ML20076L239
| ML20076L239 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/13/1983 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20076L231 | List: |
| References | |
| TVA-SQN-TS-47, NUDOCS 8307190094 | |
| Download: ML20076L239 (6) | |
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.V ENCLOSURE Revised Pages for Proposed Technical Specifications SEQUOYAH NUCLEAR PLANT TVA-SQN-TS-47 4
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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) g.
The limits specified in 4.2.2.2.c[ 4.2.2.2.e and 4.2.2.2. f above are not applicable in the following core plane regions:
1.
Lower core region 0 to 15 percent inclusive.
2.
Upper core region 85 to 100 percent inclusive.
4.2.2.3 When F (z) is measured for reasons other than meeting the requirements 9
of Specification 4.2.2.2 an overall measured F (z) shall be obtained from a q
power distribution map and increased by 3 percent to account for manufacturing tolerances for further increased by 5 percent to account for measurement uncertainty.
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POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOWRATE AND R
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LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and R, R shall be maintained within the regions of allowable j
2 operation shown on Figure 3.2-3 for 4 loop operation:
Where:
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R
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1 1.49 [1.0 + 0.3 (1.0 - P)]
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R 2
[1 - RBP (Bu)]
THERMAL POWER p
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RATED THERMAL POWER
- FfH d.
Measured values of F btained by using the movable
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H incore detectors to obtain a power distribution map.
The measured values of F shall be used to calculate R since Figure 3.2-3 includes measurement uncertainties of 3.5% for flow and 4% for incore measurement of F and e.
RBP (Bu) =
Rod Bow Penalty as a function of region average burnup as shown in Figure 3.2-4, where a region is defined as those assemblies with the same loading date (reloads) or enrichment,Jfirst core).
APPLICABILITY: MODE 1 ACTION:
With the combination of RCS total flow rate and R, R utside the regicns j
2 of acceptable operation shown on Figure 3.2-3:
a.
Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
1.
Either restore the combination of RCS total flow rate and R, R t within the above limits, or j
2 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High trip setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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CONTAINMENT SYSTEMS
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VENTILATION SYSTEM
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LIMITING CONDITION FOR OPERATION 3.6.1.9 Three pairs (three purge supply lines and three purge exhaust lines) of containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.
Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to less than or equal to 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per 365 days.
The 365 day cumulative time period will begin every January 1.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With a purge supply or exhaust isolation valve open in excess of the above cumulative limit, or with more than three pairs of 'cdntainmentipurge system lines open, close the isolation valve (s), in the purge line(s) within one hour or be 1
l 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 COLO SHUT 00WN within
.l the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS
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4.6.1.9.1 The position of the containment purge supply and exhaust isolation 3
valves shall be determined at least once per 31 days.
4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation valves are open over a 365 day ~ period shall be determined at least once-per 7 days.
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ilYDROGFN MITIGATION SYSTEM
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LIMITING CONDITION FOR OPERATION 3.6.4.3 The primary containment hydrogen mitigation system shall be operable.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With one train of hydrogen mitigation system inoperable, restore the inoperable train to OPERABLE status within 7 days or increase the surveillance interval of S.R. 4.6.4.3 from 92 days to 7 days on the operable train until the
' inoperable train is returned to OPERABLE status.
SURVEILLANCE REOUIREMENTS 4.6.4.3 The hydrogen mitigation system shall be demonstrated OPERABLE:
At least once per 92 days by energizing the supply breakers and a.
._ _ verifying that at least 66 of 68 igniters are energized.*
b.
At least once per 18 months by verifying the temperature of each igniter is a minimum of 1700 F 4I -
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" Inoperable igniters must not be on corresponding redundant circuits which provide coverage-for the same region.
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ADMINISTRATIVE CONTROLS ~
e.
An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radiciodine in gaseous effluents; The report of an unplanned offsite release of radioactive material shall include the following information:
1.
A description of the event and equipment involved.
2.
Cause(s) for the unplanned release.
3.
Actions taken to prevent ~ recurrence.
4.
Consequences of the unplanned release.
f.
Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 3.12-2 when averaged over any calendar quarter sampling period.
9 RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided to the Direc-
- tor, Nuclear Reactor Regulation, Attention, Chief of the Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 at least 60 days prior to cycle initial criticality.
In the event that these values would be.
submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.
i Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.
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SPECIAL REPORTS 6.9.2.Special ~ reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified-for each report.
6.10 RECORD RETENTION' In addition to the applicable record retention requirements of Title 10, Code
- of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The.following records shall be retained for at least five years:
Recordsandlogsofunitoperationcoveringtimei[1tervalateach a.
power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replaceme,nt of principal items of equipment related to nuclear safety.
li SEQUOYAH - UNIT-2 6-27
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