ML20155A711

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Proposed Replacement TS Sections F.1.a & F.2.b Pages, Utilizing Terminology of TEDE Instead of Whole Body & Organ Dose
ML20155A711
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 10/22/1998
From:
DETROIT EDISON CO.
To:
Shared Package
ML20155A704 List:
References
NUDOCS 9810290226
Download: ML20155A711 (4)
v • d • e


Text

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Enclosure 1 l NRC-98-0157 Page1 l

4 a

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ENCLOSURE 1 l l

l l

l Enrico Fermi Atomic Power Plant, Unit 1 I NRC Docket No. 50-16 ,

NRC License No. DPR-9 l l

l PROPOSED TECHNICAL SPECIFICATION l

CHANGES I i

1 9810290226 981022 PDR ADOCK 05000016 p PDR H e' - m 'm- --

c. Observations of the nitrogen cover gas pressure over essentially empty sodium storage tanks in the Sodium Building Complex shall be performed weekly.
4. 'The Primary System cover gas supply system may be out of service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
5. The Primary System cover gas pressure may be interrupted for no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 30 day period.

E. FUEL AND REPAIR BUILDING

1. Access - Normal access to the Fuel and Repair Building shall be limited to the door at the southwest corner of the building. At least one other door shall be operable from the inside. Other external doors may be used, if needed, for work being carried out.
2. Drains - All drains are connected to sumps. The sump pumps discharge to the liquid waste holdup system. The pumps may be disconnected or decommissioned when no longer needed for disposing of radioactive waste.

F. WASTE DISPOSAL AND RADIOACTIVE EFFLUENTS l l

Prior to commencing planned discharge of any radioactive liquid or gaseous ef0uent, a waste I disposal system shall be functional and operating procedures developed. l All discharges ofliquid radioactive emuents from Fermi i shall be sampled and analyzed by l

gamma spectral analysis and for tritium prior to release. Liquid radioactive ef0uents which have not been processed to remove particulates shall be monitored by a radiation monitor l during discharges. If the radiation detection instrument is out of service such that the emuent l cannot properly be monitored, discharge of the emuent shall be discontinued. During periods of use, the discharge radiation monitor shall be checked for response once a week with a radioactive source and shall be calibrated at least once every six months or before cach discharge batch.

Radioactive gaseous ef0uents shall be monitored or sampled and analyzed for tritium during evolutions involving the cutting of pipe containing sodium and during sodium processing.

Gaseous effluents from cutting pipe containing primary sodium or processing primary sodium shall also be monitored or sampled and analyzed for paniculates. During other evolutions resulting in radioactive gaseous effluents, the ef0uents shall be monitored or sampled and analyzed for tritium and particulates.

The calculational method of performing dose calculations to show adherence to the following requirements shall be developed and documented prior to commencing planned discharges.

Calculations shall be performed for any year in which a discharge of radioactive ef0uents occurs.

1. Liauid Efauents - Radioactive waste discharges to offsite locations shall not exceed the limits given in 10 CFR 20, Appendix B, Table 2, Column 2, on an instantaneous basis,
a. Dose Due to Release of Liauid Efnuents - The calculated annual total quantity of radioactive material in liquid ef0uents from the facility shall not result in an annual Total Effective Dose Equivalent (TEDE) in an unrestricted area from all pathways of exposure in excess of 5 mrem.

5 Amendment No.

b. Total Ouantity of Liauid Effluents - The calculated annual total quantity of radioactive material, except tritium and dissolved gases, in liquid effluents shall not exceed 5 curies.
2. Gaseous Effluents - Gaseous effluents shall not result in offsite ground level concentrations exceeding the limits given in 10 CFR 20, Appendix B, Table 2, Column 1 on an instantaneous basis,
a. Dose Due to Release of Gaseous Effluents - The calculated annual air dose due to radioactive material, above background, in gaseous effluents from the facility to any location near ground level which could be occupied by individuals at or beyond the boundvy of the site shall not exceed 10 mrad due to gamma radiation or 20 mrad due to beta radiation.
b. Individual Dose Due to Gaseous Effluents - The calculated annual quantity of radioactive material in gaseous effluents from the facility shall not result in an annual TEDE in excess of five mrem or an annual skin dose in excess of 15 mrem to any I individual in an unrestricted area at or beyond the site boundary.
3. Total Dose Due to the Facility - The calculated annual total effective dose equivalent to individual members of the public from the facility shall not exceed 100 mrem.

G. ENVIRONMENTAL SURVEILLANCES A number ofIndicator Stations have been established where it is estimated that maximum concentrations of radioactive material discharged from the plant would occur (Figure G-1).

Background sampling stations shall be located at Swan Creek (at Dixie Highway) and Detroit and Monroe raw city water sampling stations.

Environmental Surveillances are not required until discharge ofliquid radiological effluents is commenced. If discharge ofliquid radiological effluents is commenced, two different regimes of sampling and analysis shall be utilized. A summary of these regimes is given in Table G-1,

1. Regime I shall be followed if activity is released.
2. Regime II shall be followed if no activity has been released during the previous 90 days.

H. FACILITY MONITORING SURVEILLANCES l

1. Alarms - Each of the items in Table H-1 shall activate an alarm. The elements activating these alarms shall be checked semi-annually. Continuity test of the water intrusion alarm circuits shall be checked weekly (detectors are located in the waste water sump and biological shield annulus around the Reactor Building).

The primary system pressure alarm may be out of service for up to 30 days provided that carbon dioxide pressure is verified to be above atmospheric pressure within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and daily thereafter, until the alarm is restored. The water intrusion alarms may be out of service for up to 30 days provided that the affected area is checked weekly to verify no abnormal accumulation of water until the alarm is restored .

6 Amendment No.

granted permission for unescorted access. Visitors will be properly escorted and will be issued DRDs.

7. Procedures - Procedures for the following activities shall be prepared and utilized:
a. Radiation control
b. Maintaining cover gas supply
c. Facility inspections Procedure, shall be reviewed and approved by the Review Committee. The Custodian may tempo arily change a procedure by Written Order following his determination that i the change does not constitute a significant increase in the hazards associated with the operation.
8. Reporting Reauirements - An annual report shall be made to the NRC summarizing the activities carried out and the results of the facility surveillance program.

A Licensee Event Report (LER) shall be phoned to NRC Region III within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the discovery. A formal report shall be filed for any LER within 30 days of discovery.

The report shall include a description of the occurrence together with steps taken to correct the situation.

The quantity of the principal radionuclides released in liquid and gaseous effluents and calculated doses shall be reported to the Nuclear Regulatory Commission annually and the time between reports shall not exceed 12 months.

9. Record Keeping - Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least five years, unless otherwise stated:
a. Records of LERs
b. Records of pericdic checks, inspections and/or calibrations performed to verify that surveillance requirements are being met.
c. Records ofplant radiation and contamination surveys.
d. Records of CO cover 2 gas usage.
e. Records of radioactivity in liquid wastes released to the environment.
f. Records of shipments of radioactive materials.

12 Amendment No.

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