ML20059N049
| ML20059N049 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/26/1990 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059N050 | List: |
| References | |
| NUDOCS 9010090208 | |
| Download: ML20059N049 (4) | |
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,I UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE AEOUIREMENTS m
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' 14.11 RADIOACTIVE STORAGE.
45 L' 3./ 4.' 1.1.1 - UOOiD STORAGE.
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Amendment No. 3J,114,.
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usx uMmHG CONDmONS POR OPERATON AND SURVEUL'ANCE REQUIREMENTS SEEQi BhGE 3/4 9 REFUA ING CMttAT10NS 3/4.9.1 BORCN CCNCENTRATICN............................................................... 3 /4 91 3/4.9.2 INSTRUMENTATION.................................................................
92 3/4.9.3 DECAY TIME................................................................
93 3/4.9.4" CONTAINMENT BUILDING PENETRATIONS....
......... 3/4 94 3/4.9.5 COWANCATONS...............................................................................
96 3/4.9.6 MANIPULATOR CRANE OPERABILITY.....................................
............. 3I4 97 3/4.9'.7 CRAN E TRAVEL - SPENT FUEL PtT....................................................... 3/4 98
- 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Wa te r Leve ls..........................................................................
LOW W8ter Level 8.........................................................................
9 9a 3/4.9.9 CONTAaNMENT PURGE AND EXHAUST ISOLATION SYSTEM................... 3/4 9 10 3/4.9.10 WATER LEVEL REACTOR VESSEL......................................................... 3 /4 9 11 3/4.9.11 SPENT FUEL PIT WATER LEVEL........................................................... 3/4 9 12 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM................................................ 3/4 - 9 13 3/4.10 SPECIALTEST EXE89TIONS 3/4.10.1 SHUTDOWN MUIGIN............................................................................. 3 /
3I4.10.2 GROUP HEIGHT,INSERTON, AND POWER DISTRBUTION................... 3/4 10 2 3/4.10.3 P HYSICS TEST....................................................................................... 3 /4 -
- 3/4'.10.4 FEACTOR 000UWT LOOPS.................................................................... 3 /4 10 4-NORTH ANNA UNIT 2 IX Amendment No. 121,
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C g ai.o. REACTOR COOLANT SYSTEM d.,',w
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. ISOLATED LOOP.
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LIMITING CONDITION FOR-OPERATION
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3.4.1.2 The boron ~ concentration of an isolated loop shall be maintained greater,than.or' equal to the boron concentration of the operating' loops, unless the loop has been drained for maintenance.
APPLICABILITY:
MODES 1, 2, 3, 4 and 5.
ACTION:
With the requirements of the above specification not satisfied, do not open the isolated' loop's stop valves; either increase the boton concentration of the-isolated loop 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 STAN0BY within the next 6-hours with the unisolated portion of the RCS borated to a SHUTDOWN, MARGIN equivalent to at least 1.77% Ak/k at 200*F.
' SURVEILLANCE' REQUIREMENTS
.4.4.1.2 The boron concentration of an isolated loop shall.be determined to be greater than or equal to the boron concentration of the operating loops at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and within 30 minutes prior to opening either the hot.
leg or cold leg stop valves of an isolated loop.
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-l NORTH ANNA - UNIT 2 3/4 4-4
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.i REACTOR COOLANT SYSTEM-m SHUT 00TI l-SURVEILLANCE REQUIREMENTS P
L 4.4.1.3.1 The required RHR subsystems shall be demonstrated OPERABLE.per Specification 4.7.9.2.
4.4.1.3.2 The required reactor coolant. pump (s), if not in operation, shall be determined to be OPERA 8LE once per :7 days by verifying correct breaker l
alignments and indicated power availability.
4.4.'1.3.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 17% at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-4.4.1.3.4. At least once' per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify at least one coolant loop to be in operation and circulating reactor coolant by:
Verifying at least one Reactor Coolant Pump is in operation.-
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or b.
Verifying at least one RHR Loop is -in operation and, 1.
if the RCS temperature > 140'F or the time since entry into MODE 3 is < 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, circulating reactor coolant at a flow rate 1 3000 gpm, or 2.
if the RCS temperature < 140'F and the time since entry-into MODE 3 is t 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, circulating reactor ~ coolant-at a flow rate 1 2000 gpm to remove decay heat.-
NORTH ANNA - UNIT 2 3/4 4-3a Amendment No'. 120,
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