'I 7.

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8. This function is bypassed uhen the mode switch is placed in Run.
9. This function is only active when the mode switch is in Run.
10. The inoperative trips are produced by the following functions:
a. SRM and IRM 1 (1) Mode switch not in operate (2) Power supply voltage low (3) Circuit boards not in circuit

'(4) Loss of' negative Supply voltage l l\

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( f y'yN f': I-[. / A;;. iWith the : number' of operable ' acanonents less than7 required by thel minimum.

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component-Loperable}requiremex.s,: initiate the. preplanned--alternate method-

-of monitoringDthel appropriate parameter (s);within.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

p. , i k-( / , i pf , ;l)j ,either restore:therinoperable component (s)~.to operable status within' 7_. days of.ethe event,,or
2) prepare andLsubmit-a-Special Report to the.. Commission'withinh14 daysD 3.,

following the event outlining theJaction taken. the'cause of;the.

inoperability and thelplans.and schedule for restoring the'~ system to-operable status.

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1. These instrumentsDare! required to be operable at'all times except when the.

reactor is in cold shutdown or. in the ' REFUEL mode ..during', a refueling (outage.

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