ML19308A715
| ML19308A715 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/18/1979 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19308A711 | List: |
| References | |
| NUDOCS 7912040150 | |
| Download: ML19308A715 (8) | |
Text
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T APPENDIX I
INSTRUMENTATION RADI0 ACTIVE 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.
APPLICABILITY: As shown in Table 3.3-13.
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ACTION:
With less than the minimum number of radioactive gaseous effluent monitoring instrwnentation channels OPERABLE take the ACTION shown in Table 3.3-13.
SURVEILLANCE REQUIREMENTS 4.'3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13 (per occupational exposure considerations and detector sensitivity in ambient radiation areas).
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e TABLE 3.3-13 RADIDACTIVE GASEOUS EFFLUENT MONITORING INST 40 MENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 10.
EPICOR-Il VENTILATION SYSTEM a.
Noble Gas Activity Monitor 1
37 41 b.
Iodine Sampler 1
41 c.
Particulate Sampler I
36 d.
Flow Rate Monitor 1
36 e.
Sampler Flow Rate Monitor 1
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 />.
ACTION 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 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
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i TA_BLE 4.3-13 RADIOACTIVE GASEOUS EFFLUENT ":"ITORING INSTRUENTATION SJRVEILLANCE REQU:REMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALISD.ATION TEST 10.
EPICOP.-Il VENTILATION SYSTEM a.
"oble Gas Activity Monitor D
M R(3)
O(2) b.
lodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Flow Rate Monitor D
N.A.
SA SA e.
Sar.pler Flow Rate Monitor 0
N.A.
SA SA TABLE NOTATION l
i (2)
C - 4*.':EL FUNCT10NAL TEST shall also de onstrate that control room alar annsnication occurs if any of the follotting condition exist:
1.
In s trur.en t incicates neasured levels above the alarm setpoint.
2.
Circuit failure (alarm function only).
3.
Instrument indicates a dounside failure (alarm function only).
4 Instrument controls not set in operate node or the switch position administratively monitored and controlled.
(3) The initial CHANNEL CALIERATIO" shall be perfor ed using one or are of the reference standards certified by the.';ational Bureau of 5: 3.dards or using standards that have been obtained from suppliers that participate in. easuri::ent assurance activities with "SS.
These standards shall permit calibrating the system over its intended ca6;e of energy and maasurement range.
For subsecuent CHANNEL C'L:50.AT10N sources that have been related to the initial.calibra-ti:n shall be used.
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o o APPENDIX 8 TECHNICAL SPECIFICATIONS GASEOUS EFFLUENTS 2.1.2.J The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits calculated in accordance with this specification by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.
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TABLE _2.1-1 RAD 10 ACTIVE GASEOUS WASIE 5AMPLING AND ANALYSIS PROGRA'l Lower Limit of l
Minimum l
Gaseous Release Sampling Analysis Type of Activity Octection (LLD)
Iype l'requency Irequency Analysis (PCi/ml)J l
9 lx10' C. Epicore 11 Ventilation M'
N Principal Gar.aaa Imitters Grab Sample j
l H-3 lx10' i
t U1 e
e 9
9 O
e o
TABLE 2.1-1 (Continued)
TABLE NOTATION The LLD is'the sr.;allest concentration of radioactive material in a sarrple a.
that will be detected with 95% probability with Si probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 s LLD =
b E
V 2.22 Y
exp (-Mt)
Where LLD is the lower limit'of detection as defined above (as picocurie
~
per unit mass or volume),
is the standard deviation of the background counting rate or sbof 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 semple size (in units of mass or volume),
2.22 is the number of transformations per minute per dicocurie, Y is the fract onal radiochemical yield (when applica:le),
i A is the radi~.tive decay constant for the particular radionuclide, and
.st is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the back-ground counting rate or of the counting rate of the blank samsles (as appropriate) rather than on an unserified theoretically pre-dicted variance.
In calculating the LLD for a radionuclide deter-mined by ganma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the sanples.
Typical values of E, V, Y, and at shall be used in the calculation.
The background count rate is calculated fror.
the background counts that are deterWed to be witn one : M.
( ull-Width-at-Half "axim;m) energy band a: cut tre e argy of tr.e ga ma ray ::eak used for the cuantitative analysis #ce that ra:io-nuclide.
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t TABLE,_2.1-1 (Continued)
TABLE NOTATION Tritium grab samples shall be taken at least once per 7 days from the e.
ventilation exhaust from the spent fuel pool area.
g.
The principal gamma emitters for which the LLD specification applies i
exclusiyely are the following radionuclides:
Kr-87, Kr-88, Xe-133,
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Xe-133m, Xe-135, and Xe-138 for gaseous emissions and fin-54, Fe-59, 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 nuclides are to be detected and reported.
Other peaks which are measurable end 'd--tif':ble, *rgith'er t:ith the cre*/e nuclides, shell also be iden-tified and reported.
Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be i
reported as being present at the LLD level for that nuclide.
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 control, 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 annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B. Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations xceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106 (b ) ).
For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.
The specified release rate limits restrict, at all times, the corresponding gamma 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 total body or to less than or equal to 3000 cren/yr to the skin.
These re-lease rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an inf ant via the cow-milk-infant pathway to less than or equal to 1500 meem/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 RADI0 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 I
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 the 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 MilJ Island, Unit 2," NUREG-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 Commission's review of the facts and analysis in NRR's Environmental Assessment and written and oral discussion of the comments, the Commission has determined in its Memorandum 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 t
a significant effect on the envi:onment. Thus, in accordance with the fore-going finding of the Commission, no Environmental Impact Statement for the proc sed action will be prepared.
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1 The Environmental Assessment (NUREG-0591) and the Comission's Memo-randum and Order issued October 16, 1979, are available for public inspection at the Comission'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 I
in the Government Publications Section, State Library of Pennsylyania, Edu-cation Building, Comonwealtri and Walnut Streets, Harrisburg, Pennsylvania.
Copies may be obtained upon request addressed to the U. S. Nuclear Regulatory Comission, Washington, D. C.
'20555, Attention:
Richard Vollmer, Director, TMI-2 Support, NRR.
FOR THE NUCLEAR REGULATORY COMMISSION
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Harold R. Denton, Director Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 18th day of October,1979
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