ML20151H523
| ML20151H523 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/26/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151H525 | List: |
| References | |
| TAC-8132, NUDOCS 8305040626 | |
| Download: ML20151H523 (8) | |
Text
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INSTRUMENTATION h
RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRLS!ENTATION h
1 LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid ef fluent monitoring instrumantation Jj channels shown in Table 3.3-12 shall be OPERA 3LE with their alarm / trip setpoints set to ensure that the li=its of Specifica-cion 3.11.1.1 a re not exceeded. The alar'./ trip setpoints of the radiation monitoring channels shall be determined in accordance with the Offsit 7ose Calculation Manual (ODCM).
APPLICA3!LITf:
Duri'ng releases through the flow path.
ACTION:
a.
k'ith a radioactive liquid effluent conitoring instrucentation channel alar =/ trip se point less conservative than required by the above specification, i: mediately suspeed the release of radioactive liquid effluents conitored by the af fected channel or correct the alarm / trip setpoint.
b.
With one or core radioactive liquid ef fluent =enitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-12 or conservativ=ly reduce the alarm setpoint.
Exe rt a best effort to return the channel to l
operable status within 30 days, and if unsuccessful, explain in the next Se:1-Annual Effluent Release Report
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why the inoperability was not corrected in a ti=ely canner.
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c.
The provisions of Specifications 3.0.3, 6.9.1.9 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS p
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j 4.3.3.9.l Each radioactive liquid ef f luent tenitoring instru entation
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channel shall be deconstrated GPEFA3LE by perfor=ance of the CHANNEL i
y CHECK, SOURCE CHECK, CHANNEL CALIERATION and CHANNEL FUNCTIONAL TEST
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cperations at the f requenties shown f., Table 4.3-12.
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EIAVER 7 ALLEY - UNIT 1 3/4 3-53 k,endnent No. 65 T
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E 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION d
j 3.11.1.1 The concentration of radioactive caterial released from the site (See Figure 5.1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix 3, Table II, g
Colu=n 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 " pC1/=1 total activity.
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APPLICABILITY:
At all times.
1 ACTION:
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a.
With the concentration of radioactive material released f rom the site to unrestricted areas exceeding the above limits; i==ediately restore concentration within the above limits.
I b.
The provisions of Specifications 3.0.3, 6.9.1.9 and 3.0.4 are not applicable.
l c.
Pro =pt notification pursuant to specification 6.9.1.5 is l
required.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sa: pled and analyzed I
f according to the sa=pling and analysis program of Table 4.11-1*.
I 4.11.1.1.2 The results of radioactive analysis shall be used in f
accordance with tha methods of the ODCM to assure that the concentration
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at the point of release are maintained within :he li=its of specifica-tion 3.11.1.1.
i Radioactive liquia discharges are normally via batch codes.
l Turbine Building Drains shall be car.itored as specified in i
Section 4.11.1.1.3.
e 3E.cn.R VALLEY - tsIT 3/4 11-1 Arendment "o.
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SURVEILLANCE RECUIR&.ENTS._(Continued) 4.lg.l.1.3 k* hen the activity of the secondary coolant is greater than 10- MC1/=1 gross, grab sa=ples shall be taken for each sump discharge from the turbine building and che=ical waste su=ps.
The sa=ple shall
~7 be analyzed for gross activity at a sensitivity of at least 10 u C1/=1 and recorded in plant records. k'ater volu=e discharged shall oe estimated fro = the nu=ber of pu=p operations unless alternate flow or volu=e instrumentation is provided.
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?.0:0 ACTIVE EFFLUENTS LOSE (Continued) i SURVEILD_vE REQUIR..ENTS 4.11.1.2.1 Dose Calculations. Cu:ulative dase. contributions f rom liquid effluents shall be determined in accordance d.th the ODCP.
at least once per 31 days.
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RADI0 ACTIVE EFFLUENTS LIOUID HOLDUP TA_N_K__S
. LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity' of radioactive caterial contained in each of the following tanks shall be limited to 5010 curies, excluding j
tritium and dissolved or entrained noble gases.
a.
BR-TK-6A (Primary Water Storage Tank)
N b.
BR-TK-6B (Pricary Water Storage Ta' k) n i,
c.
LW-TK-7A (Stea: Generator Drain Tank) d.
LW-TK-7B (Steam Generator Drain Tank) l e.
Miscellaneous temporary cutside radioactive liquid storage tanks.
APPLICABILITY : At all times.
ACTICN:
a.
With the quantity of radioactive =aterial in any of the above listed tanks exceeding the above li=it, 12:ediately suspend all additions of radioactive =aterial to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents tr. within the limit.
l b.
The provisions of Specifications 3.0.3, and 3.0.4 are' not applicable.
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SURVEILLANCE REOUIREMENTS i
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4.11.1.4.1 The quantity of radioactive caterial contained in each of the above listed tanks shall be deter =ined to be within the above 5
limit by analyzing a representative sample of the tank's contents f'
at least once per 7 days when radioactive =aterials are being added to the tank.
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. R.CICACTIVE EFFLUENTS 1
GAS STORAGE TANKS it
. LIMITING CONDITION FOR OPERATION f
3.11.2.5 The quantity of radioactivity contained in each gas storage p
tank shall be limited tog 52000 curies noble gases (considered as Xe-133).
APPLICABILITY: At all times.
3 ACTION:
With the quantity of radioactive =sterial in any gas storage tank.
a.
exceeding the above limit, i==ediately suspend all additions of radioactive caterial to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b.
The provisions of Specifications 3.0.3, and 3.0.4 are not ap plicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 The quantity of radioactive =aterial contained in each gas k
storage tank shall be determined to be within the above limit at least s ;
once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive =aterials are being added to the y l tank when the Waste Gas Decay Tank Monitor, (RM-GW-101) is not ope rab le.
i 4.11.2.5.2 The Waste Gas Decay Tank Monitor (RM-GW-101) operability
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shall be determined i~n accordance with Table 4.3-13 unless sa=pling pursuant to 4.11.2.5.1 is being conducted.
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i BEAVER VALLEY - UNIT 1 3/4 11-20 Amendment No. 66 l
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RADICLCCICA' ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISCN PROGRAM i
L LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.
I APPLICA3ILITY : At all times.
ACTICN:
ith analyses not being performed as required above, a.
report the corrective actions taken to prevent a recur-rence to the Commission in the Annual Radiological Environmental Report.
b.
The provisions of Specification 3.0.3, 6.9.1.9 and 3.0.4 are not applicable.
r SURVEILLANCE REOUIREMENTS T
4.12.3.1 The results of ~ analyses perfor=ed as part of the above required Interlaboratory Comparison Progra shall be included in the Annual Radiological Environcental Report.
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BEAVER VALLEY - UNIT 1 3/4 12-12 Amendment No. 6t p
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- _l *:4CTIVE EFFLUENTS 7
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BASES Fi for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, p
Colu=n 1.
These limits provide reasonable assurance that radioactive caterial discharged in gaseous ef fluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrationssexceeding the limits specified in Appandix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106 (b)).
For individuals who =ay at ti=es be within the site boundary, the occupancy of the individual will be suf ficiently low to co=pensate for any increase in the atmospheric dif fusion factor above that for 'the site boundary.
The specified release rate li=its restrict, at all ti=es, the corresponding ga==a and beta dose rates above background to an individual at or beyond the exclusion area boundary to ;!500 =re=/ year to the total body or to 13,000 =re:/ year to the skin. These release rate li=its also restrict, at all ti=es, the corresponding thyroid dose rate above background to an infant via the cow-=11k-infant pathway to j: 1,500
=re:/ year for the nearest cow to the plant.
This specification applies to the release of gaseous effluents fro: 3eaver Valley Power Station, Unit No. 1.
For units with shared radwaste treatment syste=, the gaseous effluents fro: the shared syste=
are proportioned a=ong the units sharing that system.
3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to i=ple=ent the require =ents of Sections II.B. III.A and IV.A of Appendix I, 10 CFR Part 50.
The L1=iting Condition for Operation i=ple=ents the guides set forth in Section II.B of Appendix I.
The ACTION statements provide the required operating flexibility and at th t sa=e ti=e i=ple=ent the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive =aterial in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Require =ents i=plement the require =ents in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on =odels and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially under-e s ti=a t e d. The dose calculations established in the CDCM for calculating the doses due to the actual release rates of radioactive noble gases in h
gaseous ef fluents are consistent with the =ethodology provided in d
Re3ulatory Guide 1.109, " Calculation of Annual Doses to Man fro:
y Routine Releases of Reactor Effluents for the Purpose of Evaluating R*
Co=pliance with 10 CFR Part 50, Appendix I,"
Revision 1, October, 1977 and Regulatory Guide 1.111, " Methods for Esti=ating At=ospheric b
LjL 3EAVER VALLEY - UNIT 1 B 3/4 11-3 Spendment "o.
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