ML20199E655
| ML20199E655 | |
| Person / Time | |
|---|---|
| Site: | Paducah Gaseous Diffusion Plant |
| Issue date: | 11/17/1997 |
| From: | John Miller UNITED STATES ENRICHMENT CORP. (USEC) |
| To: | Paperiello C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| GDP-97-0196, GDP-97-196, TAC-L32033, NUDOCS 9711210271 | |
| Download: ML20199E655 (19) | |
Text
- - _ - -
United Sta':s Enrichment Corpor; tion --
e.
. 2 Democracy Center 6903 Rockledge Drive
. Bethesda. MD 20817 1et: (301)564 3200'.
~
Fax:(301) S64-3201 i
s JAucs H. MILLER Dr. (301)564-3309 VICE PRESIDENT, PRODUCTION Fax: (301) 571-8279 November 17,1997 Dr. Carl J. Paperiello SERIAL: GDP 97-0196 Director, Office of Nuclear Material 4
Safety and Safeguards Attention: Document Control Desk
' U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 f aducah Gaseous Diffusion Plant (PGDP)
Docket No. 70-7001
- Transmittal of Revision 19 to Paducah Certification Application
Dear Dr. Paperiello:
In accordance with 10 CFR Part 76, the United States Enrichment Corporation (USEC) hereby submits twenty (20) copies of Revision 19 (November 15,1997) to USEC-01, Applirtion for United States Nuclear Regulatory Commission Certification, Paducah Gaseous Diffusion Plam.
Revision 19 incorporates changes to the Technical Safety Requirements and Safety Analysis Report.
. These changes were previously submitted for your review in accordance with 10 CFR 76.45 and were approved as Amendment 10 to the Certificate of Compliance GDP-1 in your letter dated October 16,1997 (TAC NO. L32033). Revision bars are provided in the right-hand margin to identify the changes.
Revision 19 was implemented on November 15,1997.
Should you have any questions or comments on Revision 19, please call me at (301) 564-3309 or Steve Routh at (301) 564-3251. There are no new commitments made in this submittal.
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s II. Miller ce President, Production kbfbfb!NkN j7 2%h 1
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. Offices in Uvermore. Cakfomla Paducah, Kentucky Portsmouth. Oho Washington. DC m--:u.mm__m. _ _. -
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- r y.-
3 Dr. Carl J. Paperiello ?
November 17,1997--
ODP 97 0196 Page 2 -
Attachment:
' USl!C-01,. Application - for-United States Nuclear Regulatory. Commission
. Certification, Paducah Oaseous Diffusion Plant, Revision 19, Copy Numbers $67 through 586
Enclosure:
Aflidavit :
-cc:-
.NRC Region ill Office Copy Numbers 442,664 -
NRC Resident inspector - PODP Copy Number 697-NRC Resident inspector-PORTS Copy Number 665 Mr. Joe W. Parks (DOH)
Copy Numbers 641 through 644-5-
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OATil AND AFFIRMATION
' !! James 11. Miller, swear and affirm that I am Vice President, Production, of the United States Enrichment Corporation (USEC), that I am authorized by USEC to sign and file with the
~
Nuclear Regulatory Commissan this Revision 19 of the USEC-Application for United States Nuclear Regulatory Commission Certification, Paducah Gaseous Diffusion Plant (USEC-01), that I am familiar with the contents thereof, and that the statements made and matters set forth therein
- are true and correct to the best of my knowledge, information, and belief.
- c Jame I! Miller On this 17th day of November,1997, the ofTicer signing above personally appeared before me, I
is known by me to be the person whose name is subscribed to within the instrument, and acknowledged that he executed the same for the purposes therein contained.
In witness hereofI hereunto set my hand and official seal.
]
. $bb l
E/Af01 p
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V 'aurie M. Knisley, Notary Public' ~
l State of Maryland, Montgomery County My commission expires March 17,1998 l
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e TSR PODP November 15, 1997 Rev.19 a
f')\\
- SECTION 3.0 ADMINISTRATIVE CONTROlli f.
All nuclear critica'ity safety evaluations and approvals; g.
All proposed Requests for Enforcement Discretion; h.
NRC-required event reports.
3.10.6 RECORDS Written records of PORC reviews shall be maintained. As a minimum, these records shall include:
r.
Results of the activities conducted under the provisions of TSR 3.10; b.
Recommended approval or disapproval of items considered under TSR 3.10.5; c.
Determination of whether each item considered under TSR 3.10.5 requires prior NRC approval before implementation per 10 CFR 76.68 and 76.45.
d.
Minutes of PORC meetings, as approved by the chair or his/her designee.
y) c.
Appointments of PORC members and alternates.
3.11 NUCLEAR CRITICALITY SAFETY PROGRAM 3.11.1 A Criticality Safety Program shall be established, implemented, and maintained as described in the Safety Analy21s Report and shall address the following elements:
Adherence with ANSI /ANS Standards Nuclear Criticality Safety Responsibilities Process Evaluation and Approval Identification of SSCs and suppon systems necessary to meet the double contingency principle Design Philosophy and Review Criticality Accident Alarm System Coverage Procedure Requirements Posting and labeling Requirements Change Control Operation Surveillaace and Assessment Technical Aspects O
v 3.0 10
s
-- SAR PGDP November 15,1997.
'Rev.19 3.15.2.2 Nuclear Criticality Safety SSCs -
AQ Function These SSC: are those klanti6ed in NCSAs/NCSEs as required to meet the double contingency principle.
See Section 5.2.
Baundau A list of the NCS SSCs and the asrociated support systems required to meet the double contingency _
, principle are maintained within the System Boundary Definition Manuals.
3.15.2J Cylinder Valve Protector
- AQ Function The cylinder valve prtnector protects the cylinder valve from damage. If the cylinder valve is damaged, a UP. release couki result. 'Ihese protectors are used on product and talls cylinders (14-ton,10-ton, and 2.5-ton). -
See Sectkm 3.7.3 for a description of this system.-
Boundau
'!he boundary is the valve protector.
3.15.2.4 2S Sample Cylinders and 1-kg Sample Cylinders AQ Function These cylinders provide cemla'=nt for small amoras (1 to 2 kg) of liquid UF,.
- See Sectkm 3.7.1 for a description of this system.
Boundau These sample cylinders consist of the cylinder body plus adapters and the cylinder valve.
e
.e
SAR PGDP May 31,1996 Rev.3 3.15.2.5 Process Gas Coolers AO Function j
The stage coolers, the recycle coolers, ard the booster station coolers are R 114 heat exchangers which tegulate the temperature of the process gas. The function is to provide a toundary between R 114 and the J
process gas strean. Failure of the boundary could result in over-pressurization of the process system.
See Section 3.3.5.5.1 for a description of this system.
]Igundary Cooler componerns that separate R 114 and pncess gas.
3.15.2.6 UF, Scales AO Function The importance of the imam scales in C-310, C-315, C-333A, C-337A, and C-360 (basement) with respect to safety and safeguards is Nuc! car Material Co urol and Accountability (NMC&A) and prevention of overfilling a cylinder.
Tim scales are described in Fundamental Nuclear Materials Control Plan, ard Section 4.1.1.
Boundary
- Ihe Icam scales are klersiful and listed in Table 4.2 of the Fundamental Nuclear Material Control Plan.
included within the tvundary is the balance scale in its entirety.
3.15.2.7 inventory Instrumentation Require for Nuclear Material Accountability AO Functlan The inventory instrumentation performs a safeguards function by providing a means to demonstrate compilance with NMC&A requirements.
Also see the Fundamental Nuclear Materials Control Plan.
3.15-48
SAR-PGDP November 15,1997
[]
'Rev.19
/
The sanitary ard fire water system (SFWS, reference Section 3.9.2.3) currently supplies water to the C 315 automatic wet pipe sirinkler systems. A modification is planned to change this source to the high pressure fire water system (11PFWS, reference Section 3.15.2.11). The SFWS will be controlled as AQ until this modification is complete. After completion of that modification, the SFWS will be classified non-safety (NS).
Two trw cranes are being installed in C-360 (north) and C-337A (south). The components of these new cranes were included in the boundaries rather than the old cranes' components (reference Sections 3.15.1.1.7 and 3.15.1.4.10).
3.16.8 Identification of Nuclear Criticality Safety SSCs Section deleted.
l 3.16.9 CAAS Audibility
%cre are areas of process buildings where the CAAS horns (reference Sections 3.15.1.1.6, 3.15.1.2.5, 3.15.1.3.7. 3.15.1.4.9, 3.15.1.5.1, 3,15.1.6.1, 3.15.1.7.1, and 3.15.1.8.1) are not audible due to high ambia.nt noise levels. Modifications will be initiated to ersure that the CAAS alarm horns are unpable of being heard throughout the affected areas of the process buildings.
3.16.10 Autoclaves p)
\\'"
Several issues have been identified relative to the autoclaves that will be addressed as part of the Compliance Plan. These issues include the following:
The present instrumentation is not capable of measuring the vacuum required by the UF piping test procedure to verify integrity of piping connections, in addition, the present pressure monitorhig instrumeration on the autoclaves in C-333A, C-337A, and C-360 has too large of an accuracy range to ensure a sufticient margin between operating / trip pressures.
The SAR Upgrade activities have identified transfer and sampling piping in C-360 where the UF.
+
detection system initiates closure of only one containmera isolation valve.
ne autoclaves in C 360 do not have a low mstrument air pressure switch to initiate containment upon
+
loss of instrument air, The autoclaves in C-360 are not prevented from being inadvertently opened when an Autoclave High-
+
Pressure Isolation System containment isolation signal is present.
p 3.16-3
1 SAR PGDP July 26,1996 Rev. 4 The capability is not provided to leak test the following containment isolation valves for the autoclaves in C-333A, C-337A, and C-360:
- a. Air and steam inlet line valves.
- b. Valves t'etween the autoclaves and the cylinder over-pressure prote4>n system.
3.16.11 Power for Cell Trips The twtive power for tripping cell motors is provided by the DC power system and by the air pressure supplied to the *000" air circuh breakers. The specific values for battery performance requirements provided in the related TSR must be verified and the TSR and TSR basis statement revised accordingly. The air pressure requirements for the '000" air circuit breakers must be establisted and SAR Section 3.9.1.3.2 revised accordingly.
3.16.12 Slaving of CAAS Alarm Systems l
I Several leased buildings that are located within the evacuation area of buildings with criticality accident l
alarm system (CAAS) clusters do not have evac'tation horns and lights slaved to these clusters (reference l
Section 3.12.6). Furthermore, the criticality alarm horns from adjacent alartned buildings cannot te heard I
within most of tiese unslaved buildirgs. Therefore, the requirements that a criticalhy accident be annutriated l
Into all areas requiring evacuation is not met.
l O
3.16-4
t i
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APPLICATION FOR UNITED STATES NUCLEAR REGULATORY COMMISSION CERTIFICATION PADUCAll GASEOUS DIFFUSION PLANT REMOVE / INSERT INSTRUCTIONS REVISION 19 NOVEMBER 15,1997 Remove Pages Insert Pages VOLUMEI IJst of Effective Pages List of Effective Pages LOEP-l/LOEP-2, LOEP-7/LOEP-8 LOEP 1/LOEP 2, LOEP-7/LOEP-8 Section 3.15 Section 3.15 3.15-47/3.15-48 3.15-47/3.15-48 Section 3.16 Sectir
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