ML20063L682

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Proposed Tech Specs Changing 3.8.1.1 & 3.8.1.2,AC Sources Operating & Shutdown by Revising Min Vol of Fuel Oil Specified for Emergency Day Tanks
ML20063L682
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 02/23/1994
From:
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20063L680 List:
References
NUDOCS 9403070290
Download: ML20063L682 (7)


Text

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Attachment IV to NA 94-0006

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ATTACHMENT IV PROPOSED TECHNICAL SPECIFICATION CHANGE l

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Attachment IV to NA 94-0006

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'3/4 8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES -

i QPERATING LIMITING CONDITION FOR OPERATION 3.8.11 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System, and
b. Two separate and independent diesel generators, each with' Si
1) A separate day tank containing a minimum volume of allons of fuel,
2) A separate fuel Oil Storage System containing a minimum volume of 85,300 gallons of fuel, and
3) A separate fueltransfer pump.

6PPLICABillTY: MODES 1,2, 3, and 4.

ACTION:

a. With an offsite circuit of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining off-site A C. source by performing Specification 4.8.1.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If either diesel generator of the above required A.C. electrical power sources has not been successfully tested within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, demonstrate OPERABILITY by performing Specification 4.8.1.1.2a.4* separately for that diesel generator within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-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 />.

b.

With one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the offsite A.C.

l sources by performing Specification 4.8.1.1.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at i

least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Specifica-tion 4.8.1.1.2a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> **; restore the inoperable diesel generator to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-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 fol-lowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

  • The automatic start and sequence loading of a diesel generator satisfies the testing requirements of Specification 4.8.1.1.2a.4 for this Action Statement.

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    • This test is required to be completed regardless of when the inoperable diesel generetor is restored to OPERABLE status unless the diesel was declared inorarable to do preplanned preventative maintenance, testing, or maintenance l

to correct a condition which, if left uncorrected, would not affect the operability of the diesel generator, j

WOLF CREEK - UNIT 1 3/4 8-1 Amendment No. 8 l

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l Attachment IV to NA 94-0006 Page 3 of 7 ELECTRICAL POWER SYSTEMS A.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. One circuit between the offsite transmission network and the Onsite Class 1E Distribution System, and
b. One diesel generator with:

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1) A day tank containing a minimum volume o allons of fuel,
2) A fuel storage system containing a minimum volume of 85,300 gallons of fuel, and
3) A fueltransfer pump.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactiv-ity changes, movement of irradiated fuel, or crane operation with loads over the spent fuel pool. In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, immediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the requirements of Specifications 4.8.1.1.1,4.8.1.1.2 (except for Specification 4.8.1.1.2a.5)), and 4.8.1.1.3.

1 WOLF CREEK - UNIT 1 3/4 8-8 Amendment No. 8 1

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Attachment IV to NA 9.4-0006 Page 4 of 7

' REACTIVITY CONTROL SYSTEMS -

CIIARGING PUMPS - OPERAllNG LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two centnfugal charging pumps shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.*

ACTION:

With only one centrifugal charging pump OPERABLE, restore at least two cen-trifugal charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at leas %

1.3 %Ak/k at 200*F within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s: restore at least two charging pumps to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

4 SURVEILLANCE REQUIREMENTS 4.1.2.4 At least two centnfugal charging pumps shall be demonstrated OPERABLE by verifying, on recirculation flow, that the pump develops a differential pressure of greater than or equal to 2400 psid when tested pursuant to Specification 4.0.5.

  • The provisions of Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 3 for the centnfugal charging pump declared inoperable pursuant to Specification 4.1.2.3.2 provided that the centnfugal charging pump is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of the RCS cold legs exceeding 375*F, whichever comes first.

WOLF CREEK - UNIT 1 3/4 1-10 l

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Attachment IV to NA 94-0006 Page 5 of 7 l

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 5 - a. With the number of OPERABLE channels one less than the Mini-mum Channels OPERABLE requirement, 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 open the Reac-tor Trip Breakers, suspend all operations involving posttive reactivity changes and verify valves BG-V178 and BG-V601 are closed and secured in position within the next hour,

b. With no channels OPERABLE, open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes and verify compliance willLthe SH WN MARGIN requirements of Specification 3.1.1.1 3.J. u2, as-eaakce!e. ithin l

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> hereat;er, and ven y valves l

BG-V178 and BG-V601 are closed and secured in position within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and verified to be closed and secured in position every 14 days ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channelis placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and
b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

i ACTION 7 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 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 />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channelis operable.

l ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within l

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive l

onnunciator window (s) that the interlock is in its required state l

for the existing plant condition, or apply Specification 3.0.3.

l ACTION 9 - With the number of OPERABLE Reactor Trip Breakers one less than j

the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one breaker may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other breaker is OPERABLE.

ACTION 10 -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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.

ACTION 11 -With the number of OPERABLE channels less than the Total Number l

of Channels, operation may continue provided the inoperable channels are placed in the tripped condrtion within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

WOLF CREEK - UNIT 1 3/4 3-6 Amendment No. 42,26,43

Attachment IV to NA 94-0006 l

Page 6 of 7 l

3 4.1 REACTIVITY CONTROL SYSTEM I

BASES 3/41.1 BORATION CONTROL l

i 3/4.1.1.1 HUTDOWN MARGIN W

A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable lirtiits, and (3) the reactor will be maintained sufficiently subcritical to -

preclude inadvertent criticality in the shu+down condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,,. The most restrictive condition occurs at EOL, with T,,, at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown, in the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.3% Ak/k is required to controlthe reactivity transient. Accord-ingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T,,,less than 200 F, the reactivity transients resulting from a postulated steam line break cooldown are minimal and a 1.3% Ak/k SHUTDOWN MARGIN provides adequate protection.

3/41.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting i

condition assumed in the FSAR accident and transient analyses.

7 The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verificetion of MTC values at conditions other than those explicitly stated will requ;re extrapolation to those condfdons in order to permit an accurate comparison.

WOLF CREEK - UNIT 1 B 3/4 1-1 Amendment No. 61

Attachment IV to NA 94-0006 Page 7 of 7 i

BASES SECTION PAGE 3/4.0 APPLICABILITY...

B 3/4 0 1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL..

. B 3/4 1-1 3/4.1.2 BORATION SYSTEMS...

.... B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES..

B 3/41-3 3/4.2 POWER DISTRIBUTION LIMITS..

B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE..

B 3/

-1 3/4.2.2 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOf{pd oCS FLOt.^'

RATE ND NUCLEAR ENTHALPY RISE HOT CHANNEL FA OR.,

. B 3/4 2 1 c!GURE 9 3!4.2 4

!C^.L !ND!CATED,^v'^L FLUX D!FFERENCE VERSUS ER*.8^L POWEP 9?'i23 B /4 h 3/4.2.4 QUADRANT POWER TILT RATIO..

3/4.2.5 DNB PARAMETERS..

B 3/4 6 3 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION..

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION..

B 3/4 3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION..

B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...

B 3/4 4-1 3/4.4.2 SAFETY VALVES..

B 3/4 4-1 3/4.4.3 PRESSURIZER.,

B 3/4 4-2 3/4.4.4 RELIEF VALVES..

B 3/4 4-2 4

l WOLF CREEK - UNIT 1 XV "Y