Proposed Tech Specs Re Access Control to Provide Flexibility While Maintaining Similar Control Over Access| ML20199H261 |
| Person / Time |
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| Site: |
Fermi  |
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| Issue date: |
01/28/1998 |
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| From: |
DETROIT EDISON CO. |
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| To: |
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| Shared Package |
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| ML20199F562 |
List: |
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| References |
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| NUDOCS 9802040453 |
| Download: ML20199H261 (5) |
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[Table view] |
Text
__
Ebclosure 2
', - NRC-98-0025
. Page1 ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGES Enrico Fermi Atomic Power Plant, Unit 1 NRC Docket No. 50-16 NRC License NO, DPR-9 t
9802040453 990128 PDR ADOCK 05000016 P
PDR,
=
Key; Protected Area N
Boundary l
Underground
=
Structures Fuel & Repair Building Health Physics Building (Dismantled) Slab Sodium Building
\\
Trestleway - -,
Primary Na Storage Sodium g,ent Llullding Tank Room Cold Trap
...g Tunnel Room
\\.
\\
Waste Gas Building NaK Room
\\
Inert Ga. ',
6 laert Gas g
Tunnel Reactor Building Building
'/. Annulus I
! Inert Gas Tunnel i
Primary t..
Shield I
FPD Tank j
Bldg.
b U
s...,
Reactor Building fWe's't'5al ' '..
East Na
{, Gallery j 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 Figure B-1 Facility Plan 3
Amendment No.
J
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 senice 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 modiocations 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 BUILDING
- 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 Building. Drains from this annulus shall flow to a sump pump located outside the Protected Area.
D. PRIMARY SYSTEMS / STORAGE TANK COVER GAS
- 1. Supply - The Primary System shall be connected to reserve and backup supplies of l
carbon dioxide (CO ). The pressure of the cover gas shall be maintained above 2
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 Sunnly - The Primary System cover gas backup supply shall be sufficient to supply the system for eight days under normal conditions.
3.
Surveillancu Cover gas (CO ) pressure in the Primary System shall be checked and recorded a.
2 weekly.
- b. The Primary System (CO ) cover gas pressure relief valve shall be tested annually.
2 4
Amendment No.
Observations of the nitrogen cover gas pressure over essentiaay empty sodium c.
storage tanks in the Sodium Building Complex sha!! 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 />.
l 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 l
any 30 day period.
E. FUEL AND REPATR BUILDING 1.
Access - Normal access to the Fuel and Repair Building shall be limited to the door at the southwest corner 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 SURVEILLANCES Prior to commencing discharge of any liquid emuent, 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 efliuent cannot properly be monitored, discharge of the emuent shall be discontinued.
During periods when radioactive emuents 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.
L.iauid 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.
2.
Gaseous Emuents - Gaseous emuents 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 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 effluents is commenced. If discharge ofliquid radiological emuents 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 No.
may be different than stated here; their authority and responsibility at the Fermi I facility
,shall, however, con espond to the following specifications,
- 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 the 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 health and safety.
- 3. Health Physics Technician - A 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,
- 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 4
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, o
- 5. (Deleted)
[
- 6. Dosimetry - Thermoluminescent Dosimeters (TLD) and Direct Reading l
Dosimeters (DRD) will be supplied for all persons who have been 11 Amendment No.
l