ML20033A279
| ML20033A279 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/05/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033A276 | List: |
| References | |
| NUDOCS 8111250072 | |
| Download: ML20033A279 (2) | |
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TABLE 3.3-6 (Continued)
ACTION STATEMENTS ACTICN 25 - Oith the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, perform area survsys of the monitored area with portable menitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 26 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of. Specification (3.4.6.1).
ACTION 27 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTICN require ents of Specification (3.9.12).
ACTION 2B - With the number of OPERABLE channels less than required by tne Minimum Channels OPERABLE requirement, comply with the ACTIC" requirements of Specification (3.9.9).
ACTION 29 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initia;a and maintain operation of the control room amergency ventilatien system in the recirculation mode of operation.
ACTION 30 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) to OPERA 3LE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
- 1) Initiate the preplanned alternate method of monitoring
'the appropriate parameter (s), and
- 2) ' Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 i
days following the event outlining the action taken, the cause of the inoperability and the plans and i
schedule for restoring the system to OPERABLE status.
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INSTR, K,AfiCN BASES The 00E* 91LITY of these systems is required to provice the overall reliability, re:fundance and diversity assumed available in the facility design for the pretection and mitigation of accident and transient conditions.
The integrated cperation of each of these systems is consistent with the assumptions used in the accident analyses.
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 measurement of response time at the specified frequencies provides assurance that the RPS and ESFAS 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 test 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.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION HONITORING INSTRUMENTATION Tne OPERABILITY of the radiation monitoring channels ensures that:
- 1) the radiation levels are continually measured in the areas served by the individual channels; 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and 3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is konsistent with the recomendations of Regulatory Guide 1.97,
" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and i
Environs Conditicns During and Following an Accident," December 1980 and NUREG-0737,
" Clarification of TMI Action Plan Requirements," November, 1980.
1 3/4.3.3.2 C'!ABLE INCORE DETECTORS l
The OPERABILITY of the movable incore detectors with the specified minimum i
complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distributien of 'the reactor core. The OPERABILITY of this system is de onstrated by irradiating each detector used and, determining the acceptability of its voltage curve.
For the purpcse of measuring F (Z) or Fh a full incore flux map is used.
9 Quarter core flux r.aps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full inco,o flux maps or sye?.etric incore thimbles may be used for monitaring the QUADRANT POWER TILT RATIO when one Pcwer Range Channel is ineperable.
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