ML20237E898

Proposed Tech Specs Implementing Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits,& Annual Reporting of 10CFR50.36a

ML20237E898
Person / Time
Site:	Fermi
Issue date:	08/26/1998
From:	DETROIT EDISON CO.
To:
Shared Package
ML20237E896	List: ML20237E898 NRC-98-0128, Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a
References
NUDOCS 9809010274
Download: ML20237E898 (4)

Text

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Enclosure 2 NRC-98-0128 Page1 l ENCLOSURE 2 I

l Enrico Fermi Atomic Power Plant, Unit I l

NRC Docket No. 50-16 NRC License No. DPR-9 PROPOSED TECIINICAL SPECIFICATION CIIANGES r

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9809010274 990826 PDR ADOCK 05000016 P pm ,

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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. All other external access doors shall be locked from the inside or permanently closed unless they are needed for work being carried out. At least one other door shall be operable from the inside.

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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 and operating procedures developed.

All discharges ofliquid radioactive emuents from Fermi i shall be sampled and analyzed by gamma spectral analysis and for H-3 prior to release. Liquid radioactive emuents which have not been processed to remove particulate shall be monitored by a radiation monitor during discharges. If the radiation detection instrument is out of service such that the emuent cannot properly be monitored, discharge of the emuent shall be discontinued. During j 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 each discharge batch.

Radioactive gaseous emuents shall be monitored or sampled and analyzed for H-3 during evolutions involving the cutting of pipe containing sodium and during sodium processing.

Gaseous emuents from cutting pipe containing primary sodium or processing primary sodium shall also be monitored or sampled and analyzed for particulate. During other evolutions resulting in radioactive gaseous emuents, the emuents shall be monitored or sampled and analyzed for H-3 and particulate.

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 emuents occurs.

1. Liauid Emuents - Radioactive waste discharges to offsite locations shall not exceed the )

limits given in 10 CFR 20, Appendix B, Tabic 2, Column 2, on an instantaneous basis. l l

a. Dose Due to Release of Liauid Emuents - The calculated annu.a total quantity of  !

l radioactive material in liquid emuents from the facility shall not result in an annual l 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 5 mrem.

b. Total Ouantity of Liauid Emuents - The calculated annual total quantity of radioactive material, except tritium and dissolved gases, in liquid emuents shall not exceed 5 curies.

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2. Gaseous Effluents - Gaseous effluents shall not result in oficite ground level concentrations exceeding the limits given in 10 CFR 20, Apuendix B. Table 2, Column 1 on an instantaneous basis.

a. Dose Due to Release of Gaseous Effluents - The calcstated 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 boundary of the site shall not exceed 10 mrad due to gamma radiation or 20 mrad due 1 to beta radiation.

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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 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 1 any organ from all pataways of exposure. I

3. Total Dose Due to the Facility - The calculated annual total effective dose equivalent to l individual memt of the public from the facility shall not exceed 100 mrem.  ;

G. ENVIRONMENTAL SURVEILLANCE ,

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

Environmental Surveillance 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 11 shall be followed if no activity has been released during the previous 90 days.

H. FACILITY MONITORING SURVEILLANCE 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 .

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l granted pennission for unescorted access. Visitors will be properly escorted and will be issued DRDs. i

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

a. Radiation control l I

b. Maintaining cover gas supply

c. Facility inspections l

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

8. Reportine Requirements - 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 fonnal 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 Conunission annually and j the time between reports shall not exceed 12 months. l

9. Record Keepine . 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 periodic checks, inspections and/or calibrations performed to verify that surveillance requirements are being met.

c. Records of plant radiation and contamination surveys.

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d. Records of CO cover 2 gas usage.

e. Records of radioactivity in liquid wastes released to the environment.

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f. Records of shipments of radioactive materials.

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