ML19256E498
| ML19256E498 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/18/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256E492 | List: |
| References | |
| NUDOCS 7911070532 | |
| Download: ML19256E498 (8) | |
Text
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APPENDIX INSTRUMENTATION
_ RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE.
AFPLICABILITY: As shown in Table 3.3-13.
ACT O'(:
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
SURVE*LLA' ICE REQUIREMENTS 4.'3.3.10 Each radioactive gaseous effluent monitoring instrurentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CEANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13 (per occupational exposure considerations and detector sensitivity in amsient radiation areas).
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' TABLE 3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORI!!G INSTROMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 10. EPICOR-II VENTILATION SYSTEM a.
Noble Gas Activity Monitor 1
37
~
b.
Iodine Sampler l
41 c.
Particulate Sampler 1
41 d.
Flow Rate Monitor 1
36 e.
Sampler Flow Rate Monitor 1
36 TABLE NOTATION
- At all times.
ACTION 36 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
K TION 37 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 41 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 deys provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
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RADI0 ACTIVE GASEOUS EFFLUENT !C:ilTORING liiSTRU".ENTATION SURVEILLANCE REOUIREMENTS CHANNEL CHAriNEL SOURCE CHANNEL FUNCTIONAL ItiSTRU:'ENT CHECK CHECK CALIBRATICN TEST 10.
EPICOR-II VENTILATION SYSTEM a.
!;oble Gas Activity V.onitor D
M R(3)
()(2) b.
Iodine Sampler W
N.A.
N.~.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Flow Rate Monitor D
N.A.
SA SA e.
Sampler Flow Rate Monitor D
N.A.
SA SA n
g gr} g TABLE NOTATION (2)
Ch.".':EL FUtiCTIO :AL TEST shall also de.onstrate that contro? room dar ann;nication occurs if any of the followin; conditfor exist:
1.
Instrur.ent indicates neasured levels above the alarm setpoint.
2.
Circuit failure (alarm function only).
3.
Instrument indicates a downside f ailure (alarm functior only).
4.
Instrument controls rot set in operate mode or the switch position administrat fely monitored and controlled.
(3)
The initial CHA!;::EL CALIERATIO! shall be performed using oce or ore of the r6ference standards certified by the.*;ational Eureau of 5ta.dards or using standards that have been obtained fro suppliers that participate in reasurtz.ent assurance activities with ~.35.
These standards shall permit calibrating the system over its irtended range of energy and measurement range.
For subsecuent C ANiiEL CALIBRATION sources that have been related to the initial calibra-tion shall be used.
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APPENDIX B TECHNICAL SPECIFICATIONS GASEOUS EFFLUENTS 2.1. 2.J The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be detemined to be within the limits calculated in accordance with this specification by obtaining representativa samples and perfoming analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.
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TAntf_?el_1 ItA010 ACTIVE GASlullS WAS10 SAMPLING AND ANALYSIS PROGRA't, Minimum lower I smil of Gaseous 1(clease Sampling An.ily is Type of Ac.livity llelectinn (llp)
!ype Irettuency treiluency Analysis (l:Ci/ mild I
9 lx10 C. Epicure 11 Ventilation H"
M Principal Gauaa rmitters Grah Sample l
11 - 3 1x10' 8
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e.e. w.e _
e.
. ame-
-e_-_e
-._e e___
= _..
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i -
-y=+=-e e
U1 I
i(co)
(c 2) a Ei'P-)
N M
WE'e)
V-m LTP)
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- s5D 1
TABLE 2.1-1 (Continued)
TABLE NOTATION a.
The LLD is the smallest concentration of radioactive material in a sarple that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
EV2 2 Y
exp ( Act)
Where LLD is the lower limit of detection as defined above (as picoeurie per unit mars or volume),
sb is the standard deviation of the background counting rate o'r of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 is the number of transformatio, t per minute per picocurie, Y is the fractional radiochemi:1.1 yield hhen applicable),
A is the radioactive decay constant for the particular radionucl'de, and st is the elapsed time
- tween midpoint of sample collection and time of counting (f r plut effluents, not environmental samples',.
The value of sb used in the calculation of the LLD for a dete:ti:n system shall be based on the actual observed varirnce of the bace.-
ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically pre-dicted variance.
In calculating the LLD for a radionuclide deter-mined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and t.t shall be used in the calculation.
The background count rate is calculated from the background counts that are determined to be with ! one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radio-nuclide.
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T ABL E__2.1 -1 (Continued)
TABLE NOTATION e.
Tritium giab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, g.
The principal gamma emitters for which the LLD specifi:ation applies exclusively are the following radionuclides:
Kr-87, Kr-38, Xe-133.
Xe-133m, Xe-135, and Xe-138 for gaseous emissicns and.t-54, Fe-59, t
Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Cs-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclifes are to be detected and reported.
Other peaks which are measurable end 'd--tiff-b!c, !?;;ther w'th the :5 te r.uc1' des, shell also be ide,-
tified and reported.
Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and small not be reported as being present at the LLD level for that nu:lide. The "less than" values shall not be used in the requir'ed dose calculations.
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BASES 3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and centrol, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criterion 64 of Appendix A to 10 CFR Part 50.
2.1.2 GASEOUS EFFLUENTS This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be with-in the annual dose limits of 10 CFR Part 20 for unrestricted areas.
The ar.naal dose limits are the doses associated with the concentrations of 10 CFR Fart 20, Appendix B, Table II, Column 1.
These limits orovide reasonable assuran:e that radioactive naterial discharged in gaseous effluents will not result in the axposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.105(b) ).
For individuals who may at times be within the site boundary, tr.e occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above tFat for the site bound ary.
The specified release rate limits restrict, at all times, the corresponding ga:va and beta dose rates above background to an individual at or beyond the site boundary to less than or ecual to 500 mrem /yr to the tetal body or to less than or equal to 3000 mren/yr to the skin.
These re-lease rate limits also restrict, at all times, the correspcmding thyroid dcse rate above background to an infant via the cow-milk in' ant pathway to less than or equal to 1500 mrem /yr for the nearest cow to the plant.
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UNITED STATES NUCLEAR REGULATORY COMMISSION NEGATIVE DECLARATION REGARDING USE OF EPICOR-II SYSTEM FOR DECONTAMINATION OF INTERMEDIATE LEVEL MDI0 ACTIVE WASTE WATER AT THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 DOCKET NO. 50-320 The U. S. Nuclear Regulatory Comission has been considering the use of an EPICOR-II ion exchange decontamination system to decontaminate the intermediate level radioactive waste water which has been held in tanks at Three Mile Island since tne accident at the facility on March _28,1979.
The Comission's Office of Nuclear Reactor Regulation (NRR) prepared an Environmental Assessment, "Use of EPICOR-II at Three Mile Island, Unit 2," N'JREG-0591, which concluded that the use of this system will not sig-nificantly affect the quality of the human environment, and therefore an Environmental Impact Statement need not be prepared. This Assessment was issued for public comment on August 20,1979 (44 FR 48829). Coments were received, analyzed and presented to the Comission. Based on the Comission's review of the facts and analysis in NRR's Environmental Assessment and written and oral discussion of the coments, the Comission has determined in its Mertorandum and Order, dated October 16, 1979, that the operation of EPICOR-II and the attendant' solidification and handling of EPICOR-II resins will not have a significant effect on the environment.
Thus, in accordance with the fore-going finding of the Comission, no Environmental Impact Statement for the prepcsed action will be prepared.
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o The Environmental Assessment (NUREG-0591) and the Contnission's Meso-rardum and Order issued October 16, 1979, are available for public inspectior at the Connission's Public Document Room,1717 H Street, N. W., Washington, D. C., and at the Three Mile Island Unit No. 2 Local Public Document Room in the Government Publications Section, State Librtry of Pennsylvania, Edu-
' :aticn Building, Ccmonwealth and Walnut Streets, Harrisburg, Pennsylvania.
Copies may be :btained upon request addressed to the U. S. Nuclear Re;u'ator; Comission, Washington, D. C.
20555, Attention:
Richard Vollmer, Director.
THI-2 Support, NRR.
FOR THE NUCLEAR REGULATORY COMMISSION
[
Harold R. Denton, Director Office of Nuclear Reactor Regulatter:
Catec at Bett esda, Maryland this 7 3-h day of October,1979
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