ML19246C616
| ML19246C616 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/20/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19246C606 | List: |
| References | |
| NUDOCS 7907260838 | |
| Download: ML19246C616 (6) | |
Text
e UNIT 2 424 313 7907260y3 8 f o-
LIMITING CONDITIONS FOR OPER/. TION SURVEILLANCE REQUIRLMENTS 3.8 RADIOACTIVE MATERIALS 4.8 RADIOACTIVE MATERIALS B.
Airborne Effluents B.
Airborne Effluents 1.
The cose rate at any 1.
The grcss 6, y and time in the unre-particulate activity of stricted areas (see gaseous wastes released Figure 4.8.B.1) due to to the environment shali radioactivity released be monitored and recorded:
in gaseous effluents from the site shall be limited to the follow-ing values:
a.
The dose rate a.
For eff]uent limit for noble streams having con-gases shall be tinuois monitoring d500 mrem /yr to capab 1Lty, the the total body acti'.ity and flow and 43000 rate shall be mrem /yr to the monitored and skin, and recorded to enable release rates of gross radioactivity to be determined on an hourly basis using instruments specified in Table 3.2.K.
b.
The dose rate b.
For effluent streams limit for all without continuous radiciodines for monitoring capa-all~ radioactive bility, the activity materials in shall be monitored particulate form, and recorded ar!
and for radio-the releases through nuclides other these streanF Snall than noble gases be controlled so with '.al f lives that the release greater than 8 rates from all days shall be streams are within 1500 mrem /yr tc the limits speci-any organ.
fied in 3.8.B 2.
If the limits of 2.
Radioactive gaseous waste
- 3. 8. IL 1 are excoaded, sampling and activity appropriete corrective analysis shall be performed action shall be ini-in accordance with Table tiated to bring the 4.8.B.
releases within limits.
Provide prompt notifi-cation to the NRC pursuant to section 4[f 6.7.2.a.
283
3.H.A LIQUID EFFLUENTS (cont'd) t 'ie guides of Appendix I he shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate patnways is unlikely to be sibstantially under-estimated. The equations specified la the ODCM for calculating the ooses due to the actual release
_ces of radioactive materials in liquid effluen*.s will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Dosos to Man fram Routine Releases of Reactor Effluents for the Purpose of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. NUREG-0133 provides methods far dose calculations consistent with Regulatory Guide, 1.109 and 1.113.
Specification 3.8.A.5 requites that the appropriate portions of the lieuid radwaste treatment systen be used when specified. This provides assurance that the releases of radf uactive materials in liquid effluents will be kept "as low as is reasonably achievable."
This specification implements thc requirements of 10 CFR Part 50.36a, General Desv;n Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Secti an 11.D of Appenaix ! to 10 CFR Part 50.
The specified limits governit.g the use of appropriate portions of the liquid radwaste treatment system were specified as a suitabic fraction of the guide set f orth in Section 11. A of Appendix 1, 10 CFR Part 50, for liquid effluents Specification 3.8.A.6 requires submittal of a special report if the limiting values of Specification 3.8.A.5 are exceeded and unexpected failures of non-redundant radwaste processing equipment halt vaste treatment.
Specificacion 1.8.A.7 requires that suitable equipment to control and monitor the releases of radioactive materials in the liquid effluents are operating during any period when these releases are taking place.
3.8 B AIRBON E EFFLUENTS Specificatian 3.8.B.1 is provided to ensure that t'ae dose rate at any-time at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for-unrestricted arean. The annual dose limits are the doses associated wi.th the concentrations of 10 CPR Part 20, Appe.. dix B, Table II.
These limite provide reasonable assurance that radioactive materi?1 discharged in gaseous effluents will not result in the exposure of an individaal in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the 11mfes 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 exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the ex-clusion area boundary.
424 315 290
6.0 A D HI N I ST RATI V E CONTROLS (9)
Performance of structures, systems, or components that requires remadial action or
'v cor ective measures.to prevent operation in a manner less conservative than assumed in the accidi.nt analyses in the sa f ety analysis report or technical specifications banes; or discovery during plant lif e of conditions not specifically considered in the safety analysis report or technical specifications that require ;enedial actica or corrective measures to pre 1ent the existence or development of an un t..' f e condi tion.
tote:
This item is ir nnded to provida for reporting of potentially genoric problems.
(10) The concentration of radioactive material in liquid efiluents released to unrestricted areas exceeds the concer.tra tions specified in 10 CFR Part 20, Appendix B, N ble II, Column 2 for radionuclides other than dissolved or entrained nobic gases.
Ccncentration of dissoged or entrained noble gaces exceeds 2 x10 p C1/ml total activity.
(11)
(a). The dose rate for noble gaset equals or exceeds 500 mrem /yr to the total body y
or 3000 mrem /yr to the skin.
(b). The dose rate for all radiciodines, for all radioactive materials in particular form, aed for radianuclides other than nob 1c gases with half lives greater than 8 days exceeds 1500 mrem /yr to any organ, y,
354 bfb
6.0 A 0fiI f M P,T RATI V E CO t;T R O L~>
V 3.
Renponsible for overall planning, establishment, and maintenance of critRai path schedule for restoration of units 1 and 2.
4 Coordination and approval of TVA's overall efforts in fire protection and prevention improvements, including design and installation of new systems and changes nececsary in fire fighting methods and techniques.
6.10 OFFSITE DOSE CALCULATION MANUAL (ODCM)
FUNCTION 6.10.1 The ODCM dee cibes the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip secpoints consistent with the applicable LCO's contained in these Technical Specifications.
(Methodologins and calcula.
tional procedures acceptable to the Commission are contained in NUREG-O'.33.)
6.10.2 Changes to the ODCM shall be made by either of the following methods:
A.
Licensee initiated changes:
1.
Shall be submitted to the Commissior by includion in the Monthly operating Report pursuant to Specification 6.9.1.10 within 90 days of the date the change (s) was made ef fective v
and shall contain:
Y a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
a determination the the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
documentation of the fact that the change has been reviewed and found acceptable by PORC.
2.
Shall become effective upon a date specified and agreed to by PORC following their review and acceptance of the change (s).
359 V
V A2A 317
6.10 0FF~'TE DOSE CALCULATION MANUAL (ODCM)
(Cont'd)
B.
Concission initiated changes:
1.
Shall be determined by the PORC to be applicable to the facility after consideration of facility design.
2.
The licensee shall provide the Commission with written notification of their determination of applicability including any necessary revisions to reficct facility design.
424 318 359a