ML19347E356
| ML19347E356 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/20/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347E354 | List: |
| References | |
| NUDOCS 8104270113 | |
| Download: ML19347E356 (4) | |
Text
ATTACHMENT TO ORDt'R FOR MODIFICATION OF FACILITY OPERATING LICEi;SE NO. NPF-3 i
DOCKET NO. 50-346 i
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Replace the following pages of Appendix "A" Technical Specifications with the enclosed pages. The revised pages contain vertical lines indicating the area of change.
3/4 4-15 3/4 4-16 3/4 4-16a (new) i 8104s7o3:3
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION F0,R OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE B0UNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, c.
1 GPM total primary-to-secondary leakage through steam generators, d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, e.
10 GPM CONTROLLED LEAKAGE, and f.
5 GPM leakage from any Reactor Coolant System Pressure Isolation Valve as specified in Table 3.4-2.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
a.
With any PRESSURE B0VHDARY LEAKAGE, be in at least HOT STANDBY 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 B0UNDARY LEAKAGE, reduce the 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 /> except as ptmitted by paragraph c below.
I c.
In the event that integrity of any pressure isolation valve specified in Table 3.4-2 cannot be demonstrated, power 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.(a) d.
The provisions of Sections 3.0.4 and 4.0.4 are not, applicable for entry into MODES 3 and 4 for the purpose of testing the isolation valves in Table 3.4-2.
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(a)
Motor operated valves shall be placed in the closed position and power supplies deenergized.
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DAVIS-BESSE, UNIT 1 3/4 4-15 Order dtd. 4/20/81 1
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l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within l
each of the above limits by:
Monitoring the containment atmosphere particulate radioactivity a.
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 />.
Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals c.
to the makeup system when the Reactor Coolant System pressure is 2185
+ 20 psig at least once per 31 days.
d.
Performance of a Reactor Coolant System water inventory halance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation.
4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-2 shall be individually demonstrated OPERABLE by verifying leakage testing (or the equivalent) to be within its limit prior to entering MODE 2:
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, and if leakage testing has not been performed in the previous 9 months, and Prior to returning the valve to service following maintenance, repair l
c.
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 l
pressure isolation valve in each high pressure line having a leaking l
valve shall be determined and recorded daily.
In addition, the posi-tion of the other closed valve located in the high pressure piping shall be recorded daily.
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DAVIS-BESSE,. UNIT 1 3/4 4-16 Order dtd. 4/20/81 l
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TABLE 3.4-2 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES SYSTEM VALVE NUMBERS (b)
MAXIMlT4 ALLOWABLE LEAKAGE (a)(c) 1.
Decay Heat Removal CF-30 1 5.0 gpm 2.
Decay Heat Removal CF-31 5 5.0 gpm 3.
Decay Heat Removal DH-76 s 5.0 gpm 4.
Decay Heat Removal DH-77 5 5.0 gpm Notes:
(a) 1.
8 eakage rates less than or equal to 1.0 gpm are considered acceptable.
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 h63 not exceeded the 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.
3.
Leakage 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 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 unaccept~able.
(b)
Valvei CF-30 and CF-31 will be tested with the Reactor Coolant l
system pressure >1200 psig. Valves DH-76 and DH-77 will be tested with normal Core Flooding Tank pressure which is >575 psig. Mini-mum differential test pressure across each valve shall not be less than 150 psid.
(c)
To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance
[
with the leaka<je criteria.
l DAVIS-BESSE, UNIT 1 3/4 4-16a Order dtd.
4/20/81 l
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