ML20082H504
| ML20082H504 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/22/1983 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20082H490 | List: |
| References | |
| TAC-53476, TAC-53477, NUDOCS 8312010183 | |
| Download: ML20082H504 (6) | |
Text
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LIMITI?G CCNDITIONS FOR OPERATION SURVEILINCE RfDUIREMENTS 3.6.F Reactor Coolant Chemistry 4.6.F Reactor Coolant chemistry
- 1. Radioactivity
- 1. Radioactivity Whenever the reactor is critical
- a. During equilibrium power the limits on activity concen-operation an isotopic trations in the reactor coolant analysis, including shall not exceed the equilibrium quantitative measurements value of 0.2 pCi/gm of dose l
for at least I-131, I-132, equivalent
I-133, and I-135 shall be performed nonthly on a If activity concentration > 0.2 l
coolant liquid sample.
pCi/gm dose equivalent I-131 but 14.0 pCi/gm, operation may con-
- b. During equilibrium power tinue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided operation an isotopic that operation onder these condi-analysis, including tions shall not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> quantitative measurements in any consecutive 12 month period.
for at least Xe-133 and Xe-Should the total operating time of 135 shall be performed a specific activity
>0.2 pC1/gm monthly on a steam jet air dose equivalent I-131 exceed 500 ejector off-gas sample.
hours in any consecutive 6 month period, the licensee shall report
- c. Additional coolant samples the ntaber of hours of operation shall be taken whenever the above this limit to the NBC within reactor coolant dose equiva-30 days.
lent I-131 concentration exceeds 0.2 p Ci/gm and any i of the following conditions If activity concentration
>0.2 are met:
p Ci/gm 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 con-
- 1) During startup tinuous time interval, or
>4.0 I
p Ci/gm, be in at least HOP SHITT-
- 2) Following a power change DOWN with the main steam line exceedire 15% of rated isolation valves closed within 12 l
thermal power in less hours.
than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (net charge averaged for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- That I-131 concentration which alone would
- 3) The off-gas level, at produce the same thyroid dose as the the SJAE, increases by quantity and iodine mixture actually l
more than 10,000 p Ci/sec present.
in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at release rate 1 75,000 pCi/sec, or
- 4) The off-gas level at the S7AE, increases by morc-than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at release rate > 75,000 pCi/sec.
- 5) Whenever the reactor coolant dose equivalent 8312010183 831122 PDR ADOCK 05000321 I-131 concentration ex-P ceeds 4.0 pCi/gm.
l PDR 3.6-4
l LIMITIN3 031DITIOf6 FOR OPERATION SURVEILIAICE REQUIREMENTS
'Ihe first additional coolant sample shall be taken between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> followirg the change in thermal power of off-gas level.
Additional coolant liquid sanples shall be taken at 4-hour intervals for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or until a stable iodine concentra-tion below the limiting value of 4.0 u Ci/gm is l
established.
An isotopic analysis shall be performed for each
- sanple, and quantitative measurements made to determine the dose equivalent I-131 concen-tration If' the total iodine activity. of the sample is below 0.2 PCi/gm, an isotopic l
analysis to determine equivalent. I-131 is not required.
All data obtained, from normal; and any additional samples shall be included in the annual report.
If the limits of the specifi-cation are
-exceeded, a
report: shall be made to the Directorate of Licensing within 30 days.
l HA'ICH UNIT 2 3.6-5
BASES EDR LIbi1TItG CONDITIONS FOR OPERATION AND SURVEILINCE REQUIRD4EN1'S 3.6 Recirculation Punp Start The coolant in the bottom of the vessel is at a lower temperature than that in the upper regions of the vessel when there is not recirculation flow.
The colder water is forced up when recirculation pumps are started. 'Ihis will not result in stresses which exceed ASME Boiler and Pressure Vesr,el Code,Section III limits when the temperature differential is not greater than 145 F.
F.
Reactor Coolant Chemistry The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid and whole body doses resulting from a main steam line failure outside the containment dtring steady state operction will not exceed small fractions of the dose guidelines of 10 CFR 100.
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, such as site boundary location and meteorological conditions, were not considered in this evaluation.
The maximum activity limit during a short term transient is established from consideration of a maximum iodine inhalation dose less than 300 rem.
The probability of a steam line break accident coincident with an iodine concentration transient is significantly lower than 9at of the accident alone, since operation of the reactor with iodine levels above the equilibrium value is limited to 10 percent of total operation.
Based upon a review of daily reactor water iodine concentrations at several sites that show the iodine transients during power generation are less than a factor of ten, sanpling frequencies have been established that vary with the iodine concentration in order to assure that the maximum coolant iodine concentrations are not exceeded.
t4aterials in the primary system in contact with the coolant are primarily stainless steel and Zircaloy.
The reactor water chemistry limits are established to prevent damage to these materials.
Limits are placed on conductivity and chloride concentrations. Conductivity is limited because it is continuously measured and gives an indication of abnormal conditions and the presence of unusual materials in the coolant.
Chloride limits are l
l specified to prevent stress corrosion cracking of the stainless steel.
According to test data, allowable chloride concentrations could be set several orders of magnitude above the established limit at the oxygen concentration
(.2.3];pm) experienced during power operation without causing significant failures.
Zircaloy does not exhibit similar stress corrosion failures.
However, there are some conditions under which the dissolved oxygen content of the reactor coolant water could be higher than
.2.3 ppm, such as reactor startup and hot standby.
During these periods, a more restrictive limit of 0.lppn has been established to assure that permissible chloride-oxygen combination are not exceeded.
During refueling when the reactor is depressurized Specification 3.6.F.2.c would apply.
Boiling occurs at higher steaming rates causing deaeration of the reactor water, thus maintaining oxygen concentration at low levels and assuring that the chloride-oxygen content is not such as would tend to induce stress corrosion cracking.
3.6-18
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i' ATTACitENT 3
. NRC DOCKET 50-3f,6 OPERATIPG LICENSE NT-5 EDWIN I. HA'IOi NIELEAR PIANT UNIT 2 DOSE EQUIVALENT IODINE- (DEI)
'Ihe propord change to' the 'mchnical Specification (Appendix A to the Operating License) would be incorporated as follows:
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r IEACTOR COGJNP SYSTEM
-LIMITIIG CQOITION PCR OPERATION (Continued)
- ACTION:
(
tinued) 2.
Withs.
a)
'INERMAL POGER changed by more than 15% of RATED THER%L POER in one
~
hour, or
" b)
'Ihe off-gas level,. at the
- SJAE, increased by more than 4
10,000. u Ci/sec.. in one hour at release rates less than 75,000 p Ci/sec.'or I
c)
'Ihe off-gasf level, at the SJAE, increased by more than 15% in one hour at release rates greater. than 75,000 u Ci/sec.,
.c perform the sampling and ~ analysis requirement of Item 4C of Table 4.4.5-1.
Prepare and subnit to the Canaission a Special Report pursuant to Specification 6 9.2 at least once per 92l days containing the results of the specific; activity ' analysis together =with the below additional information for each occurrence.-
i, Additional Information,
t 1.
Reactor power history starting.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to:
a)
The first sanple-in which the limit was exceeded, and/or
. b)
' The THERMAL POWER or off-gas level change.
I 2., ' Fuel butnup by core region, 3.
Cleanup flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to:
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a)
'Ibe first sanple in which the. limit was exceeded, and/or b)
The '1HERMAL POWER or' off-gas level dange.
l4.
Off-gas level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to:
t
'a)
The first sample in whid the limit was exceeded, and/or
/: b)
The THERMAL POWER or off-gas level change.
SURVEILIAICE REQUIREMiNTS 4.4.5 The specific activity of ' the reactor coolant shall be demonstrated to be
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'within the limits-by performance 'of the sanpling and analysis program of Table 4.4.5-1.,,;
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ATTACHMENP 4 NRC DOCKETS 50-321, 50-366 OPERATIN3 LICENSES DPR-57, NPF-5 EIWIN I. HA'ICH NUCLEAR PIANT UNITS 1 AND 2 DPIEMINATION OF AN CLASS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amerxtnent to Operating Licenses DPR-57 and NPF-5 and has determined that:
a)
The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)
The proposed amendment does not contain several complex issues, does not involve ACRS review, and does not require an environmental impact statement; c)
The proposed amendment does not involve a canplex issue or more than one environmental or safety issue; d)
'Ihe proposed amendment does involve a single safety or environmental issue, namely, charyjes to the Dose Equivalent Iodine limit.
e)
The proposed amendment is therefore a Class III amendment for Unit 2.
The submittal is an amendment to a previous subnittal for Unit 1 for which a check has already been subnitted.
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