ML20154R225

Amend 13 to License DPR-9,allowing Access Control Flexibility,Establishing Compensatory Provisions Re PA Boundary,Eliminating Redundancy Between Ts,Revising Figure B-1 & Correcting Typos

ML20154R225
Person / Time
Site:	Fermi
Issue date:	10/21/1998
From:	Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20154R222	List: ML20154R218 ML20154R225 ML20154R233 ML20154R238 ML20154R242
References
NUDOCS 9810260247
Download: ML20154R225 (8)

Text

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[ d UNITED STATES

< S NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. M1

• * * * * ,o DETROIT EDISON COMPANY DOCKET NO. 50-16 ENRICO FERMI ATOMIC POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.13 License No. DPR-9

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

A. The application for amendment by Detroit Edison Company (the licensee) dated January 28,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission regulations set forth in 10 CFR Chapter 1; B. The facility will be maintained in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; 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 10 CFR Chapter 1; D. The licensee is technically and financially qualified to engage 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 Commission regulations and all applicable requirements have been satisfied.

2. Accordingly, Facility Operating License No. DPR-9 is hereby amended in its entirety to read as follows:

A. This amended license applies to the Enrico Fermi Atomic Power Plant, Unit No.1 (the facility) owned by The Detroit Edison Company. The facility is located at the Lagoona Beach, Frenchtown Township, Monroe, Michigan and is described in the application for renewal dated May 17,1985, as supplemented by letters dated July 23,1986, September 15,1986, September 25,1987, September 15,1988, and December 22, 1988.

9810260247 981021

PDR ADOCK 05000016 P pon

B. Subject to the conditions and requirements incorporated herein, the Commission hereby l l 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 operate the facility.

(2) Pursuant to the Act and 10 CFR Part 30 " Rules of General Applicability to Domestic Licensing of Byproduct Material" to pocsess, 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 l 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.13 are hereby incorporated in this license. The licensee shall maintain the facility in accordance with the Technical Specifications.

D. This license is effective as of date of 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 4 /-

f /

l John W. N. Hickey, Chief J Low-Level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards Date of Issuance: October 21,1998 1

a ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.13 TO FACILITY OPERATING LICENSE NO. DPR-9 DOCKET NO. 50-16 1

1 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages The revised pages are identified by the captioned amendment number and contain marginallines indicating the areas of change.

REMOVE INSERT i 3 3 l 4 4 5 5 11 11 l

1 l

l l

l l

l 1

I I m j Key:

_ Protected Area N _ Boundary l

l - .

Underground Structures Fuel & Repair Building llealth Physics Building (Dismantled) Slab Sodium Building

\ Trestleway w Primary i Na Storage Sodium Vent Building I Tank Room Cold Trap . ../ Tunnel 1 Room Waste Gas Building NaK Room I

\ Inert Gas Inert Ga's.

Tunnel  !

Building Reactor  !

Building

- Annulus l

Inert Gas Tunnel A

[ Primary '\ -

FPD

( Shield } Bldg.

( Tank / .

1 W i Reactor Building iWe'st' Sal .-

! East Na

!, Gallery j l Gallery Office Building Control Outside of Building Protected Area Outside of Protected Steam Generator Building Area Outside of Protected Area Turbine Building Outside of Protected Area l

l Figure B-1 Facility Plan i 3 AMENDMENT NO. 13

Access to the facility shall be through locked gates in the fencing or locked doors. Doors in the building walls making up part of the perimeter shall be locked, secured from the inside, or peimanen'tly closed. The gates and doors may be unlocked and/or open when work is in progress in the Protected Area or personnel are within. Security shall be maintained by 24-hour guard service within the owner controlled area boundary.

The Custodian (or Delegate) and the Fermi 2 Radiation Protection control point shall be responsible for keys to the facility. The Custodian and Fenni 2 Radiation Protection personnel shall only permit key use by authorized persons. Unescorted access to the Protected Area must be approved by the Custodian or Delegate. Records shall be kept of key issuance.

Temporary modifications may be made to the Protected Area boundary shown in Figure B-1, provided the boundary continues to meet the requirements of a Physical Barrier, as defined in Section A, and any access points meet the requirements in this Section.

If work needs to be performed on the Protected Area fence or building walls making up part of the perimeter, such that the requirements for the boundary will temporarily not be met, an individual shall be posted in the vicinity or observe the area remotely using a camera capable of viewing the affected area, during periods when there is no ongoing work in progress or personnel within the Protected Area. '

C. REACTOR BUILM

1. Access - Doors into the Reactor Building shall remain locked (or not operable from l

outside the building) except for authorized entry.

2. Drains - There shall be no drains within the Reactor Building. Surrounding the Reactor Building below grade is the biological shield which forms an annulus around the Reactor Builoing. Drains from this annulus shall flow to a sump pump located outside the Protected Area.

D. PRIMARY SYSTEMS / STORAGE TANK COVER GAS

1. Supolv - The Primary System shall be connected to reserve and backup supplies of l

carbon dioxide (CO 2). The pressure of the cover gas shall be maintained above atmospheric pressure (see Table H-1). The supply system piping shall be fitted with a pressure relief valve set for approximately 5 psig.

2. Bac'(un Sunolv - The Primary System cever gas backup supply shall be sufficient to l supply the system for eight days under nonnal conditions.

l 3. Surveillances

a. Cover gas (CO 2) pressure in the Primary System shall be checked and recorded weekly.

b. The Primary System (CO 2) cover gas pressure relief valve shall be tested annually.

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4 AMENDMENT N0. 13 L--_________-.---

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c. Observations of thecitrogen cover gas pressure over essentially empty sodium storage tanks in the Sodium Building Complex shall be performed weekly. .

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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 />.

l S. The Primary System cover gas pressure may be intermpted 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 l

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 l 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.

(

l. 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.

l F. WASTE DISPOSAL SURVEILLANCES Prior to commencing discharge of any liquid effluent, monitoring facilities in the liquid waste

. disposal system shall be provided to ascertain the concentration of radioactivity. If a radiation instrument is out of service such that the efuuent cannot properly be monitored, discharge of the emuent shall be discontinued.

During periods when radioactive effluents 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 each discharge batch.

1. Liauid Ef0uents - Radioactive waste discharges to offsite locations shall not exceed the i limits given in 10 CFR 20, Appendix B, Table 2, Column 2, on an instantaneous basis.

2. Gaseous Efnuents - 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.

G. ENVIRONMENTAL SURVEILLANCES A numlier 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 samplips 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 l is commenced. If discharge ofliquid radiological ef0uents is commenced, two different regimes of sampling and analysis shall be utilized. A summary of these regimes is given in Table G-1.

5 AMENDMENT N0. 13

1 may be different than stated here; their authority and responsibility at the Femii i facility l l shall, however, correspond to the following specifications.

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a. Custodian or Delecate - The responsibility of the Custodian or Delegate shall be to coordinate, approve and assign all work being done at the facility.

b. Health Physicist - The Health Physicist shall review procedures and limits involving the handling of radioactive materials. He shall be responsible to see that all plant discharges and all shipments are within 'he limitations set forth in the Code of Federal Regulations.

The qualifications for the Health Physicist shall be two years of specialized training in health physics or equivalent and three years of work experience related to radiological I health and safety.

3. Health Physics Technician - person who has received training in health physics techniques and procedures shall be on site and may direct health physics activities

whenever radioactive materials are being moved.

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4. Review Committee - A Review Committee shall be established for the purpose of reviewing and approving facility monitoring results and procedures for activities at the facility and resolution of LERs.

The membership of the Review Committee shall be composed of five personnel from within The Detroit Edison Company or consultants, at least three (3) of whom have had two (2) years or more of experience in a responsible position at an operating nuclear power facility and have had basic health physics training. The Review Committee shall meet at intervals not to exceed 13 months and shall prepare formal minutes ofits meetings.

5. (Deleted)

6. Dosimetry - Thermoluminescent Dosimeters (TLD) and Direct Reading Dosimeters (DRD) will be supplied for all persons who have been l

l AMENDMENT N0. 13 33 1

G 4

5 ENCLOSURE 2

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