ML20199H256

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Proposed Tech Specs,Modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Requirements Per 10CFR50.36a
ML20199H256
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/28/1998
From:
DETROIT EDISON CO.
To:
Shared Package
ML20199G510 List:
References
NUDOCS 9802040452
Download: ML20199H256 (4)
v • d • e


Text

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Enclogure 2

. NRC 98*0027 Page1 ENCLOSURE 2

PROPOSEI)
TECHNICAL SPECIFICATION CHANGES Enrico Ferral Atomic Power Plant, Unit 1 NRC Docket No. 5016 NRC License NO. DPR 9 I

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9902040452 990128 PDR ADOCK 05000016.. "

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E. FUEL AND REPAIR HUILDING

1. Amn - Nonnal access to the Fuel and Repair Buildind . hell be limited to the door at the southwest corner of the building. All other extemal access doors shall be locked from the inside or pennanently closed unless they are needed for work being carried out. At least one other door shall be operable from the inside.
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 Prior to commencing planned discharge of any radioactive liquid or gaseous emuent, a waste disposal system shall be functional, monitoring facilities shall be provided to ascertain the concentration of radioactivity, and operating procedures developed, if a radiation detection instrument is out of service such that the emuent cannot properly be monitored, discharge of the emuent shall be discontinued.

During periods when radioactive emuents are being discharged, the discharge radiation monitor shall be checked for response once a week with a source and shall be calibrated at least once every six months or before cach discharge batch.

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 perfonned for any year in which a discharge of rad. ctive emuents occurs.

1. Liquid Emuents - 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.

Dose Due to Release of Liquid Emuents - The calculated annual total quantity of radioactive material in liquid emuents from the facility shall not result in an annual dose or dose commitment to the total body or to any organ of an individual in an unrestricted area from all pathways of exposure in excess of five mrem.

. Total Ouantity of Liauid Emuents - The calculated annual total quantity of radioactive

! material, except tritium and dissolved gases, in liquid emuents shall not exceed five curies.

2. Gutqps Emuents Gaseous emuents 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.

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3. Dose Due to Release of Gasecus Emuents The calculated annual air dose due to radioactive material, above b.,ckground, in gaseous emuents from the facility to any location near ground level which could be occupied by individuals at or beyond the boundary of the site shall not exceed 10 mrad due to gamma radiation or 20 mrad due to beta radiation.

The calculated annual quantity of radioactive material in gaseous emuents from the facility shall not result in an annual dose or dose commitment to any individual in an unrestricted area at or beyond the site boundary in excess of five mrem whole body, 15 mrem to the skin, or 15 mrem to any organ from all pathways of exposure.

4. Ic:al 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.

O, ENVIRONMENTAL SURVEILLANCES A number ofindicator Stations have been c.wablished where it is estimated that maximum concentrations of radioactive material discharged from the plent weuld occur (Figure G 1).

Background sampling stations shall be located at Swan Creek (at Dixie liighway) 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 emuents 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 ie ieleased.
2. Regime 11 shall be followed if no activity has been released during the previous 90 days.
11. FACILITY MONITORING SURVEILLANCES j
1. Alamis - Each of the items in Table 11 1 shall activate an alann. The elements activating these alarms shall be checked semi annually. Continuity test of the water intrusion alann 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 eatbon 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 alann 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 abnonnal accumulation of water until the alaml is restored .

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I granted permission for unesconed access. Visitors will be properly encoded and will be l issued DRLs.

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7. Procedures . Procedures for the following activities shall be prepared and utilized:

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a. Radiation control l

- b. Maintaining cover gas supply l

c. Facilityinspections  ;

l Procedures shall be reviewed and approved by the Review Committee. The Custodian l may temporarily change a procedure by Written Order following his determination that l the change does not constitute a significant increase in the hazards associated with the ,

operation, j

8. Renortina Reauirements . An annual report shall be made to the NRC summarizing the j

. activities carried out and the results of the facility surveillance program, j A Licensee Event Report (LER) shall be phoned to NRC Region Ill within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of l

. the discovery. A formal report shall be file 6 for any LER within 30 days of discovery. -  ;

The report shall include a description of the occurrence together with steps taken to t correct the situation.. I The quantity of the principle 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. j s

-9. Record Keenina . 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:-' .!

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, a. Recordt of LERs j i . .

-i l b. Records of periodic checks, inspections and/or calibrations performed to verify that l

,: . surveillance requirements are being met.

c. Records of plant radiation and contamination sun'eys.

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d. - Records of CO, cover gas usage.

L c. Records of radioactivity in liquid wastes released to the environment.  !

f. Records of shipments of radioactive materials.

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