ML20211A296
| ML20211A296 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/03/1986 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20211A294 | List: |
| References | |
| TAC-61930, NUDOCS 8610150063 | |
| Download: ML20211A296 (7) | |
Text
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DEFINITIONS Je CORE ALTERATION 1.7 CORE ALTERATION shall be the addition, removal, relocation or movement of fuel, sources, incore instruments or reactivity controls within the reactor o
pressure vessel with the vessel head removed and fuel in the vessel.
3 Suspension of CORE ALTERATIONS shall not preclude completion of the movement 2-of a component to a safe conservative position.
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h CRITICAL POWER RATIO
,.7 1.8 The CRITICAL POWER RATIO (CPR) shall be the ratiofof that power in the
/
assembly which is calculated by application of the-6Ent correlation to cause l
some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE EQUIVALENT I-131 1.9 00SE EQUIVALENT I-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, I-133,1-134, and I-135 actually present.
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The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
DRYWELL INTEGRITY 1.10 DRYWELL INTEGRITY shall exist when:
a.
All drywell penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an OPERABLE drywell automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, L
except as provided in Table 3.6.4-1 of Specification 3.6.4.
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8 b.
The drywell equipment hatch is closed and sealed.
c.
The drywell airlock is in compliance with the requirements of ne Specification 3.6.2.3.
m 88 d.
The drywell leakage rates are within the Itaits of Specification g4 3.6.2.2.
og e.
The suppression pool is in compliance with the requirements of am. a-Specification 3.6.3.1.
f.
The sealing mechanism arsociated with each drywell penetration; e.g., welds, bellows or 0-cings, is OPERABLE.
GRAND GULF-1 1-2
$DOMENT NO-
d 3/4.2 POWER DISTRIBUTION LIMITS h
h 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 4
During wo loop opm# ion all f
3.2.1(-AM AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figure 3.2.1-1 as multiplied by the smaller of either the flow-dependent MAPLHGR factor (MAPFAC ) of Figure 3.2.1-2, or the power-dependent f
MAPLHGR factor (MAPFAC ) of Figure 3.2.1-3.
N W it.T 3.21 p
APPLICABILITY:
OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
ACTION:
r" 1N4LET 1 "ith :: f'"""" :::::dia; th: ;;;15::51: licit:, initiate corrective action l
within 15 minutes and restore APLHGR to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
t SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the :;;1icabh g,rg )
g limits:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is c.
operating with a LIMITING CONTROL ROD PATTERN for APLHGR.
d.
The provisions of Specification 4.0.4 are not applicable.
GRAND GULF-UNIT 1 3/4 2-1 Amendment No.
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Insert 3.2.1 During single loop operation, the APLHGR for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits as determined below:
a) for fuel types 8CR210 and 8CR160 - the limit shewn in figure 3.2.1-1 as multiplied by the smaller of either MAPFAC(f), MAPFAC(p) or 0.86; and b) for fuel type XN-1 the Ifmit determined in "a" above for fuel type 8CR210.
Insert 1 During two loop operation or single loop operation, with an APLHGR exceeding the limits of Figure 3.2.1-1, as corrected by the appropriate multiplication factor for each type of fuel, J13 MISC 86092302 - 3 J
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AVERAGE PLANAR EXPOSURE (mwd /ST)
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FIGURE 3.2.1-1 MAXIMUM AVERAGE PLArJAR LINEAR HEAT GENERATION RATE (MAPI.HGR)
VERSUS AVERAGE PLAtlAR EXPOSURE '^^ "^"' " "^ ~^^ ~'N-l CORE FUEL TYPES 8CR2iO,8CRl60, AND XN-l i
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t POWER DISTRIBITTION LIMITS y
3/4.2.4 LINEAR HEAT GENERATION RATE g
LIMITING CONDITION FOR OPERATION t
rm 3.2.4.1 The LINEAR REAT GENERATION RATE (IJIGR) for GE fuel shall not exceed D
U 13.4 kw/ft.
'Ibe LINEAR HEAT GENERATION RATE (LHGR) for ENC fuel shall not exceed the.W"*i lisi: de e. gd f Figu 3.2.4-1.
APPLICABILITY: OPERATIONAL CONDITION 1, when 'DIERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
.In +ser 2 ACTION'
" ENC.
-of Rgore 3. 2A-l Vith the LHGR"of any" fuel rod exceeding the limit, initiate corrective action within 15 minutes and restore the LHGR to within the limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or
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reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS of M 6.G. fuel W ENC 848 LHGR's(shall be determined to be equal or less than th lici::g-Weir-allewdle UmM 4.2.4.1 4o/
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, c.
Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating on a LIMITING C0!frROL ROD PATIIRN for LHGR, and d.
The provisions of Specification 4.0.4 are not applicable.
GRAND GULF-UNIT 1 3/4 2-7 MENDMEN1-No.
J38 MISC 86070704 - 1
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F Insert 2 of any GE fuel rod exceeding the 13.4 Kw/ft limit or with the LHGR J13 MISC 86092302 - 4 1