ML20198S327

Amend 15 to License DPR-9,consisting of Changes to TS

ML20198S327
Person / Time
Site:	Fermi
Issue date:	01/06/1999
From:	Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20198S313	List: ML20198S310 ML20198S323 ML20198S327 ML20198S334 ML20198S337
References
NUDOCS 9901110269
Download: ML20198S327 (8)

Text

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N DETROIT EDISON COMPANY

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l DOCKET NO. 50-16 I

l-ENRICO FERMI ATOMIC POWER PLANT. UNIT 1 l

AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No.15 Licens No. DPR-9 j

1. The U.S. Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.. The application for amendment by Detrnit Edison Company (the licensee) dated January 28,1998, and supplemented b, letters dated August 26,1998, and October 22, i

1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of i-the Act, and the rules and regulations of the Commission; I

C. There is reasonable assurance: (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in

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10 CFR Chapter 1; D. The licensee is technically and financially qualified to encage in the activities authorized by this amended license in accordance with the rules and regulations of the Commission; E. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and F. The issuance of this amendment is in accordance with 10 CFR Part 51 of the i-Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, Possession-Only License No. DPR 9 is hereby amended in its entirety to read l

as follows:

A. This amended license applies to the Enrico Fermi Atomic Power P.lant, Unit No.1 (Fermi 1, or the facility) owned by the Detroit Edison Company. The facility is located at l

the Lagoona Beach, Frenchtown Township, Monroe, Michigan and is described in the l

Fermi 1 Safety Analysis Report as ammded.

B. Subject to the conditions and requirements incorporated berein, the Commission hereby licenses the Detroit Edison Company; (1)

Pursuant to Section 104(c) of the Act and 10 CFR Part 50," Domestic Licensing of Production and Utilization Facilities" to possess but not to operate the facility.

9901110269 990106

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i (2) Pursuant to the Act and 10 CFR Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Mate iar to possess, but not to separate, such byproduct material as may have been produced by operations of the reactor.

l (3) Pursuant to the Act and 10 CFR Part 30, " Rules of General Applicability i

to Domestic Licensing of Byproduct Material," to receive, acquire, possess, use and transfer byproduct material without restriction to chemical or physical form for sample analysis, instrument calibration, or l

associated with radioactive apparatus, hardware, tools, and equipment, l

provided the cumulative radioactive material quantity of the byproduct material does not exceed the criteria contained in Section 30.72, Schedule C, Quantities of Radioactive Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a -

Release.

C. This license shall be deemed to contain and is subject to the conditions specified in Part 20, Section 50.59 of Part 50, Section 30.34 of Part 30 of 10 CFR Chapter I, and is subject to all applicable prchions of the Act, and to the rules, regulations and orders of l

the Commission now or hereafter in effect, and is subject to the additional condition l

specified below:

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I (1) The Technical Specifications contained in Appendix A as revised through Amendment No.15 are hereby incorporated in this license. The licensee shall maintain the facility in accordance with the Tecnnical Specifications.

i D. This license is effective as of the date of its issuance and shall expire on March 20,2025.

j 3.

This license arnendment is effective as of the date of its issuance and must be fully implemented no later than 60-calendar days from.the date of its issuance.

' hay of January 1999.

l Dated at Rockville, Maryland, this 2

FOR THE NUCLEAR REGULATORY COMMISSION l

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Q6hn W. N. Hickey, Chief j'

Low-Level Waste and Decommissioning Projects Branch Division of Waste Management' Office of Nuclear Material Safety and Safeguards

Attachment:

Ch&nges to the Technical Specifications

_y January 6,1999 M

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(2) Pursuant to the Act and 10 CFR Part 30," Rules of General Applicability to Domestic l

Lic:nsing of' Byproduct Material" to possess, but not to separate, such byproduct material as may have been produced by operations of the reactor.

(3) Pursuant to the Act and 10 CFR Part 30," Rules of General Applicability to Domestic Licensing of Byproduct Material," to receive, acquire, possess, use and transfer byproduct material without restriction to chemical or physical form for sample analysis, instrument calibration, or associated with radioactive apparatus, hardware, tools, and equipment, provided the cumulative radioactive material quantity of the byproduct material does not exceed the criteria contained in Section 30.72, Schedule C, Quantities of Radioactive Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a Release.

C. This license shall be deemed to contain and is subject to the conditions specified in Part 20, Section 50.59 of Part 50, Section 30.34 of Part 30 of 10 CFR Chapter I, and is subject to all applicable provisions of the Act, and to the rules, regulations and orders of the Commission now or hereafter in effect, and is subject to the additional condition specified below:

(1) The Technical Specifications contained in Appendix A as revised through Amendment No.15 are hereby incorporated in this license. The licensee shall maintain the facility in j

accordance with the Technical Specifications.

D. This license is effective as of the date of its issuance and shall expire on March 20,2025.

3.

This license amendment is effective as of the date of its issuance and must be fully implemented no later than 60-calendar days from the date of its issuance.

Dated at Rockville, Maryland, this g# day of January 1999.

FOR THE NUCLEAR REGULATORY COMMISSION j

(Original signed by)

John W. N. Hickey, Chief Low-Level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards

Attachment:

Changes to the Technical Specifications TICKET: LLDP-8021 D M 11LS/6 E DISTRIBUTiO_ N:

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.c ATTACHMENTTO LICENSE AMENDMENT AMENDMENT NO.15 TO FACILITY OPERATING LICENSE NO. DPR-9 DOCKET NO. 50-16 Revised Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment i

number and contain marginal lines indicating the areas of change.

_ REMOVE INSERT 5

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c. Observa'tions 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 comer of the building. At least one other door shall be operable from the inside. Other extemal 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

Prior to commencing planned discharge of any radioactive liquid or gaseous efnuent, a waste disposal system shall be functional and operating procedures developed.

All discharges ofliquid radioactive ef0uents from Fermi i shall be sampled and analyzed by 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 during discharges. If the radiation detection instrument is out of service such that the efauent cannot properly be monitored, discharge of the effluent 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 each 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 ef0uents from cutting pipe containing primary sodium or processing primary sodium shall also be monitored or sampled and analyzed for particulates. During other evolutions resulting in radioactive gaseous ef0uents, the efnuents shall be monitored or sampled and analyzed for tritium and paniculates.

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 Efnuents - 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 Liauid Efauents - The calculated annual total quantity of a.

radioactive material in liquid effluents 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.

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b. Total Ouantity of Liquid Ef0uents - The calculated annual total quantity of radioactive material, except tritium and dissolved gases, in liquid efnuents shall not exceed 5 curies.

' 2. Gaseous Ef0uents - Gaseous efnuents 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 EfHuents - The calculated annual air dose due to I

radioactive material, above background, in gaseous efDuents 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.

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 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 efnuents is commenced. If discharge ofliquid radiological efGuents 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 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).

i 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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granted pennission 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 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 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 discoveiy. 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 'oetween reports shall not exceed 12 months.

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.

d. Records of CO cover gas usage.

2 c.

Records of radioactivity in liquid wastes released to the environment.

f. Records of shipments of radioactive materials.

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