ML20133A713

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Proposed Tech Specs 3.13 Re Refueling & Fuel Consolidation Operations & Table 4.2-1 Re Minimum Frequencies for Sampling Tests
ML20133A713
Person / Time
Site: Maine Yankee
Issue date: 12/19/1996
From:
Maine Yankee
To:
Shared Package
ML20133A703 List:
References
NUDOCS 9701020071
Download: ML20133A713 (4)


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AUACHMENLB TECHNI. CAL _ SPEC IEICAIION_ CHANGE _PAGES )

E0R_ PROP _0 SED _CHANGEJi0._202 3.13 Refueling and Fuel Consolidation Operations Page 3.131 3.15 Reactivity Anomalies Page 3.151, and  !

Table 4.21, Minimum Frequencies for Sampling Tests Page 4.2 2 j 9

l 9701.020071 961219 PDR ADOCK 05000309.

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, 3.13 REEUELING_AND lVEL_ CONS 0LIDATION 0RERATIONS Applicability:

Applies to operating limitations during refueling and fuel consolidation operations. l l

Objective To minimize the possibility of an accident occurring during refueling and fuel consolidation operations that could affect the health and safety of plant personnel l and the public. i

Specification: )

A. Prior to each refueling a complete checkout, including a load test, shall be conducted on fuel handling cranes that will be used to handle irradiated fuel j assemblies.

B. Irradiated fuel shall not be moved until 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> after the reactor has been made subcritical.

C. Whenever the reactor vessel head is removed and there is fuel in the reactor, the refueling boron concentration shall be maintained in the reactor  :

l coolant system and shall be checked by sampling Daily (D) to insure that it I is sufficient to maintain the core 5% delta k/k subcritical.

D. The following conditions shall be satisfied during core alterations or movement of irradiated fuel within the containment:

1. The containment equipment hatch must be closed and held in place by a minimum of four bolts when the reactor has been subcritical less than 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />.
2. At least one door in the personnel airlock shall be closed when the reactor has been subcritical less than 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />.

Exception: Both personnel airlock doors may be opened briefly within the 210 hour0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> period to allow passage of long objects through the airlock.

3. The containment venting and purge inlet and outlet trip valves shall be closed or be operable and able to isolate the ventilation system in response to high radiation signals. The venting and purge system discharge shall be filtered through the high efficiency particulate air filters and charcoal absorbers.

Exception: The HEPA filters and charcoal absorbers may be bypassed after the reactor has been subcritical for 210 or more hours.

Amendment No. 54r65-73-75-144 3.13 1

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l ' AppGcability:

, Applies to potential reactivity anomalies. )

i- Objective:

To require evaluation of reactivity anomalies within the reactor.

l Specification:

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Following a normalization of the computed boron concentration as a function of l

~ burnup, the actual boron concentration of the reactor coolant shall be periodically  :

compared with the predicted value. The difference between the observed and ,

predicted steady-state concentrations shall be less than the equivalent of 1% of  !

-- reactivity. I RemediaLA.ction:

1 The Nuclear Regulatory Commission shall be notified and an evaluation as to the cause of the discrepancy shall be made and reported to the Nuclear Regulatory Commission in accordance with Technical Specification 5.9.1.7.

Basis:

To eliminate possible errors in the calculations of the initial reactivity of the core and ,

the reactivity depletion rate, the predicted relation between fuel bumup and the boron concentration, necessary to maintain adequate control characteristics, must be adjusted (normalized) to accurately reflect actual core conditions. When full power is reached initially, and with the CEA groups in the desired positions, the boron concentration is measured and the predicted curve is adjusted to this point.

As power operation proceeds, the measured boron concentration is compared with the predicted concentration and the slope of the curve relating bumup and reactivity i is compared with that predicted. This process of normalization should be completed i after about 10% of the total core bumup. Thereafter, actual boron concentration can  !

.] be compared with prediction and the reactivity status of the core can be periodically l l evaluated, and the occurrence of a discrepancy would be thoroughly investigated i and evaluated. The methods employed in calculating the reactivity of the core vs.  ;

bumup, and the reactivity worth of boron vs. burnup, are given in the FSAR. I i

Amendment No. 19, 48.'65. 91 3.15-1

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, , Table 4.2-1  ;

Minimum Frequencies for Sampling Tests l Test Frequency

1. Reactor Coolant Gross Activity Determination . At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. ,

Samples ,

Isotopic Analysis for DOSE E@IVALENT I 131 concentra-tion. 1 per 14 days i Radiochemical for 8 -

Determination 1 per 6 months * *

, Isotopic Analysis for Iodine, Until the spec 111c activity of

. including I 131,1 133, and the primary coolant system is

[ I 135 restored within the limits.

j .- once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever the.

DOSE EWIVALENT I-131 exceeds 1.0 pC1/ gram, and j One Sample between 2 and 6 4 hours following a THERMAL 2

POWER change exceeding 15 percent of the RATED THERMAL  :

POWER within a one hour ,

period.

Chemistry (chloride 3 times per week.

and fluoride)

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Hydrogen Weekly *  !

0xygen Prior to heatup above 250 F, and 3 times per week when above 250"F.

Process Radiation Monitor Continuous * *

2. Reactor Coolant Boron Boron Concentration H (Power Ops & Hot Standby)

D (Hot Shutdown Transthermal.

Cold Shutdown, Refueling Shutdown & Refueling Ops)

3. Refueling Water Tank Boron Concentration Monthly *
  • Water Sample Amendment No. 38 d 1 4.2 2