Text

Proposed Changes to Tech Spec 3/4.3.1 Re Reactor Trip Sys Instrumentation Per Generic Ltr 85-09
	ML20235A553
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Site:	Wolf Creek
Issue date:	06/29/1987
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
To:	;
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ML20235A512	List: ML20235A510; ML20235A553;
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	GL-85-09, GL-85-9, NUDOCS 8707080471
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O ATT10MD'r 'III PROPOSED TEDINICAL SPfrIFICATION QUJK;E 1

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l G707080471 870629 PDR ADOCK 05000482 P

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1 Attachment III to WM 87-0177 Page 1 of 13 June 29,1987 3 '*. 3 INSTRUMENTATION 2 /4. 3. 2 REACTOR TRIP SYSTEM INSTRUMENTATION L!!'! TING C3NDIT 0N FOR OPEilATION l

3 3. 3..' As a minimum, the R actor Trip System instrumentation channels and

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interlo:1.s of Tabie 3.3-1 snail be OPERABLE with RESPONSE TIMES as shown in Tanle 3.3-2.

A DDL ::AE.I L:TY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

]URVE1LL A14CE RE0'JIREMENT5

4. 3. :.1 Each Reactor Trip System instrumentation cnannel anc interlock and the automatic trip logic shall be demonstrated GPERABLE by tr.e performance of the Reactor Trip System Instrumentation Surveillance Reovirements specified Taole 4.3-1.

in 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSI. TIME of eacn. Reactor trip function 1

~ hall be cemonstrated-to.be within its limit at.least once.per 19 tenths.

s

'Each test shall include at least one train such that both trains are tested at leiast once per 36 months and ont channel per function such that all Channels are tested at least once every N times 18 months where N is the total number of redun:: ant channels in a specific Reactor trip f unction as shown in the

" Total No. of Channels" column of Table 3.3-1.

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A'ttachment III to WM 87-0177 Page 5 of 13 June 29.1987 TABLE 3.3-1 (Continued)

TABLE NOTATIONS

'Only if the Reactor Trip System breakers haopen to be in the closed position and ne Control Roc Drive System is capable of rod vithdrawal.

- The boron dilution flux doubling signal may be blocked during reactor startuo in accordance with normal operating procedures.

FThe orovisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

772Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setooint.

ACTION STATEMENTS ACTION 1 - 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 HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the numoer of OPERABLE channels one less than the Total

. Number of. Channels. STARTUP and/or POWER OPERATION may oroceec crovided the following. conditions are. satisfied:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for uo to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per.5pecif.ication 4.3.1.1: and c.

Either. ~ THERMAL POWER.is restricted.to less than or ecual to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trio Setooint is reduced to less than or ecual to 85% of RATED THERMAL POWER within 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s: or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

ACTION 3.With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

l Below the P-6 (Intermediate Range Neutron Flux Interlock) a.

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setooint; or b.

Above the P-6 (Intermediate Range Neutron flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER. restore the inoperable channel to OPERABLE status orier to increasing l

THERMAL POWER above 10% of RATED THERMAL POWER.

w ACTION

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

~

Channels OPERABLE recuirement susoend all operations involving positive reactivity changes.

WOLF CREE F-UNIT 1 3/4 3-5

.s ;

1

-Attachment III to WM 87-0177 Page 6 of 13' June ~29,1987 TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued).

ACTION 5 With the number of OPERABLE channels one less than the Mini-a.

mum Channels OPERABLE requirement, restore the inoperaole channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reac-tor Trip Breakers, suspend all ooerations involving positive q

reactivity changes and verify valves BG-V178 and BC-V601 are closed and secured in position within the next hour, b.

With no channels OPERABLE, coen the Reactor Trip Breakers.

j suspend all operations involving positive reactivity changes and verify compliance with the SHUTDOWN MARGIN recuirements j

of Specification 3.1.1.1 or 3.1.1.2, as acplicable, within

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1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter, and verify valves

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BG-V178 and BG-V601 are closed and secured in oosition within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verified to be closed and secured in position every 14 days.

I ACTION 6 With the number of OPERABLE channels one less than the Total Number of Channels. STARTUP and/or POWER OPERATION may proceed j

provided the following conditions are satisfied:

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The. inoperable channel is placed in 'the tripoed coneit1:n

.a.

within 1 hour: and b.

The Minimum Channels OPERABLE requirement is met: however.

I the inoperable channel may be bypassed for uo to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels cer Speci fication 4. 3.1.1.

I ACTION.7 - With the numberrof OPERABLE chan"els one less-than the Total Numcer of Channels, STARTUP and/or POWER OPERATION may oroceec until performance of the next required ANALOG CHANNEL OPERATICNAL TEST provided the inoperable channel is placed in the trictec condition within I hour.

ACTION 8 With less than the Minimum Number of Channels OPERABLE. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine b., observation of the, associated permissive annunciator window (s) that the interlock is in its recuired state for the existing plant condition, or apply Specification 3.0.3.

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT $TANDSY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassec for uo to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification.:.3.1.1.

provided the other channel is OPERABLE.

ACTION.10 - With the number of GPERABLE channels one less than tne Mini.um Channels OPERABLE reouirement. restore the inceeratie :nserei to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or ooen the Reactor tr1:

breakers within the next hour.

m ACTICM

'.1 - With thebtamber of CPERABLE channels less than :ne Total Nu of C'hannels, operation may contine crovided the incre acie cnannels are placed in the tripped condition witnin 1 tour.

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i A,ttachment III to WM 87-0177 Page 12 of 13 June 29, 1987 2

TABLE 4.3-1 (Continued)

TABLE NOTATIONS

Only if the Reactor Trip System breakers happen to be closed and the control rod drive system is capable of rod withdrawal.

1. Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)

If not performed in previous 7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric I

power if absolute difference is greater than 21 The provisions of speci-fication 4.0.4 are not applicable for entry into MODE 2 or 1.

(3)

Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15%

of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3L The provisions of Specification 4.0.4 are not applic-able for entry into MODE 2 or-1.

(4) Neutron cetectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained, evaluated and comparec to manu-facturer's data.

For..the Intermediate Range and Power Range. Neutron Flu channels the provisions of Specification 4.0.4 are not applicaole for entry into MODE 2 or 1.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The nrovi-sions of Specification 4.0.4 are not applicable for entry into MCCE 2 or 1.

(7)

Each train shall be tested at least every 62 days on a STAGGERED TE5T BASIS.

(8)

With. power greater than or equal to the inter.leck Setroint the recuireo ANALOG CHANNEL' OPERATIONAL TEST shall consist of verifying tna. t a inter-lock is in the required state by observing the permissive annunciater window.

(9)

Monthly surveillance in MODES 3", 4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant -

conditions by observation of the permissive annunciator window.

Monthly surveillance shall include verification of the Boron Oilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute pe'riod.

(10) Setpoint verification is not required.

(11)

^.t ' : x t c n c e p e r --13 = n t h: cnd fe!!c. 4 g =intenance er ad55 em :' "

cxt-t-ipbreakers,AheTRIPACTUATINGDEVICEOPERATIONALTESTshp i nc!ude 4dependent ver 'icaticr cf the Ur.dcrvc',t;;c cr.d Shu.

4 (12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Doubling test signal the normal CVCS discharge val <es -ill close, and the centrifugal charging pumps suction valves from the L5T will open within 30 seconds.

% NEL CALIBRATION shall Insert C" include the RTD bypass loops flow rate.

~

+c

.o WOLT CREEK - U5IT 1 3/4 3-12

.v

o Attachment III to WM 87-0177 Page 13 of 13 June 29,1987 Insert A Action 12 - With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 9.

The breaker shall not be bypassed while one of the

)

diverse trip features is inoperable except-for the time required for performing maintenance to restore the breaker

^

OPERABLE status.

Insert B independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Punction.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

Insert C (14) - The TRIP ACTUATING DEVICE OPERATIONAL. TEST ' shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(15) - Local manual shunt trip prior to placing breaker in service.

(16) - Automatic undervoltage trip.

1 l

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ML20235A553

Text

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