ML17053C582
| ML17053C582 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/20/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17053C578 | List: |
| References | |
| NUDOCS 8105010579 | |
| Download: ML17053C582 (6) | |
Text
Attachment 3
ATTACHMENT TO ORDER FOR MODIFICATION OF FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Add page 120a and 120b to the Appendix "A" Technical Specifications.
1
p'
LIHITING CONDITION FOR OPERATION SURVEILLANCE RE(UIREHENT 3.2.7.1 PRIHARY COOLANT SYSTEH PRESSURE ISOLATION VALVES AmffifAliflii 4.2.7.1 PRIHARY. COOLANT SYSTEH PRESSURE ISOLATION VALVES A~ii Alii Applies to the operating status of isolation valves for systems connected to the primary
-coolant system.
'0b ective:
To increase the reliability of primary coolant system pressure isolation valves thereby reducing the potential of an intersystem loss of coolant accident.
~fifl a.
The integrity of all pressure isolation valves listed in Table 3.2.7.1 shall be demonstrated.
Valve leakage shall not exceed the amounts indicated.
Applies to the periodic testing of primary c'oolant system pressure isolation valves.
~0b'ective To increase the reliability of primary coolant system pressure isolation valves thereby reducing the potential of an inter system loss of coolant accident.
AA ifi a.
Periodic leakage testing on each valve listed in Table 3.2.7.1 shall be accomplished prior to exceeding 2C power while in the power operating condition. every time the plant is placed in a cold shutdown condition for refueling, each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to returning the valve to service after maintenance, repa r
replacement work is performed.
- b. If Specification a cannot be met, an orderly shutdown shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the reactor shall be in the cold shutdown condition within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Or der dated:
April 20, 1981 To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pr essure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.
120a
~ >
TABLE 3.2.7.1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES
~Ss tern 1.
Core Spray System
-2.
Condensate Supply to Core Spray (Keep Fill System)
Val ve No.
40-03.
40-13 40-20 40-21 40-22 40-23 Maximum Allowable Leaka e
<5.0 gpm
<5.0 gpm
<5'.0 gpm
<5.0 gpm
<5.0 gpm
<5.0 gpm Footnote:.
Leakage 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 has not exceeded the rate determined by the previous test by,an amoun 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 50Ã or greater.
4.
Leakage rates greater than 5.0 gpm are considered unacceptable.
5.
Test differential pressure shall not be less than 150 psid.
Order dated:
April 20, 1981 120b
0 a,r.~ w,