ML20147D974
| ML20147D974 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 12/15/1987 |
| From: | Sheeran R ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Rouse L NRC |
| References | |
| 28867, NUDOCS 8801200411 | |
| Download: ML20147D974 (10) | |
Text
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((L33pety IO87 k, License SNM-1067 Docket 70-1100 (Arog I'c, e '
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December 15, 1997 Q
U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. L. C. Rouse, Chief Fuel Cycles Safety Branch Subj ec t:
Reference:
R. E. Sheeran letter to L. C. Rouse, dated October 9, 1987
Dear Mr. Rouse:
t The referenced letter submitted several proposed changes to the subject lic ense. At a meeting held on December 10, 1937 in Silver Springs, !01 i
with members of your staff, several changes were made to the original i
submittal and these changes are incorporated in the attached submittal.
License pages affected by the proposed changes are as follows:
Deleted Page_
Added Page Page No.
Rev.
Page No.
Rev.
i I.1-3 4
I.1-3 5
I.1-4 3
1.1-4 4
I.3-9 5
I.3-9 6
i j
I.4-12 3
I.4-12 4
I.4-17 3
1.4-17 4
m I.4-18 3
I.4-18 4
s" II.8-75 0
p II.8-76 0
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O Very truly yours, Ec22 b
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R. E. Sheeran 4
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Power Systems 1000 Prospect Hill Road (203) 688 1911 t
Combustion Engineenng, Inc.
Post Offee Box 500 Telex: 99297 Windsor. Connectcut 06095-0500 j
l.5 Definitienn Any dafinitions which cro not definOd in stend:rd refsrcncos (o.g.,
ANSI-N-1.1-1976, "American Standard Glossary of Terms in Nuclear Science and Technology" or Title 10 of the Code of Federal Regulations) or that are unique to activities described in this license applications shall be defined where first used in the application.
1.6 Authorized Activities The primary activities carried out in buildings at the Windsor site include, but are not limited to the following:
Bldg. il & 1A -
Storage and use of small quantities of Radioactive o
Material (1700 Gms U235)
Bldg. 42 &.2A -
Product Development Activities (17 00 Gms U2 3 5).
Bldg. 43 & 3A - Storage of small quantities of Radioactive Material (1700 Gms U235)
Bldg. 5 - Product Development Ac'tivities.
Bldg. 6 - Waste water processing from manufacturing and product development activities.
Bldg. 16 -Product Development Activities (1700 Gms U235)
Bldg. 17 -Manufacture of fuel assemblies utilizing low enriched uranium (up to 4.1 weight percent U235) in the form of uranium oxi3e powder, pellets, rods, and in assemblies.
Bldg. 18 -Product Development Activities (1700 Gms U235).
Bldg. 21 -Storage of SNM in shipping containers.
Windsor Site - Residue from prior operations, not to exceed 350 gms 235 U
in any one location.
Additional locations to be separated from one another by a minimum of 12 feet.
1,7 Exemptions and Special Authorizations Licensed activities in Bldgs.
1, lA, 2,
2A, 3,
3A, 5,
6, 16 and 18 shall License No. SNM-1067, Docket 70-1100 Rev. 5 Date: 12/15/87 Page: I.1-3
ba of a product development noturo end ths materici any ultimntoly b3 roturned to the Nuclear Fuel Manufacturing facility.
These transfers shall not require the issuance of applicable NRC transfer documents, but shall be trcnsferred in accordance with the provisions of this license, and shall be handled as a departmental transfer and shall be controlled by the Fundamental Nuclear Material Control Plan (FNMC) referenced in Section 9.0 of this application.
- Building 1, lA, 2,
2A, 3, 3A, 16 and 18 shall be exempt from the
- rcquirement of a criticality monitoring system as specified in 610CFR70. 24 (a) (1).
The above buildings are not required to have a
- criticality monitoring systems because of the exemptions allowed in
- 10CFR70.24(a).
- In each area where labelling of all containers is not in accordance with
- 10CFR20.203(f), all personnel ingress locations shall be posted with a sign
- stating that "Every container or vessel in this area, unless otherwise
- identified, may contain radioactive material."
License No. SNM-1067, Docket 70-1100, Rev. 4 Date: 12/15/87 Page:I.1-4
first b nk of cbsoluto filt0ro.
The proccuro drcp for c11 syctCao ch ll b3 ch ckOd conthly and docum:nt0d.
Whtn tho foco volocity ct c ventilated hood drops below 100 fpm, the hood filters or ventilation system filters will be changed, brushed, or knocked down to increase the air flow to 100 fpm minimum or the hood will not be used to handle radioactive material.
Face velocities will be checked monthly in Product Development.
The filters in these stacks shall be tested either by 1) counting samples immediately after 1/2 hour of operation or 2) DOP testing the filters in accordance with ANSI standards. Such testing shall be done after all filter changes or movement of the filters to assure they are adequately filtering the exhaust air.
The results of these tests shall be documented.
Each ventilating filter system described in Section 3.2.3 shall be equipped with an instrument that measures the pressure drop continuously.
3.2.
Instrumentation capabilities of radiation detection and measurement instrumentation shall be as follows:
Alpha Counting System 10 - 10,000 dpm Alpha Survey Meters 0 - 50,000 counts per minute Beta-Gamma Survey Instruments
.05 mR/hr - 200 mR/hr Neutron Survey Instruments
.5 - 5,000 mrem /hr A sufficient number of the instruments, meters and systems listed above shall be maintained operational to adequately conduct our Health Physics program.
Additional instrumentation is maintained for emergency use as outlined in Part I Section 8.
The detectors for the criticality alarm system are calibrated semi-annually and following any repair that affects the accuracy of the measurements.
All other instruments are calibrated semi-annually and following any repair that affects the accuracy of the measurements.
The calibration of the survey instruments shall meet the specifications described in Section 1.11 of Regulatory Guide 8.24, "Health Physics Survey During Enriched License No. SNM-1067, Docket 70-1100 Rev. 6 Date: 12/15/87 Page:I.3-9
8.12, "Criticality Accid:nt Alcrm Systcm" chn11 b3 maintain 0d in Product Development areas and the manufacturing facility.
The detectors operate in the range of 1-10,000 mR/hr.
The locations of the detectors within the manufacturing facility 0
are shown on Page II.8-75 and within the Product Development 0
on Page II.8-76.
The radiation intensity is shown on a central panel located in the Building 17 Health Physics office
-0 O
for Building 6, 17 and 21, and in the main hallway in Bldg. 45 0
of Product Development.
There is an alarm which serves as a local and general audible radiation evacuation alarm.
When the alarm is sounded, the Emergency Plan is immediately put into effect.
The monitors are connected to the emergency power system, which is supplied to all emergency lights and alarms in the event of a general power failure within the facility.
This electrical system renders the alarm system 0
operative at all times.
Operation is further enhanced by visual observation by Health Physics personnel.
Alarm operational tests of the radiation monitors are performed monthly by Health Physics personnel.
A radioactive source is used to perform these tests.
The entire system is calibrated semi-annually and following any repair that affects the accuracy of the measurement.
4.3 Specific Criticality Safety Criteria Specific criticality safety criteria in addition to the general criteria described in Section 4.2 are necessary to assure nuclear safety for several process operations, as described below:
^
License No. SNM-1067, Docket 70-1100 Rev. 4 Date: 12/15/87 Page: I.4-12
l This Page 'ntentionally Left Blank l
License No.
SNM-1067, Docket 70-1100 Rev. 4 Date:
12/15/87 Page:
I.k-17
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t Thir, Page Intentionally Left Blank License No. SNbl067, Docket 70-1100 Rev. 4 Date:
12/15/87 Page: I.4-18
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.I PE M -- S ise No. SW.1067 Docket 70-1100 Revision:
'd Date: 12/15/87 f
P69e: 11.8-76
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