ML20247J811

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Proposed Tech Specs Re Elimination of Cycle Specific Parameter Limits
ML20247J811
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 05/24/1989
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20247J801 List:
References
TAC-66153, TAC-66154, NUDOCS 8906010136
Download: ML20247J811 (6)


Text

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j ENCLOSURE 3 i

l BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS, 50-325 & 50-324/ LICENSE NOS, DPR-71 & DPR-62 ELIMINATION OF CYCLE SPECIFIC PARAMETER LIMITS UPDATED TECHNICAL SPECIFICATION PACES (NRC TAC NOS. 66153 AND 66154)

UNIT 1 TECHNICAL SPECIFICATION PAGES I

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060 f

,, hah 4

P

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D INDEX.

SAFETY LIMITS ' AND IIMIT fNC SAFETY SYSTEM SETTINGS 4

SECTION PACE 2.1 SAFETY LIMITS Thermal Power (Le r Pre s sure or Low F1ow).........................

2-l '

i Thermal Power (Hith Pressure and High Flow).............

2-1 3

Reactor Coolant System Pressure..................................

2-1 Reactor' Vessel Water Leve1.......................................

2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System. Instrumentation Setpoints..............

2-3 BASES 2.1 SAFETY LIMITS Thermal Powe r (Low Pres sure or Low F1ow).......................... B 2-1

' Thermal Power (High Pressure and High F1ow)....................... B 2-2 deactor Coolant System Pressure................................... B 2-3 Reactor Vessel Water Leve1........................................ B 2-3 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints............... B 2-4 l

. BRUNSWICK - UNIT 1 III Amendment No.

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,3 l

1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

,a 7

SECTION

.PAGE

' 3 / 4. 0 APPLI CAB I LI TY................................................. 3 / 4 0-1 3/411 REACTIVITY CONTROL SYSTEMS s

3/4.1.1. SHUTDOWN MARCIN.......................................'..... 3/4 1-1

- 3 /4.1'.2 REACTIVITY AN0HALIES....................................... 3/4 1-2 3/4.1.3 CONTROL RODS-Control Rod Operability.................................... 3/4 1-3 Control Rod'Haximum Scram Insertion Times.................. 3/4'1-5 Control Rod Average Scram Insertion Times.................. 3/4 1-6 Four Control R)d Group Scram Insertion Times..............

3/4 1-7 Control' Rod Scram Accumulators............................. 3/4 1 Control Rod Drive Coupling................................. 3/4 1-9

-Control. Rod' Position Indication............................ 3/4 1-11.

Control Rod Drive Housing Support.......................... 3/4 1 13 l

-3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer........................................ 3/4-1-14 f

Rod Sequence Control System................................ 3/4'1-15 t

Rod Block Monitor.......................................... 3/4 1-17 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM.............................. 3/4 1-18 3/4.2 POWER DISTRIBUTION LIMITS

't 3/4.2.1.'AVERACE PLANAR LINEAR HEAT CENERATION RATE................. 3/4 2-1 3/4.2.2 APRM SETP0INTS............................................. 3/4 2-2 3/4.2.3 MINIMUM CRITICAL-POWER RAT10............................... 3/4 2-3 l.

i BRUNSWICK - UNIT 1 IV Amendment No.

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INSTRUMENTATION 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4 The control rod withdrawal block instrumentation shown in Table 3.3.4-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4-2.

APPLICABILITY: As shown in Table 3.3.4-1.

ACTION:

With a control rod withdrawal block instrumentation channel trip a.

setpoint less conservative than the value shown in the Allowable values column of Table 3.3.4-2, declare the channel inoperable until the channel is restored to OPERABLE status with its Trip Setpoint adjusted consistent with the Trip Setpoint value.

b.

With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, POWER OPERATION may continue provided that either:

1.

The inoperable channel (s) is restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 2.

The redundant trip system is demonstrated OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the inoperable channel is restored to OPERABLE status, and the inoperable channel is restored to GP?.RABLE status within 7 days, or 3.

For the Rod Block Monitor only, THERMAL POWER is limited such that MCPR will remain abcve the Safety Limit MCPR of Specification 2.1.2, assuming a single error that results in complete withdrawal of any single control rod that is capable of withdrawal.

4.

Otherwise, place at least one trip system in the tripped condition within the next hour.

c.

With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one trip system in the tripped condition within one hour.

d.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

{

SURVEILLANCE REQUIREMENTS 4.3.4 Each of the above required control rod withdrawal block instrumentation channels shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK, CHANNEL CALInitATION, and a CHANNEL FUNCTIONAL TEST. during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.4-1.,

BRUNSWICK - UNIT 1 3/4 3-47 Amendment No.

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j 1

ENCIDSURE 4 I

BRUNSWICK STEAM ELECTRIC' PLANT, UNITS 1 AND 2

)

DOCKET NOS. 50-325 6 50-324/ LICENSE NOS. DPR-71 & DPR-62

)

ELIMINATION OF CYCLE SPECIFIC PARAMETER LIMITS UPDATED TECHNICAL SPECIFICATION PAGES (NRC TAC NOS. 66153 AND 66154) 1 UNIT 2 TECHNICAL SPECIFICATION PAGES l

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_s:L.

i INSTRUMENTATION 3/4.3.4 CONTROL ROD WITHDRAWeb BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4 The control rod withdrawal block instrumentation shown in Table 3.3.4-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4-2.

APPLICABILITY: As shown in Table 3.3.4-1.

ACTION:

)

With a control rod withdrawal block instrumentation channel trip a.

setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4-2, declare the channel inoperable until the channel is restored to OPERABLE status with its Trip Setpoint adjusted consistent with the Trip Setpoint value.

b.

With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, POWER OPERATION may continue provided that either:

1.

The inoperable channel (s) is restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 2.

The redundant trip system is demonstrated OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the inoperable channel is restored to OPERABLE status, and the inoperable channel is restored to OPERABLE status within 7 days, or 3.

For the Rod Block Monitor only, THERMAL POWER is limited such that the MCPR will remain above the Safety Limit MCPR of 1

Specification 2.1.2, assuming a single error that results in complete withdrawal of any single control rod that is capable of withdrawal.

4.

Otherwise, place at least one trip system in the tripped condition within the next hour.

c.

With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one trip system in the tripped condition within one hour.

d.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

SURVEILLANCE REQUIREMENTS 4.3.4 Each of the above required control rod withdrawal block instrumentation channels shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK, CHANNEL CALIBRATION, and a CHANNEL FUNCTIONAL TEST during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.4-1.

BRUNSWICK - UNIT'2 3/4 3-47 Amendment No.

.