ML20217P841

Rev TS Pages Changing Actions Required Should Channel of Recirculation Actuation Signal (RAS) Be Placed in Tripped Condition,Replacing TS Pages Submitted in 970603 Submittal

ML20217P841
Person / Time
Site:	Waterford
Issue date:	05/01/1998
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20217P833	List: ML20217P830 ML20217P841
References
NUDOCS 9805070108
Download: ML20217P841 (12)

Text

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(No elmn9es tr TABLE 3.3-3 ftentinued) -/-h/ s pap e, f ru,s/ec/

TABLE NOTATION b d du b" "I 9 )

(a)' Trip function may be bypassed in this MODE when pressurizer pressure is less than 400 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 500 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

The provisions of Specification 3.0.4 'are not applicable.

ACTION STATEMENTS ACTION 12 -

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STAND 8Y within the I next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 13 -

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATIpN and/or opera-tion in the other applicable MODE (S) may continue provided the inoperable channel is placed in the bypassed or tripped condition within I hour. If the inoperable channel is bypassed,  !

the desirability of maintaining this channel in the bypassed  !

condition shall be documented by the Plant 0p'erations Review Committee in accordance with plant administrative procedures.

The channel shall be returned to OPERA 8LE status no later than I prior to entry into the applicable MODE (S) following the next COLD SHUTDOWN.

With a channel process measurement circuit that affects multiple l functional units inoperable or-in test, bypass or trip all associated functional units as listed below:

Process Measurement Circuit Functional Unit Bypassed / Tripped ,

1. Containment Pressure - High Containment Pressure - High (ESF; Containment Pressure - High (RPS,

2. Steam Generator. Pressure -

Low Steam Generator Pressure - Low Steam Generator AP 1 and 2 (EFAS; .

3. Steam Generator Level Steam Generator Level - Low Steam Generator Level - High Steam Generator AP (EFAS)

WATERFORD - UNIT 3 3/4 3-17 AMENDMENT NO.109

(Alo c imny es M TABLE 3.3-3 (Continued) N Aer cca k & / d TABLE NOTATION

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ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERA 8LE, STARTUP and/or POWER OPERATION and/or opera-tion in the other applicable MODE (S) may continue provided the following conditions are satisfied:

a. Verify that one of the inoperable channels has been bypassed and place the other innperable channel in the tripped condition within I hour.

b. All functional units affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped condition as listed below.

Process Measurement Circuit Functional Unit 8ypassed/ Tripped

1. Containment Pressure Circuit Containment Pressure - High (ESF)

Containment Pressure - High (RPS)

2. Steam Generator Pressure - Steam Generator Pressure - Low Low Steam Generator Level - High Steam Generator AP (EFAS)

3. Steam Generator Level Steam Generator Level -Low Steam Generator Level - High Steam Generator AP (EFAS)

STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE (S) may continue until the performance of the next required CHANNEL FUNCTIONAL TEST. Subsequent STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE (S) may continue if one channel is restored to OPERA 8LE status and the provisions of ACTION 13 are satisfied.

ACTION 15 - With the number of OPERA 8LE channels one less than the Total Number of Channels, restore the inoperable channels to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HDT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 16 - With the number of OPERA 8LE channels one less than the Total Number of Channels, restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 17 - With the number of OPERA 8LE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the tripped (D.C.

Relay energized) condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the remaining Emergency Diesel Generator is OPERABLE, and the inoperable .

channel is restored to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Otherwise, be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ~

and COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The surveillance requirements of Table 4.3-2 are waived for all channels while this action requirement is in effect.

WATERFORD - UNIT 3 3/4 3-18 Amendment No. 47

TABLE 3.3-3 (Continued)

TABLE NOTATION ACTION 18 - With more than one channel inoperable, or if the inoperable channel cannot be placed in the trip (D.C. Relay energized) ,

condition, declare the associated Emergency Diesel Generator .

inoperable and take the ACTION required by Specification 3.8.1.1. l The surveillance requirements of Table 4.3-2 are waived for all channels while tr.is action requirement is in effect.

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WAT N ORD - UNIT 3 3/4 3-1Sa W No. 47

e 3/4.3 INSTRUMENTATION BASES l

3/4.3.1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES _

ACTUATION SY!* EMS INSTRUMENTATION I

The OPERABILITY of the Reactor Protective and Engineered Safety Features Actuation Systems instrumentation and bypasses ensures that (1) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter monitored by each channei or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintai'ned to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.

The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.

The redundancy design of the Control Element Assembly calculators (CEAC) provides reactor protection in the event one or both CEACs become inoperable.

If one CEAC is in' test or inoperable, verification of CEA position is performed at least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If the second CEAC fails, the CPCs will use DNBR and LPD penalty factors to restrict reactor operation to some maximum fraction of RATED THERMAL POWER. If this maximum fraction is exceeded, a reactor trip will occur.

The Surveillance Requirements specified for these systems ensure thit the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests pt . formed at the :ninimum frequencies are sufficient to demonstrate this capabi4ity. The quarterly fre-quency for the channel functional tests for these systems comes from the analyses presented in topical report CEN-327: RPS/ESFAS Extended Test Interval Evaluation, as supplemented.

RPS\ESFAS Trip Setpoints values are determined by means of an explicit setpoint calculation analysis. A Total Loop Uncertainty (TLU) is calculated for eacn RPS/ESFAS instrument channel. The Trip Setpoint is then determined by adding or scbtracting the TLU from the Analytical Limit (add TLU for decreasing process value; subtract TLU for increasing process value). The l I

Allowable Value is determined by adding an allowance between the Trip Setpoint and the Ar.alytical Limit to account for RPS/ESFAS cabinet Periodic Test Errors i FTE) which are present during a CHANNEL FUNCTIONAL TEST. PTE combines the l RPS/ESFAS cabinet reference accuracy, calibration equipment errors (M&TE), and RPS/ESFAS cabinet bistable Drift. Periodic testing assures that actual setpoints are within their Allowable Values. A channel is inoperable if its actual setpoint is not within its Allowable Value and corrective action must be taken. Operation with a trip set less conservative than its setpoint, but witMn its specified ALLOWABLE VALUE is acceptable on the basis that the difference between each trip Setpoint and the ALLOWABLE VALUE is equal to or

) less than the Periodic Test Error allowance assumed for each trip in the safety analyses.

WATERFORD - UNIT 3 B 3/4 3-1 Amendment No. 69,11

( Al )c el<anyeS ea 3/4.3 INSTRUMENTATION Nv 5 p o p e , p ro v/ded f er c u A % g// 9)

BASES (Cont'd) {

3/4.3.1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION The measurement of respense time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the safety analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either (1) in place, onsite, or offsite test measurements or (2) utilizing replacement sensors with certified response times.

WATERFORD - UNIT 3 B 3/4 3-la Amendment No.113

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ACTION 18 - With more than one channel inoperable, or if the inoperable channel cannot be placed in the trip (D.C. Relay energized) condition, declare the associated Emergency Diesel Generator inoperable and take the ACTION required by Specification 3.8.1.1.

The surveillance requirements of Table 4.3-2 are waivod for all channels while this action requirement is in effect.

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W TERFORD - UNIT 3 3/4 3-18a Amendeont No.47

INSERT 1 ACTlON 19 - With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE (S) may continue, provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour: I

a. If the inoperable channel is to remain in the bypassed condition, the desirability of maintaining this channelin the bypassed condition shall be documented by the Plant Operations Review Committee in accordance with plant administrative procedures. The channel shall be returned to OPERABLE status no later than prior to enny into the applicable MODE (S) following the next COLD SHUTDOWN.

b. If the inoperable channel is required to be placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either restore the channel to OPERABLE status or place the channel in the bypassed condition. If the tripped channe! can not be returned to OPERABLE status in 48 nours, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> or place the tripped channelin bypass.

ACTION 20 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE (S) may continue provided the following conditions are satisfied:

a. Verify that one of the inoperable channels has been bypassed and place the other inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. Restore at least one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Subsequent operation in the applicable MODE (S) may continue if one channel is restored to OPERABLE status and the provisions of ACTION 19 are satisfied.

M4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION The OPERABILITY of the Reactor Protective and Engineered Safety Features i nuation Systems instrumentation and bypasses ensures that (1) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out of service for testirg or maintenance, and (4) sufficient sys, tem functional I 1

capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.

The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.

The redundancy cesign of the Control Element Assembly Calculators (CEAC) provides reactor protection in the event one or both CEACs become inoperable.

If one CEAC is in test or inoperable, verification of CEA position is performed at least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If the second CEAC fails, the CPCs will use DNBR and LPD penalty factors to restrict reactor operation to some maximum fraction of RATED THERMAL POWER. If this maximum fraction is exceeded, a reactor trip will occur. _ ggg The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed.at the minimum frequencies are sufficient to demonstrate this capability. The quarterly fre-quency for the channel functional tests for these systems comes from the i

(

analyses presented in topical report CEN-327: RPS/ESFAS Extended Test Interval Evaluation, as supplemented.

RPS\ESFAS Trip Setpoints values are determined by means of an explicit setpoint calc,slation analysis. A Total Loop Uncertainty (TLU) is calculated for each RPS/ESFAS instrument channel. The Trip Setpoint is then determined by adding or subtracting the TLU from the Analytical Limit (add TLU for decreasing process valuc; subtract TLU for increasing process value). The Allowable Value is determined by adding an allowance between the Trip Setpoint and the Analytical Limit to account for RPS/ESFAS cabinet Periodic Test Errors (FTE) which are present during a CHANNEL FUNCTIONAL TEST. PTE combines the RPS/ESFAS cabinet reference accuracy, calibration equipment errors (M&TE), and RPS/ESFAS cabinet histable Drift. Periodic testing assures that actual l setpoints are within their Allowable Values. . A channel is inoperable if its actual setpoint is not within its Allowable Value and corrective action must be taken. Operation with a trip set less conservative than its setpoint, but within its specified ALLOWABLE VALUE is acceptable on the basis that the difference between each trip Setpoint and the ALLOWABLE VALUE is equal to or less than the Periodic Test Error allowance assumed for each trip in the safety analyses.

WATERFORD - UNIT 3 B 3/4 3-1 Amendment No. 69,113 J

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INSERT 2

. o Table 3.3-3 ACTION 19 allows for continued operation in the applicable MODE (S) with one of the Refueling Water Storage Pool (RWSP) Low channels inopenble provided the channelis placed in the bypass or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If an inoperable channel of the RWSP - Low is required to be placed in the tripped condition within one hour, then within 48  :

hours the channel must either be restored to OPERABLE status or be placed in the bypassed condition. The bypassed channel must be restored to OPERABLE status prior to entering MODE 4 following the next MODE 5 entry. With one of the RWSP- Low channels inoperable and in bypass, and testing or repairs is necessary on one of the remaining channels, ACTION 20 must l be entered.

ACTION 19a is annotated with an askerisk for the 3.0A . emption to allow the changing j of MODES even though one channelis bypassed. MODE changes between MODES 1 and 4 with this configuration are allowed, to permit maintenance and testing on the inoperable channel.

In this configuration, the protection system is in a two-out-of-three logic, and the probability of a random failure affecting two of the OPERABLE channels is remote. The tripped condition does not have this annotation as a single f ailure could cause the Emergency Core Cooling System and Containment Spray System suctions to be supplied from the Safety injection System Sump prematurely and loss of the Low Pressure Safety injection Systems.

Table 3.3-3 ACTION 20 allows for continued operation in the applicable MODE (S) with two of the RWSP - Low channels inoperable providea that one of the inoperable channels is bypassed and the other inoperable channel is placed in the tripped condition within cre hour.

One of the inoperable RWSP - Low channels must be restored to OPERAELE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to allow removal of th3 channel from the tripped condition. The allowea time is j acceptable because operating experience has demonstrated the low probability of the following l sequence of events occurring: the need to place one RWSP - Low channel in the tripped I condition while another RWSP - Low channel is in bypass, the receipt of a valid Safety injection i Actuation Signal Actuation, and a coincident failure of one of the two remaining OPERABLE l RWSP - Low channels. These conditions could cause the Emergency Core Cooling System and l Containment Spray System suctions to be supplied from the Safety injection System Sump i prematurely due to containment pressure taing higher than RWSP outlet pressure and loss of I the Low Pressure Safety injection Systems.

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When one of the inoperable channels is restored to OPERABLE status, subsequent operation in the applicable MODE (S) may continue in accordance with the provisions of ACTION 19.

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