ML20211G307
| ML20211G307 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/19/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211G313 | List: |
| References | |
| NUDOCS 9710020216 | |
| Download: ML20211G307 (8) | |
Text
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INDEX BASES SECTION EAG1 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 and 3/4.5.2 ECCS-OPERATING and SHUTDOWN.............. B 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER................................ B 3/4 5-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity...................... B 3/4 6-1 l
Primary Containment Air Locks...................... B 3/4 6-1 Drywell and Suppression Chamber Internal Pressure.
B 3/4 6-2 Drywell Average Air Temperature.................... B 3/4 6-2 Drywell and Suppression. Chamber Purge System....... B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS........................... B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES...............
B 3/4 6-4 3/4.6.4 VACUUM RELI EF...................................... B 3 /4 6-4 3/4.6.5 SECONDARY CONTAINMENT..............................
B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL............. B 3/4 6-5 LA SALLE - UNIT 1 XIV Amendment No. 118 9710020216 970919 i
PDR ADOCK 05000373 P
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:
a.
b.
5 gpm UNIDENTIFIED LEAKAGE.
c.
25 gpm total leakage averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, d.
1 gpm leakage at a reactor coolant system pressure at 1000 1 50 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.
e.
2 gpm increase in UNIDENTIFIED LEAKAGE within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With any reactor coolant system leakage greater than the limits in.b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed valves, or be in at least HOT SHUTDOWN within the next 12' hours and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
'With one or more high/ low pressure interface valve leakage pressure monitors inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication; restore the inoperable monitor (s) to OPERABLE status within-30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, e.
With any reactor coolant system leakage greater than the limit in e above, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
LA SALLE - UNIT 1 3/4 4-7 Amendment No. 118
CONTAINMENT SYSTEMS SURVElllANCE RE0VIREMENTS (Continued) c.
Deleted.
d.
By conducting drywell-to-suppression chamber bypass leak tests at least once per 18 months at an initial differential pressure of 1.5 psi and verifying that the A//k calculated from the measured leakage is within the specified limit.
If any 1.5 psi leak test results in a calculated A//k >20% of the specified limit, then the test schedule for subsequent tests shall be reviewed by the Commission.
If two consecutive 1.5 psi leak tests result in a calculated A//k greater than the specified limit, then:
1.
A 1.5 )si leak test shall be performed at least once per 9 montas until two consecutive 1.5 psi leak tests result in the calculated A//k within the specified limits, and 2.
A 5 psi leak test, performed with the second consecutive successful 1.5 psi leak test, results in a calculated A//k within the specified limit, after which the above schedule of once per 18 months for only 1.5 psi leak tests may be resumed.
If any required 5 psi leak test results in a calcu'ated A//k greater than the specified limit, then the test schedule for subsequent tests shall be reviewed by the Commission.
If two consecutive 5 psi leak tests result in a calculated A//k greater than the specified limit, then a 5 psi leak test shall be performed at least once per 9 months until two consecutive 5 psi leak tests result in a calculated A//k within the specified limit, after which the above schedule of once per 18 months for only 1.5 psi leak tests may be resumed.
I LA SALLE - UNIT 1 3/4 6-18 Amendment No.
118
INDEX BASES SECTION EAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 and 3/4.5.2 ECCS-OPERATING and SHUTDOWN..............
B 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER................................
B 3/4 5-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity......................
B 3/4 6-1 Primary, Containment Air Locks......................
B 3/4 6-2 Drywell and Suppression Chamber Internal Pressure..
B 3/4 6-2a Drywell Average Air Temperature....................
B 3/4 6-2a Drywell and Suppression Chamber Purge System.......
B 3/4 6-2a 3/4.6.2 DEPRESSURIZATION SYSTEMS........
B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES...............
B 3/4 6-4 3/4.6.4 VACUUM RELIEF......................................
B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT..............................
B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL.............
B 3/4 6-5 LA SALLE - UNIT 2 XIV Amendment No. 103
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION
.3.4.3.2 Reactor coolant system leakage shall be limited to:
a.
No PRESSURE B0UNDARY LEAKAGE.
b.
5 gpm UNIDENTIFIED LEAKAGE.
c.
25 gpm total leakage averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
d.
I gpm leakage at a reactor coolant system pressure at 1000 50 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.
e.
2 gpm increase in UNIDENTIFIED LEAKAGE within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
u ACT12N:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.
With any reactor coolant system pressure isolation valve leakage greater than the above limits, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, d.
With one or more high/ low pressure interface valve leakage pressure
. monitors inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication; restore the inoperable monitor (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
e.
With any reactor coolant system leakage greater than the limit in e, above, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
LA SALLE - UNIT 2 3/4 4-8 Amendment No.
103
EMERGENCY CORE COOLING SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) l ACTION:
(Continued) 1.
In the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.6.C within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
j.
With one or more ECCS corner room watertight doors inoperable, restore all the inoperable ECCS corner room watertight doors to OPERABLE status within 14 days, otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
k.
With ADS accumulator backup compre sed gas system bottle pressure s
less than 500 psig, restore ADS accumulator backup compressed gas system bottle pressure to greater than 500 psig within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the associated ADS valves inoperable, and follow Action e of this specification.
1
)
LA SALLE - UNIT 2 3/4 5-3a Amendment No. 103
o CONTAINMENT SYSTEMS SURVElllANCE RE0VIREMENTS (Continued) c.
Deleted.
d.
By conducting drywell-to-suppression chamber bypass leak tests at least once per 18 months at an initial differential pressure of 1.5 psi and verifying that the A//k calculated from the measured leakage is within the specified listit.
If any 1.5 psi leak test results in a calculated A//k >20% of the specified limit, then the test schedule for subsequent tests shall be reviewed by the Commission.
If two consecutive 1.5 psi leak tests result in a calculated A//k greater than the specified limit, then:
1.
A 1.5 asi leak test shall be performed at least once per 9 montis until two consecutive 1.5 psi leak tests result in the calculated A//k within the specified limits, and 2.
A 5 psi leak test, performed with tie second consecutive successful 1.5 psi leak test, results in a calculated A//k within the specified limit, after which the above schedule of once per 18 months for only 1.5 psi leak tests may be resumed.
If any required 5 psi leak test results in a calculated A//k greater than the specified limit, then the test schedule for subsequent tests shall be reviewed by the Commission.
If two consecutive 5 psi leak tests result in a calculated A//k greater than the specified limit, then a 5 psi leak test shall be performed at least once per 9 months until two consecutive 5 psi leak tests result in a calculated A//k within the specified limit, after which the above schedule of once per 18 months for only 1.5 psi leak tests may be resumed.
LA SALLE - UNIT 2 3/4 6-21 Amendment No.
103
i ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) the Initial Structural Integrity Tests were not within 2 years of each other.
The Onsite Review and Investigative Function shall be responsible for reviewing and approving changes to the Inservice Inspection Program for Post Tensioning Tendons.
The provisions of 4.0.2 and 4.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
6.2.F.7 Primary Containment leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions.
Thisprogramshallbein accordance with the guidelines contained in Regulatory Guide 1.163,
" Performance-Based Containment Leak-Testing Program," dated September 1995.
The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P,, is 39.6 psig.
The maximum allowable primary containment leakage rate, L, at P,, is 0.635% of primary containment air weight per day.
Leakage rate acceptance criteria are:
a.
Primary containment overall leakage rate acceptance criterion is s1.0 L During the first unit startup following testing in accordance with this,.
program, the leakage rate acceptance criteria are s 0.60 L, tests.
for the combined Type B and Type C tests, and 5 0.75 L, for Type A b.
Air lcck testing acceptance criteria are:
1)
Overall air lock leakage rate is so 05 L, when tested at 2 P,.
2)
For each door, the seal leakage rate is s 5 scf per hour when the gap between the door seals is pressurized to 2 10 psig.
The provisions of specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of specification 4.0.3 are applicable to the Primary Contair. ment Leakage Rate Testing Program.
6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Onsite Review and Investigative Function.
LA SALLE - UNIT 2 6-20a Amendment No.
95 l