ML19290A397
| ML19290A397 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/04/1976 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19290A396 | List: |
| References | |
| NUDOCS 7911060636 | |
| Download: ML19290A397 (5) | |
Text
hfetropolitan Edison Company (Met-Ed)
Three Mile Island Nuclear Generation Station Unit 1 (TMI-1)
Docket No. 50-289 Operating License No. DPR-50 Environmental Technical Specification Change Reauest No. 3h Replace Appendix B pages 15, 16, 23, and 24 with the enclosed replacement pages.
Page 16 is unchanged and is included only for convenience.
Reason For Proposed Change To comply with Appendix I 10 CFR 50 Environmental Analysis Justifying Change The proposed change incorporates the design criteria of Appendix I of 10 CFR 50 into present Environmental Technical Specifications. Studies performed recently at our direction by Nuclear Safety Associates, Inc.
show that the existing systems and related operating procedures provide adequate assurance that the release li=its of Appendix I are being, and will continue to be met.
This change vill not serve to change existing systems or related operating procedure. Therefore, it does not involve an unreviewed safety question nor does it cause undue risk to the health and safety of the public, nor an unreviewed environmental impact.
Cost-Benefit Analysis Surnorting Change There is no significant cost involved in this change.
1556 269
< 9 n os0536
2.0 LIMITING CONDITIONS FOR OPERATION Objective (cont'd) are as lov as reasonably achievable in conformance with 10 CFR Parts 50.3ha and 50 36a, and to ensure that these releases result in lll concentrations of radioactive materials in liquid effluents released to unrestricted areas within the limits specified in 10 CFR Part 20.
To ensure that the releases of radioactive material above back-ground to unrestricted areas are as lov as is reasonably achievable, the following design objectives as defined in Appendix I to 10 CFR Part 50.36a apply:
a.
The annual total quantity of all radioactive material above background that may be released to unrestricted areas should not result in an annual dose or dose commitment from liquid effluents for any individual in an unrestricted area from all pathways of exposure in excess of 3 millirems co the total body or 10 millirems to any organ.
llg b.
The annual average concentration of radioactive materials in the effluent from the Unit 1 Mechanical Draft Cooling Tower prior to dilution in the LJ7 Susquehanna River, excluding tritium and dissolved L37 gases, should not exceed 2 x 10-0 pCi/ml.
CN c.
The annual average concentration of tritium in p,
liquid vaste prior to dilution in the environment sq C3 should not exceed 5 x 10-6 pei/ni,
2.0 LIMITING CONDITIONS FOR OPERATION s
Specification Specification a.
The radioactivity release concentration in During release of liquid radioactive wastes from llh effluents from Unit 1 to the environment the Waste Evaporator Condensate Storage tank, the shall not exceed the values specified in following conditions shall Fw met.
~
10 CFR Part 20, Appendix B, for unrestricted areas.
a.
The liquid gross activity monito.r, KM-L6 or similar device, and recorder on the rad-b.
The total release of radioactive liquid waste effluent line shall be operable.
effluent from Unit 1 excluding tritium and noble gases, shall not exceed 10 curies b.
The liquid gross activity monitor RM-L6 or during any calendar quarter.
similar device shall be set to alarm and automatically close the waste discharge c.
The equipment installed in the liquid radio-valve WDL-V-257 prior to exceeding the active waste system shall be naintained and limits specified in 10 CFR Part 20, Appendix B shall be operated to process all radioactive for unrestricted areas.
liquid wastes prior to their discharge when the activity release rate will exceed 1.25 c.
Liquid waste radioactivity and flow rate ~
curies, excluding tritium and dissolved from the waste evaporator condensate storage glg gases during any calendar quarter.
tanks shall be continuously monitored and recorded during release.
If this requirement d.
The maximum activity to be contained in cannot be met, continued release of liquid one liquid radwaste tank excluding tritium effluents shall be permitted only during the and dissolved gases that can be discharged succeeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that during this ty, directly to the environs, shall not exceed 48-hour period, two independent samples of each ty, 10 curies.
tank shall be analyzed and two station personnel C7s shall independently check valving prior to the e.
Uhen the release rate of radioactive discharge.
I\\)
ef fluents, excluding tritium and dissolved N
M e
P
p pm e.
. 2.0 LIMITING CONDITIONS FOR OPERATION Bases (Cont'd)
In addition to the limiting conditions for operation listed under Specification b, the reporting requirements of Specification e, in addition to the requirements of Section 5.6.2, delineate that the licensee shall identify the cause whenever the rate of radioactive effluents, excluding tritium and noble gases, exceeds 2.5 curies during any calendar quarter and describe the proposed program of action to reduce such release rate.
This report must be filed within 30 days following the calendar quarter in which the 2.5 curies release occurred.
2.3.2 Caseous Effluents Applicability Applies to the controlled release of radio-active gases from TMI Unit 1.
Objective Objective LJ7 To define the limits and conditions for the To ensure that radioactive gaseous releases
'37 controlled release of radioactive effluents from the facility are within the limits of C7s to the environs to ensure that these releases specifications, are as low as.[S reasonably achievable in g
l
'sJ rs;
- 2h -
9 2.0 LIMITING CONDITIONS FOR OPERATION Objectives (cont'd) conformance with 10 CFR Parts 50.3ha and 50.36a, and to ensure that these releases result in concentrations of radioactive materials in gaseous effluents released to unrestricted areas within the limits specified in 10 CFR Part 20.
To ensure that the releases of radioactive material above back-ground to unrestricted areas are as lov as is reasonably achievable, the following design objectives as defined in Appendix I to 10 CFR Part 50.36a apply:
The annual total quantity of all radioactive material above a.
background that may be released to unrestricted areas should not result in an annual does or dose commitment from liquid effluents for any individual in an unrestricted area from all pathways of exposure in excess of 3 millirems to the total body or 10 millirems to any organ.
b.
The annual total quantity of all radioactive material hbove background that may be released to the atmosphere should not result in an annual air dose from gaseous effluents at any location near ground level which could be occupied by individuals in unrestricted areas in excess of 10 millirads for gamma radiation or 20 millirads for beta radiation, or (17 that this quantity should not result in an annual external (J7 dose from gaseous effluents to any individual in unrestricted C7s areas in excess of 5 millirems to the total body or 15 millirems to the skin.
p)
N The ar.nual total quantity of all radiactive iodine and radio-c.
(,q active material in particulate form above background that may be released in effluents to the atmosphere should not result in an annual dose from such radioactive iodine and radioactive material in particulate form for any individual in an unrestricted area from all pathways of exposure in excess of 15 millirems to an organ.