ML20003G108
| ML20003G108 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/20/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003G098 | List: |
| References | |
| TAC-12883, NUDOCS 8104280264 | |
| Download: ML20003G108 (4) | |
Text
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ATTACHMENT TO ORDER FOR 10DIFICATION OF FACILITY OPERATIrlG LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages contain vertical lines indi-cating the area of change.
3/4 4-15 3/4 4-16 3/4 4-18a (new)
I DN r8704280
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, 1 GPM total primary-to-secondary leakage through steam gen-c.
- erators, d.
10 ;@M IDENTIFIED LEAKAGE from the Reactor Coolant System, 10 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure e.
of 2150 + 20 psig, and f.
Leakage as specified in Table 3.4-2 for those Reactor Coolant System Pressure Isolation Valves identified in Table 3.4-2.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY a.
within 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 any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce taa leakage rate to within 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 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 />.
With any Reactor Coolant System Pressure Isolation Valve leakage greater c.
than the above limit, reactor operation may continue provided that at least two ' valves in each high pressure line having a non-functional valve are in, and remain.in, the mode corresponding to the isolated condition.
(Motor operated valves shall be placed in the closed position and power supplies dqenergized,)
d.
The provisions of Section 3.0.4 are not aoolicable for entry into MODES 3 and 4 for the purpose of testing the isolation check valves.
i CRYSTAL RIVER - UNIT 3 3/4 4-15 Order dtd.4/zu/ul
REACTOR C00LAt;T SYSTEM SURVEILLANCE REGUIREMENTS 4. 4. 6. 2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
a.
Monitoring the containment atmosphere iodine radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
Measurecent cf the CONTROLLED LEAKAGE from the reactor coolant.
pump seals when the Reactor Coolant System pressura is 2150 ; 20 psig at least once per 31 days, d.
Performance of a Reactor Coolant System water inventory balance at least once per 72 nours during steacy state cperation.
4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Yalve specified in Table 3.4-2 shall be individually demonstrated OPERABLE prior to entering
.%DE 2 by verifying leakage to be within its limit:
a.
After each refueling outage,
.b.
Whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or more, if leakage testing has not been perfomed in the previous 9 nonths, and c.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve.
4.4.6.2.3 Whenever integrity of a pressure isolation valve listed in Table 3.4-2 cannot be demonstrated, the integrity of the remaining valve in eacn high pressure line having a leaking valve shall be detemined and recorded daily.
In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily.
t i
hde dj. 4 2 CRYSTAL RIVER - Utili 3 3/4 #-I6 1
TABLE 3.4-2 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES System Valve Maximum Allowable Leakage (a)(b)(c)
Decay Heat / Low CFV-1
< 5.0 gpm Pressure Injection DHV-2
< 5.0 gpm l
CFV-3
< 5.0 gpm DHV-1
< 5.0 gpm Notes:
(a) Maximum Allowable Leakage (each valve):
1.
Leakage rates less than or equal to 1.0 gpm are considered acceptable.
l 2.
Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum pemissible rate of 5.0 gpm by 50% or greater.
l l
3.
!.eakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the l
rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
4.
Leakage rates greater than 5.0 gpm are considered unacceptable.
(b) To satisfy ALARA requirements, leakage may be measured indirectly (as fmm the perfomance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the l
method is capable of demonstrating valve compliance with the leakage l
criteria.
l (c) Minimum differential test pressure shall not be less than 150 psid.
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e 3
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I CRYSTAL RIVER - UNIT 3 3/4 4-18a Order dtd.4/20/81
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