ML051820139

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Limiting Condition for Operation and Surveillance Requirements
ML051820139
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/29/2005
From:
NRC/NRR/DLPM/LPD1
To:
Dominion Nuclear Connecticut
References
Download: ML051820139 (11)
v • d • e


Text

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT ..................................... 3/4 6-1 Containment Integrity ..................................... 3/4 6-1 Containment Leakage ..................................... 3/4 6-2 Containment Air Locks ..................................... 3/4 6-6 Internal Pressure ..................................... 3/4 6-8 Air Temperature ..................................... 3/4 6-9 DELETED 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS ............................... 3/4 6-12 Containment Spray and Cooling Systems ..................................... 3/4 6-12 DELETED 3/4.6.3 CONTAINMENT ISOLATION VALVES ..................................... 3/4 6-15 Containment Ventilation System ..................................... 3/4 6-19 3/4.6.4 COMBUSTIBLE GAS CONTROL ..................................... 3/4 6-20 DELETED DELETED DELETED Post-Incident Recirculation Systems ..................................... 3/4 6-24 3/4.6.5 SECONDARY CONTAINMENT .......... ........................... 3/4 6-25 Enclosure Building Filtration System ..................................... 3/4 6-25 Enclosure Building ..................................... 3/4 6-28 MILLSTONE - UNIT 2 VII Amendment No. 4-04, 44-, 208, 2-I, a33,2 ., 287

CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL DELETED MILLSTONE - UNIT 2 3/4 6-20 Amendment No. 420,287

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 2 3/4 6-21 Amendment No. 287

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 2 3/4 6-22 Amnendment No. 287

INDEX LIMITING CONDMONS FOR OPERATION AND SURVEiLLANCE REQUIREMENTS SECTION Air Temperature .............................................. 3/4 6-9 Containment Structural Integrity .............................................. 3/4 6-10 Containment Ventilation System .............................................. 3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Quench Spray System . 3/4 6-12 Recirculation Spray System .3/4 6-13 3/4.6.3 CONTAINMENT ISOLATION VALVES .314 6-15 3/4.6.4 DELETED 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM Steam Jet Air Ejector ............. 3/4 6-18 3/4.6.6 SECONDARY CONTAINMENT Supplementary Leak Collection and Release System ................................ 3/4 6-19 Secondary Containment .............................................. 3/4 6-22 Secondary Containment Structural Integrity......................................................................................3/4 6-23 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves..............................................................................................3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES ....... 3/4 7-2 TABLE 3.7-2 DELETED ................ 3/4 7-2 MILLSTONE - UNIT 3 ix Amendment No. 5, 6;, ;, 8A , 4-00, 4--, 4-6, 247, 224

lNSTRUMENTATION ACCIDENT MONITORING INJSTRUMENTATIO>N LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE accident monitoring instrumentation channels except the containment area high range radiation monitor, and reactor vessel water level, less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel(s) to OPERABLE status within 7 days, 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 at least 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 />.
b. With the number of OPERABLE accident monitoring instrumentation channels

'except the containment area-high range radiation monitor, and reactor vessel water level less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore the inoperable channel(s) 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 at least 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 />.

c. With the number of OPERABLE channels for the containment area-high range radiation monitor less than required by either the total or the Minimum Channels OPERABLE requirements, initiate an alternate method of monitoring the 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 either restore the inoperable channel(s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission, pursuant to Specification 6.9.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status.
d. Deleted C. With the number of OPERABLE channels for the reactor vessel water level monitor less than the Total number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the MILLSTONE - UNIT 3 3/4 3-59 Amendment No. 47, 5, 46,224

LIMITING CONDITION FOR OPERATION (Continued) action taken, the cause of the inoperability, and the plans and schedule for restoring the chanmel to OPERABLE status.

f. With the number of OPERABLE channels for the reactor vessel water level monitor less than the minimum channels OPERABLE requirements of Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or I. Initiate an alternate method of monitoring the reactor vessel inventory;
2. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 withini 30 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the channel(s) to OPERABLE status; and
3. Restore the channel(s) to OPERABLE status at the next scheduled refueling.
g. Entry into an OPERATIONAL MODE is permitted while subject to these ACTION requirements.

SURVEILLANCE REQUIREMENTS.

4.3.3.6.1 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-7.

4.33.62 Deleted MNLLSTONE - UNIT 3 3/4 3-59a Amendment No. 4-7, 5, 6, 44f 224

H TABLE 3.3-10 (Continued)

ACCIDENT MONITORING INSTRUMENTATION TOTAL MINIMUM NO. OF CHANNELS U3 INSTRUMENT

16. Containment Area - High Range Radiation Monitor CHNNELS 2

OPERABLE 1

17. Reactor Vessel Water Level 2* 1*
18. Deleted I
w 19. Neutron Flux 2 1
  • A channel consists of eight sensors in a probe. A channel is operable if four or more sensors, half or more in the upper head region and half or more in the upper plenum region, are operable.

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P N)- N) :~' . I.

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cn TABLE 4.3-7 (Continued)

ACCEDENT-MONITORING INSTRUMENTA ION SURVEITLLANC:E RECOUEREMUENTS I

0 CHANNEL CHANNEL 5INSRUMENT CHECK CALIBRATION

16. Containment Area - High Range Radiation Monitor M
17. Reactor Vessel Water Level M
18. Deleted I
19. Neutron Flux M R l6) w 0%
  • CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed or portable gamma source.

1* Electronic calibration from the ICC cabinets only.

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THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 6-16 Amendment No. 47, 47, iO,4a4, 224

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE, - UNIT 3 3/4 6-17 Amendment No. 4-7, 63, 40,,,42, , 224

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