ML19210D582
| ML19210D582 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/14/1979 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19210D581 | List: |
| References | |
| FOIA-80-347, FOIA-80-548, FOIA-80-550 NUDOCS 7911270340 | |
| Download: ML19210D582 (5) | |
Text
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ENCLOSURE I Dresden Unit i Revised Technical Specification Pages Revised Pages 87 91 98 102 New Page 91a
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1399 1 N R11a43Y
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4.7 LlHITING CONDITION FOR OPERATION
- 4. 7 SURVEILLANCE REQUIREMENT NOTE: During the outage beginning November,1978, d.
The test duration shall not be less to decontaminate the primary system, the than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for integrated leak rate requirenent of 3.7. A.1 is not applicable mcasurenents, but shall be extended to when all fuel is removed from the reactor a sufficient period of time to verify, and the containment.
by measuring the quantity of air required to return to the starting point (or other methods of equivalent sensitivity), the validity and accuracy of the leak rate resul ts.
e.
Acceptance Criteria for IPCLT (1) The maximum allowable leak rate L
shall not exceed 0.4 weight per-c8n,t of the contained air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a pressure of 20 psig.
(2) The allowable operational leak rate, r$9u(20), which shall be met prior to L
,a nption of power operation following sm) s;)
a test (either as measured or following repairs and retest) shall not exceed 0.75 L,
P ca C0) f.
Corrective Action for IPCLT If leak repairs are necessary to meet the allowable operational leak rate, the inte-grated leak rate test need not be repeated provided local leakage measurements are conducted and the leak rate differences prior to and after repairs, when correc-ted to the test pressure and 87
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t Bases:
3.7 A.
Primary Containment - The integrity of the B.
Primary Containment Isolating Valves primary containment and operation of the Isolation valves are provided on lines pene-energency core spray system in canbination, trating the primary containment and open to limit the off-site doses to values less than free space of the containment.
Closure of those in 10 CFR 100 in the event of a break one of the valves in each line would be in the primary system piping.
Thus, containment sufficient to maintain containmant integrity, integrity is specified whenever the potential Automatic initiation is required to minimize,,
for violation of the primary reactor system the potential leakage paths from the contain-integrity exists.
Concern about such a ment in the event of a loss of coolant accident.
violation exists whenever the reactor is critical and above atmospheric pressure.
In addition, even during periods when the reactor is shutdown, primary containnent integrity is required to ensure fission products would be contained in the event of a refueling accident or large spill of radioactive water frem the primary system.
If no work is being done in the primary containment which has the potential for release of radioactivity, containnent integrity is not required.
With all fuel removed from the reactor, any volatile activities which could be released during the chemical cleaning outage beginning in November,1978, would be minimal.
No rmal sphere ventilation flow would ensure that air-borne activity would be conveyed to the stack, and the stack gas monitor will be in service.
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Chemical cleaning procedures will be established
- jj for dunping the cleaning solution to receiving
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tanks in case of significant leakage from the
~ f) primary system and to ensure that any leakage of liquids to the sphere will be contained within
.x) the sphere. Therefore, based on the above,
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primary containment integrity is not required for the November, 1978 chemical cleaning outage when no fuel is in the containment.
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The primary containment has a design temperature and pressure of 325'F and 29.5 psig, respectively.
In addition, the containment was designed for a maximum leakage of 0.5% (by weight) per day at 37 psi.
For the largest break, the paximum containment pressure is approximately L ' ~ '
i 20 psig which is less than design pressure I
i and containment leakage should be less than O.4%/ day, which is specified at 20 psig.
The allowable leakage rate at 20 psig is calculated from the containment design leakage rate of 0.5% (by weight) per day at 37 psig by using the following equation:
LT
- La.( t/pa)1/2 O
mmA wO
%Q I
91a
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3_. 8 LIMITING CONDITION FOR opt inTION 4.8 SURVEILLANCE REOUIREMENT 3.
Two independent samples from a tank 3.
The performance and results of independent shall be taken and analyzed and the samples and valve checks shall be logged.
valve line-up checked prior to dis-charge of liquid effluents from that tank.
4.
If the limits of 3.8.C cannot be met, radioactive liquid effluents shall not be released.
D.
Radioactive Waste Storage D.
Radioactive Waste Storage The maximum amount of radioactivity in A sample from each of the above-grade liquid liquid storage in all Dresden Stations waste tanks shall be taken, analyzed, and above grade tanks shall not exceed 90 recorded every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If no additions to a curies.
If these conditions cannot be met tank have been made since the last sample, the the stored liquid shall be recycled within tank need not be sampled until the next addition.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to below grade tanks.
All tanks located within the seismic portion of the Chemical Cleaning Building are not considered above grade storage.
E.
General E.
General It is expected that releases of radioactive 1.
Operating procedures shall be developed and naterial in effluents will be kept at small used, and equipment which has been installed fractions of the limits specified in Section to maintain control over radioactive materials 20.106 of 10 CFR Part 20.
At the same time in gaseous and liquid effluents produced the licensee is permitted the flexibility during normal reactor operations, including of operation, compa tible with considerations expected operational occurrences, shall be of health and safety, to assure that the maintained and used, to keep levels of public is provided a dependable source of radioactive material in effluents released power even under unusual operat.nc, conditions to unrestricted areas as low as is reasonably
>4 which may temporarily result in releases achievable.
The environmental monitoring
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higher than such small fractions, but still program given in Table 4.8.1 shall be conducted.
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The assumptions used by the AEC staff for D.
Radioactive Liquid Waste Storage - The maixmum these calculations were:
(1) On-site
' gross radioactivity in liquid storage in the meteorological data were used for the specified tanks has been limited on the basis most critical 22.5 degree sector.
(2)'No of an accidental spill from all stated building wake credit was used.
(3) To tanks due to a seismic event great enough
- consider possible reconcentration effects to damage them.
The Chemical Cleaning Building a reduction factor of 700 was applied to is seismically qualified and designed to allow for the milk production and consump-contain a simultaneous spill from all the tion mode of uptake.
contaminated liquid storage tanks housed within.
Assuming a low river flow of 3100 ft3/sec, B.
Mechanical Vacuum Puap-The purpose of iso-a day period over which the radioactive liquid lating the mechanical vacuum pump line is wastes are diluted in the river, and consumption to limit release of activity from the main of J e water by individuals at standard man condenser.
During an accident, fission consumption rate (3000 ml/ day), the single intake products would be transported from the by an individual would not exceed one-third the yearly intake allowable by 10 C unidentified radioisotopes (1 x 10 JR 20 foruCi/ml).
reactor through the main steamline to the main condenser.
The factor of 3 was applied to 10 CFR 20 limits C.
Liquid Effluents - Liquid effluent release as recommended for situations in which population rate will be controlled in terms of the groups could be exposed.
concentration in the discharge canal.
In the case of unidentified nixtures, such The sampling frequency has been established so concentration limit is based on assumption that if the maximum amount of gross radioactivity that the entire content is made up of the is exceeded, action can be taken to reduce the most restrictive isotope in accordance with radioactivity to a level below the specified 10 CFR 20.
Such a limit assures that even limit.
if a person obtained all of his daily water intake from such a source, the E.
Environmental Radiological Monitoring Program -
resultant dose would not exceed that The environmental radiological monitoring specified in 10 CFR 20.
Since no such program is designed to:
use of the discharge canal is made and considerable natural dilution occurs prior 1.
Provide data on measurable levels of to any location where such doses could radiation and radioactive materials in occur, this assures that of f-side doses the environment in order to evaluate
'4 from this source will be far less than the calculational models used to relate
'4) the limits specified in 10 CFR 20.
the quantities of radioactive material
'43 released in effluents to the radiation doses received by individuals via the
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principal pathways of exposure; YS 102