ML17326B595
| ML17326B595 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/07/1989 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17326B594 | List: |
| References | |
| NUDOCS 8904210212 | |
| Download: ML17326B595 (10) | |
Text
- 'REACTOR COOLANT SYSTEM 3 4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the reactor coolant shall be limited to:
a.
Less than or equal to 1 microCur'ie per gram DOSE EQUIVALENT I-131, and b.
Less than or equal to 100/E microCuries per gram of gross radioactivity.
APPLICABILITY:
MODES 1, 2, 3,
4 and 5
ACTION:
MODES 1, 2 and 3*
With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line 0 shown on Figure 3.4-1, be in HOT STANDBY with T less than 500 F
avg within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the specific activity of the reactor coolant greater than 100(E microCuries per gram, be in HOT STANDBY with T less than avg 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1, 2,
3, 4 and 5
a.
With the specific activity of the reactor coolant greater than 1
microCurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microCuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 unti,l the specific activity of the reactor coolant is restored to within its limits.
SURVEILLANCE RE UIREMENTS 4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.
- With T greater than or equal to 500 F.
0 avg COOK NUCLEAR PLANT - UNIT 1 I
PDR ADOCK 050003i5
~au 3/4 4-21
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COOK NUCLEAR PLANT - UNIT 1 3/4 4-22
ADMINISTRATIVECONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),
supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of stations, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their aspciated man rem exposure according to work and job functions, e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge
'easurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
b.
The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).
c.
Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.
d.
Information regarding any instances when the I-131 specific activity limit was exceeded.
1 A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
2 This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
D.
C.
COOK - UNIT 1 6-15 Amendment No.
. - REACTOR COOLANT SYSTEM BASES The surveillance requirements provide adequate assurance that concentrations
'in excess of the limits will be detected in sufficient time to take corrective action.
3 4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator.
tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.
The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters of the Cook Nuclear Plant site, such as site boundary location and meteorological conditions, were not considered in this evaluation.
The NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site.
This reevaluation may result in higher limits.
Reducing T
to less than 500 F prevents the release of activity should a
0 ave steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena.
A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
COOK NUCLEAR PLANT - UNIT 1 B 3/4 4-5
." REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:
a.
Less than or equal to 1 microCurie per gram DOSE EQUIVALENT I-131, and b.
Less than or equal to 100/E microCuries per gram of gross radioactivity.
APPLICABILITY:
MODES 1, 2,
3, 4 and 5
ACTION:
MODES 1, 2 and 3*
With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval for exceeding the limit line0 shown on Figure 3.4-1, be in HOT STANDBY with T less than 500 F
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b, With the specific activity of the reactor coolant greater than 100$ E microCuries per gram, be in HOT STANDBY with T less than avg 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1, 2, 3,
4 and 5
With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microCuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.
SURVEILLANCE RE UIREMENTS 4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4'-4,
- With T greater than or equal to 500 F.
0 avg COOK NUCLEAR PLANT - UNIT 2 3/4 4-20
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COOK NUCLEAR PLANT - UNIT 2 3/4 4-21
ADMINISTRATIVECONTROLS power operation),
supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTS
~
6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of stations, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their as~~elated man rem exposure according to work and job functions, e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
b.
The complete results of steam generator tube in'service inspections performed during the report period (reference Specification 4.4.5.5.b).
c.
Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.
d.
Information regarding any instances when the 1-131 specific activity limit was exceeded.
1 A single submittal may be made for a multiple unit station:
The submittal should combine those sections that are common to all units at the station.
2 This tabulation supplements the requirements of 20.407.of 10 CFR Part 20.
D.
C.
COOK - UNIT 2 6-15 Amendment No.
<r
.. REACTOR COOLANT SYSTEM BASES 3 4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.
The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters of the Cook Nuclear Plant site, such as site boundary location and meteorological conditions, were not considered in this evaluation.
The NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site.
This reevaluation may result in higher limits.
Reducing T
to less than 500 F prevents the release of activity should a
ave steam generator tube rupture since the saturation pressure of the primary coolant is below the liftpressure of the atmospheric steam relief valves.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena.
A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
COOK NUCLEAR PLANT - UNIT 2 V
B 3/4 4-5
4s 4
4