ML20133L617

Amend 11 to License DPR-9,allowing Certain Equipment & Instruments to Be Removed from Svc for Short Periods of Time Allowing for Maint,Testing,Insp & Account for Equipment Failures

ML20133L617
Person / Time
Site:	Fermi
Issue date:	01/02/1997
From:	Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20133L531	List: ML20133L529 ML20133L617 ML20133L737 ML20133L771
References
NUDOCS 9701220081
Download: ML20133L617 (7)

Text

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.4 QE_TROIT EDISON COMPANY DOCKET NO. 50-16 ENRICO FERMI-ATOMIC POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 11 License No. DPR 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 August 29 1996. 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 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: (1) 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 I:

D. The licensee is technically and financially qualified to engage in the act.vities authorized by this amended license in accordance with the rules and regulations of the Commission:

E. The issuance of this amendment will nu be inimical to the common defense and security or to the health aad 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, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.

and paragraph C.(1) of Facility Operating License No. DPR-9 is hereby amended to read as follows:

9701220081 970102'" <

- hDR ADOCK o PDR; mN Enclosure

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 11 TO FACILITY OPERATING LICENSE NO. DPR-9 DOCKET NO. 50-16 l 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 marginal lines indicating the areas of change, j REMOVE I'JSERT  ;

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Access to the facility shall be through locked gates in the fencing. Doors in the building walls making up part of the perimeter shall be either locked from the inside or permanently closed. The gates and doors may be open when required work is in progress. All access points to the Protected Area are to be kept locked except when open for use by an authorized person. Security shall be maintained by 24-hour guard service within the owner controlled area boundary.

C. REACTOR BUILDING

1. Access - Doors into the reactor building shall remain looked (or not operable from 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 Building. Drains from this annulus shall flow to a sump pump located outside the Protected Area.

D. PRIMARY SYSTEM / STORAGE TANK COVER GAS

1. Supolv - The primary system shall be connected to reserve and backup supplies of carbon dioxide (CO2). 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.

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2. Backup Supojy - The Primary System cover gas backup supply shall be sufficient to supply the system for eight days under normal conditions.

3. Surveillances i

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

b. The Primary System (CO2) cover gas pressure relief valve shall be tested annually.

c. Observations 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.

4 Amendment No.11

t 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 l unless they are needed for work being camed out. At least one door shall be operable from the inside. i

2. Q.gian - All drains are comected 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 SURVEILLANCES l Prior to commencing discharge of any liquid eNiuent, 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 enluont 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 Effluents - Radioactive waste discharges to onsite locations shall not exceed the limits given in IOCFR20, Appendix B, Table 2, Column 2, on an instantaneous basis.

2. Gg.seous Effluents - Gaseous effluents shall not result in ofisite ground

! level concentrations exceeding the limits given in 10CFR20, Appendix B Table 2, Column 1 on an instantaneous basis.

1 G. ENVIRONMENTAL SURVEILLANCES A number of Indicator Stations have been established where it is estimated i that maximum concentrations of radioactive material discharged from the plant i 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 of liquid radiological effluents is commenced. If discharge of liquid radiological l effluents is commenced, two different ragimes of sampling and analysis shall be utilized. A summary of these regimes is given in Table G-1.

5 Amendment No.11

1. Regime I shall be followed if activity is released.

2. Regime II shall be followed if no activity has been released during the previous 90 days.

E. FACILITY MONITORING SURVEILLANCES.

1. Alarms - Each of the items in Table H-1 shall activate an alarm. The elements activating these alarms shall be checked semi-annually.

4 Continuity test of the water intrusion alarm circuits shall be checked weekly (detectors are located in the waste water sump and biological l shield annulus around the Reactor Building). 4 The primary system pressure alarm may be out of service for up to 30 4 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 1 alarm is restored. The water intrusion alarms may be out of service for j 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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TABLE G-1 Environmental Surveillance Reaimes Numberof Stations Reaime Samole Media Indicator Backaround I II Water South Lagoon 1 0 G26b G26b River Water (Swan Creek) 1 1 Gib G26b Lake Water 1 0 Gib G26b Raw City Water

• O 2 G4b G26bl Sediment South Lagoon Sediment 1 0 G26g G26g  ;

River Sediment (Swan Creek) 1 1 G26g G26g i

Symbols:

G - Grab Sample or composite sample l Frequency Of Sampling:

1 1 -One week interval 4 - Fourweek interval i 26-Twenty six week interval l l

1 Type of Analysis:

b - beta g - gamma 4

Example: Gib - sample is collected at one week intervals and analyzed for beta radioactivity t

List of Cities Detroit Monroe l

7 Amendment No.11

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. j TABLE H-1 4 1

Fermi i Mc+ 4torina Elements i

Alarm Point

a. Primary System Pressure 1/2" W.C.G. minimum -

2 psig maximum l

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b. Water intrusion:

1. Biological Shield Annulus Greater than 6-inch l .

around the Reactor Bldg. accummulation of water

2. Waste Water Sump Greater than lower grating level l over sump pit i

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9 Amendment No.11