ML20107J281
| ML20107J281 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/04/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20107J286 | List: |
| References | |
| TAC 53476, TAC 53477, DPR-57-A-106, NPF-05-A-044 NUDOCS 8502270455 | |
| Download: ML20107J281 (12) | |
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~g UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 7;
j WASHINGTON, D. C. 20555 s...../
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 06 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated May 31, 1983, as supplemented September 1 and November 22, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.~ The. facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Conunission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can oe conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
8502270455 850204 PDR ADOCK 05000321 p
PDR p
I
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.106, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION oh F. Stolz, Chief 0 rating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 4, 1985 t
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ATTACHMENT TO LICENSE AMENDMENT NO. 106 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 3.6-3 3.6-3*
3.6-4 3.6-4 3.6-5 3.6-5 3.6-18 3.6-18 Overleaf page included for document completeness.
1
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E. Recirculation Pump Start 4.6.E. Recirculation Pump Start The reactor recirculation pumps Prior to starting a recirculation shall not be started unless the pump, the reactor coolant temper-coolant temperatures between the atures in the dome and in the bottom head drain shall be com-dome and the bottom head drain pared and permanently recorded.
are within 145'F.
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1 4
I 3.6-3
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LIMITI!G CCNDITIONS FOR OPERATION SURVEILIAICE REQUIREMENIS 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 uCi/gm of dose l
for at least I-131, I-132, equivalent *. I-131.
I-133, and I-135 shal1~be performed. monthly on a If activity concentration > 0.2 coolant liquid sample, pCi/gm dose equivalent I-131 but
.54.0 uCi/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 under these condi-analysis, including tions shall nct 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 uCi/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 number of hours of operation shall be taken whenever_the above this limit to the NRC within reactor coolant dose equiva-30 days.
lent I-131 concentration
" exceeds 0.2 u Ci/gm and any
[
of the following conditions If activity concentration
>0.2 are met:
u 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 u Ci/gm, be in at least HOT SHUT-
- 2) Following a power change DOWN with the main steam line exceeding 15% of rated isolation valves closed within 12 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 change averaged for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- Tnat I-131 concentration which alone would
- 3) The off-gas level, at produce the same thyroid dose as the the S7AE, increases by quantity and iodine mixture actually l
more than 10,000 u 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 5-75,000 uCi/sec, or
- 4) The off-gas level at the S7AE, increases by more 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 uCL/sec.
- 5) Whenever the reactor coolant-dose equivalent I-131 concentration ex-ceeds 4.0 u Ci/gm.
l I
3.6-4 Amendment No.106
l-LD1ITI1G CCNDITIONS FOR OPEFATION SURVRTT.TAPCE REQUIIDENTS The 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 /> following the change in thermal power or off-gas level.
Additional coolant liquid samples 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 uCi/gm, an isotopic I
analysis to determine equivalent I-]31 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
re. port shall be made to the Directorate of Licensing within 30 days.
3.6-5 Amendment No.
106 4
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BASES EUR LIMITI?G CONDITIONS EUR OPERATION AND SURVEILINCE REQUIRENENTS t
E. Recirculation Pump Start i
The coolant in the bottom of the vessel is at a lower temperature than that in l
the upper regions of the vessel when there is not recirculation flow.
The colder water is forced up when recirculation pumps are started. This will not result in stresses which exceed ASME Boiler and Pressure Vessel 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 i
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 during steady state operation 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 i
evaluation by the NRC of typical site locations.
These values are censervative in that specific site parameters, such as site boundary.locatior i
and meteorological conditions, were not considered in this evaluation.
The maximum activity limit during a short term transient is established fron i
consideration of a maximum iodine inhalation dose less than 300 rem.
The i
probability of a steam line break accident coincident with an iodine concentration transient is significantly lower than that of.the accident
- alone, since operation of the reactor with iodine levels above the equilibrium 4
l 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 i
factor of ten, sanpling frequencies have been established that vary with the 4
iodine concentration in order to assure that the maximum coolant iodine concentrations are not exceeded.
Materials in t51e 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 1
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 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 ppm) experienced during power operation without causing significant i-N 1"rae H ecaloy 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
.2.3ppn, such as reactor startup and hot standby.
During these periods, a more restrictive limit of 0.lppm has been established to assure that permissible chloride-oxygen comoination 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 4
- oxygen concentration at low levels and assuring that the chloride-oxygen j
content is not such as would tend to induce stress corrosion cracking.
3.6-18 i
Amendment No i d6,>.
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UNITED STATES y
k NUCLEAR REGULATORY COMMISSION y
j WASHINGTON, D. C. 20555 8
g GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated May 31, 1983, as supplemented September 1 and November 22, 1983, complies with the. standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10.CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by i
l this amendment can be conducted without enc' angering the health and safety of the public, and (ii) that such activities will be conducted
[
in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
g v.
. l Technical Specifications The Technical Specifications contained-in Appendices A and B, as revised through Amendment No. 44, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
F THE NUCLEAR REG LATORY COMMISSION ohn F. Stolz, Chief /
9 ating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
February 4,1985 1
ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Remove Insert 3/4 4-11 3/4 4-11 4
k.
_EE;CIOR 001 ANT SYSTEM LIMITItG CONDITION FOR OPERATION (Continued)
ACTION:
(Continued) 2.
With:
a)
THERMAL PGiER changed by more than 15% of RATED THERMAL POWER in one hour, or b)
The off-gas
- level, at the
- SJAE, increased by more than 10,000 u Ci/sec.
in one hour at. release rates less than 75,000 p Ci/sec. or,
l c)
The off-gas level, at the S7AE/ increased by more than 15% in one hour at release rates greater than 75,000 u Ci/sec.,
perform the sampling and analysis requirement of Item 4C of Table 4.4.5-1.
Prepare and submit to the Commission a Special Report pursuant to Specification 6.9.2 at least once per 92 days containing the results 'of the specific activity analysis together with the below additional information for each occurrence.
Additional Information 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 sample in which the limit was exceeded, and/or b)
The THERMAL PONER or off-gas level change.
2.
Fuel burnup 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:
a)
The first sample in which the limit was exceeded, and/or b)
The THERMAL POWER or off-gas level change.
4.
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:
a)
The first sample in which the limit was exceeded, and/or b)
The THERMAL POWER or off-gas level change.
SURVEILIA?CE REDUIREMENTS 4.4.5 The specific activity of the reactor coolant shall be demonstrated to be within the limits by performance of the pampling and analysis program of Table 4.4.5-1.
HATCH - UNIT 2 3/4 4-11 Amendment flo. 44 l
)
TABLE 4.4.5-1 v,
PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM I
x M
OPERATIONAL CONDITIONS 9
TYPE OF MEASUREMENT SAMPLE AND ANALYSIS IN WHICH' SAMPLE '
s AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED E
f
- 1.
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 /> 1, 2, 3 2.
Isotopic Analysis for DOSE At least once per 31 days 1
EQUIVALENT I-131 Concentration 3.
Radiochemical for E At least once per 6 months
- 1 Determination 4.
Isotopic Analysis for Iodine a) At least once per 31 days 1
Including I-131, I-133 and I-135 R
b) At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 1,2,3,4 whenever the specific activity exceeds a limit.
c) At least one sample between 1, 2 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change;in THERMAL POWER or off-gas level.
5.
Isotopic Analysis of an Off-At, least once per 31 days 1
gas Sample Including Quantitative Measurements for at least Xe-133, Xe-135 and Kr-88
- Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
I Until the specific activity of the primary coolant system is restored to within its limits.
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