ML20235J425
| ML20235J425 | |
| Person / Time | |
|---|---|
| Site: | 07003013 |
| Issue date: | 09/08/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Thompson H NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 28559, 3559K, NUDOCS 8710010441 | |
| Download: ML20235J425 (7) | |
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CN Commonwealth Edison M'
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Chicago, Illinois 60690 0767 LRETURN TO' 393-55 September 8,.1987
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Mr. H. L. Thompson, Director Office'of Nuclear Material Safety and Safeguards 2
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Subject:
Braidwood Station Unit 2
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Application for Amendment to' A
NRC Materials License No. SNM-1945 NRC Docket No. 70-3013 e
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Reference (a): July 27, 1987 L.C. Rouse letter
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SEP 10Jgg7 y 8 (b): May 6, 1987 S.C. Hunsader letter C
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Dear Mr. Thompson:
g ;g Pursuant to 10 CFR Part 70.34c r' commonwealth Edison Company proposes to amend Special Nuclear Materials (Sist) License SNM-1945 (Reference (a))
which authorizes receipt, possession, inspection and storage of uranium in the U-235. isotope contained in fuel assemblies. The proposed amendment updates the Physical Security Plan applicable to Braidwood Station. The revised License pages are contained in Attachment A.
As the construction phase of Braidwood Unit 2 comes to a conclusion and reduction in contractor traffic in the fuel handling area occurs, the temporary security barriers described in the " Security Plan for the Braidwood Nuclear Power Station" will no longer be required. At such a time, the temporary barriers will be removed, and the entire Fuel Handling Buidling will be governed by the " Security Plan for the Braidwood Nuclear Power Station" as'a controlled access area. Though changes wi}l be made in l
the prescribed security barriers, overall, appropriate security measures will remain in place.
Commonwealth Edison is notifying the State of Illinois of our application for this amendment by transmitting a copy ot' this letter and its attachments to the designated State Official.
8710010441 870908 ADOCK 0700g1
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H.L. Thompson September 8, 1987 Pursuant to 10 CPR Part 70.21(e), no fee is required to accompany this amendment request.
Please address any questions concerning this matter to this office.
Very truly yours,
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S. C. Hunsader Nuclear Licensing Administrator cc:
S. Sands (NRR)
D. McCaughey (NMSS)
NRC - RIII M.C. Parker - State of Ill.
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ATTACHMENT A PROPOSED CHANGES TO SPECIAL NUCLEAR MATERIALS l
LICENSE SNM-1945 l
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Revised Pages:
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- Page 2 of 2 of Materials License SNM-1945 l
- Pages 18 and 19 of the Commonwealth Edison May 6, 1987 application (Reference (b))
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MATERIALS UCENSE I
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- 13. The licensee shall maintain and fully implement all provisions of the Comission l
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approved Physical Security Plan, including changes made pursuant to the authority E.
N of 10 CFR 70.32(e). The approved Physical Security Plan consists of RexisignJ1 to the (uclear Matplials Secu ity for Co nwealtVEdisot Com/Securify Plan for Special)bmitted by/ letter da I
pril 19. 1985 ffhePhysical l
pany,Traidwoodgtation,"fuDe withheld from pubTic disclosure pursuant to 10 CFR 2.790 y
ecurity Plan snati
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)i FOR THE NUCLEAR REGULATORY COMMI SION
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JUL 2 71987 By:
Leland C. Rouse ti Date:
ivision of Fuel Cycle, Me, dical f(. i
/ a emic, and Comercial Use' Safety, NMSS g
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,a 1.2.5 The fire protection measures for the Fuel Handling Building consist of separation of the area from the rest of the plant by a fire barrier.
Fire dampers are provided in the fire wall.
Fire dampers are fusible link type which will be closed when the temperature exceeds 165*F.
There are no safety-related cable trays in this area. All cables in the area not in motor-control cubicles are in conduit.
The new fuel storage racks are designed to preclude criticality when subjected to water spray.
Nonfogging type nozzles are used for the manual hose stations located in this area to preclude tha optimum moderation condition for the new fuel storage racks.
Refer to Byron /Braidwood Fire protection Report, Section 2.3.12 (Attachment B).
Portable fire extinguishers and four manual hose stations constitute the fire protection equipment.
Two portable fire extinguishers and two manual hose stations are located on elevation 426 feet, and two i
l manual hose stations on elevation 401 feet.
Similar equipment can be I
brought in from the Auxiliary Building at elevation 426 feet, if needed.
Ionization detectors are provided for elevation 401 feet which alarm and annunciate locally and in the Control Room.
The large area above elevation 426 feet is provided with ultraviolet detectors, which will be more effective than ionization detectors for this area due to the large room volume.
These also alarm and annunciate in the Control Room.
b.
- blue Pcwer 1.2.6 The Security plan for Opccial %c10cr-#aterial at-Braidwood Station A
will be implemented during fuel receipt, handling, and storage.s-Tha following are areas where new fuel may reside for varying periods of ]
time prior to reactor core loading:
1.
The area immediately outside the fuel handling building.
2.
The following creas of the fuel handling building:
k Unloading area of the fuel handling building trackway a.
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New fuel unloading area (for removal from shipping containers) c.
New fuel storage racks d.
Spent fuel storage pool L - h n M ph f cd pec h $$a d Mear N P*
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During plant construction, whenever fuel is being received, handled or stored in any of these areas, access to that area will be controlled.
The controlled access area will be defined by using a locked physical barrier or by watchmen stationed at cach functional entrance to the area. Unauthorized access will be prevented by manning the personnel entry points of these areas to limit entry to those individuals identified as having a need to enter.
The physical barriers will be patrolled by watchmen to verify continued integrity and any irregularities shall be reported immediately to the Shift Supervisor.
An access authorization list will be maintained which lists all individuals having a need to work within the controlled access areas.
1.3 Physical Protection No U-233 or plutonium is to be possessed under the license and the quantity of U-235 to be possessed is classified as "special nuclear material of low strategic significance".
Commonwealth Edison Company will comply with all applicable sections of 10 CFR Part 73, " Physical Protection of Plants and Materials", particularly paragraph 73.67(f),
Fixed Site Requirements for Special Nuclear Material of Low Strategic Significance, as outlined in the " Security Plan for-Epe;icl Ng;1ea - 4Lt c
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1.4 Transfer of Special Nuclear Material 1.4.1 Westinghouse. the fuel fabricator, is responsible for the shipment of fuel to Braidwood Station.
1.4.2 Any unirradiated fuel to be returned to Westinghouse will be packaged and shipped in the containers originally used to ship fuel to l
Braidwood Station.
1.4.3 The applicable provisions of 10 CFR Part 70 related to the control and accounting practices of special nuclear material are complied with using Commonwealth Edison Company's (CECO) Nuclear Procedures Nos. I through 8 (Attachment C).
These Nuclear Procedures clearly define the organization, responsibilities, and facilities comprising CECO's Nuclear Material Control System, which provide a method for detecting l
any loss or unauthorized diversion of nuclear material.
An index of specific nuclear procedures is shown in Table 1.4.3.
A few key positions in implementing the CECO Nuclear Procedures and l
their responsibilities are discussed below.
The Nuclear Materials Safeguards Manager (UMS Manager) will have overall responsibility for surveillance and control of nuclear material.
His specific duties include preparing and filing Nuclear Material Transaction Reports, Nuclear Material Balance Reports and Physical Inventory Listings as may be required.
19 0661m(041387) 0327A L_-___-___________--_.___._____
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