ML20217N430

Amend 17 to License DPR-9,revising TS by Deleting SR D.3.c, Which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building

ML20217N430
Person / Time
Site:	Fermi
Issue date:	10/25/1999
From:	Camper L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20217N429	List: ML20217N426 ML20217N430 ML20217N438 ML20217N449
References
NUDOCS 9910290027
Download: ML20217N430 (7)

Text

g

>Q CE O

~

4 +

y* 4 UNITED STATES r

g NUCLEAR REGULATORY COMMISSION

• WASHINGTON, D.C. 2056H001 4

9 . . . . . ,o DETROIT EDISON COMPANY -

DOCKET NO. 50-16 ENRICO FERMI ATOMIC POWER PLANT. UNIT I AMENDMENT TO FACILITY OPER.ATING LICENSE Amendment No.17 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 April 20,1999, 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 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 quali6ed 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 sect. 'y 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's regulations and all applicable requirements have been satisfied.

2. Accordingly, Possession-Only License No. DPR-9 is hereby amended ir. its entirety to read as follows:

A. This amended license applies to the Enrico Fermi Atomic Power Plant, Unit No.1 (Fermi 1, or the facility) owned by the Detroit Edison Company. The facility is located at 9910290027 991025 PDR ADOCK 05000016 Qub t- -

2 the Lagoona Beach, Frenchtown Township, Monroe, Michigan, and is described in the Fermi 1 Safety Analysis Report as amended.

B. Subject to the conditions and requirements incorporated herein, 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.

(2) Pursuant to_the Act and 10 CFR Part 30," Rules of Genera' Applicability to Domestic Licensing 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,"hules 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.

(4) Pursuant to the Act and 10 CFR Part 70," Domestic Licensing of Special Nuclear Material" to receive, acquire, possess, use and transfer, but not separate, special nuclear material in a quantity not to exceed 15 grams of U-235, U-233, or plutonium, or any combination thereof and not to exceed plutonium activity of 2 curies, if special nuclear material in quantities exceeding 15 grams or more than 2 curies of plutonium are identified in plant contamination in the future, this license permits possession and transfer of special nuclear material and the additional applicable requirements of 10 CFR Part 70, Part 73, and Part 74 will apply for the amount possessed.

I CJ 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 1; 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:  ;

i The Technical Specifications contained in Appendix A, as revised through Amendment No.17, 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 the date ofits issuance and shall expire on March 20,2025.

r

o 3

3. . This license amendm:nt 'is effective as of the date ofits issuance and must be fully implemented no later than 60-calendar days fmm the date ofits issuance.

Dated at Rockville, Maryland, this4b day of October 1999.

FOR TIIE NUCLEAR REGULATORY COMMISSION QAv4

, _La .W. Camper, Chief g Dec mmissioning Branch Division of Waste Management Office of Nuclear Material Safety and Safeguards

Attachment:

As stated -

4

'a t

b y

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.17 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 areidentified by the captioned amendment number and contain marginal lines indicating the areas of changes, JtEMOVE INSERT 4 4 5 5 l

l l

l l

l f

l e

- l

1

. 4 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 permanently 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 Fenni 2 Radiation Protection control point shall be responsible for keys to the facility. The Custodian and Fermi 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 temporann r_ot 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 Protect',d Area.

C. REACTOR BUILDING

1. Access - Doors into the Reactor Building shall remain locked (or not operable from outside the building) except for authorized entry.

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

D. PRIMARY SYSTEM COVER GAS l

1. Sunolv - The Primary System shall be connected to reserve and backup supplies of 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. Backun Supolv - The Primary System cover gas backup supply shall be sufficient to supply the system for eight days under normal conditions.

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.

6 AgatdmaisNa 17

4. The Pdmary 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 />.

S. 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 a..d 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 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 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 1 shall be sampled and analyzed by gamma spectral analysis and for tritium prior to release. Liquid radioactive emuents 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 emuent 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 l with a radioactive source and shall be calibrated at least once every six months or before each i discharge batch. )

Radioactive gaseous effluents 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 particulates. During other evolutions resulting in radioactive gaseous emuents, the emuents 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 effluents i occurs.

1. Liauid 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.

l

a. Dose'Due to Release of Liauid Emuents - The calculated annual total quantity of radioactive material in liquid emuents 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.17

.