ML20199A532
| ML20199A532 | |
| Person / Time | |
|---|---|
| Site: | Portsmouth Gaseous Diffusion Plant |
| Issue date: | 01/20/1998 |
| From: | Rifakes G 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-98-0005, GDP-98-5, TAC-L32035, NUDOCS 9801280006 | |
| Download: ML20199A532 (19) | |
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..USEC A clot,at Energy company GEORGE P. RIFAKES Dir; (301)(44 3301 EXECUTIVE VicE PRESIDENT, OPERAflONS Fax: (301) 064-3208 January 20,1998 Dr. Carl J. Paperiello SERIAL: GDP 98 0005 Director, Office of Nuclear Material Safety and Safeguards Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Portsmouth Gascous Diffusion Plant (PORTS)
Docket No. 70 7002 Transmittal of Revision 17 to Portsmouth 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 17 (January 12,1998) to USEC-02, Application for United States Nuclear Regulatory Commission Certification, Portsmouth Gaseous Diffusion Plant.
Revision 17 incorporates changes to the Safety Analysis Report and Technical Safety Requirements.
These changes were previously submitted for your review in accordance with 10 CFR 76.45 and were approved as Amendment 7 to the Certificate of Compliance GDP 2 in your letter dated December 12, 1997 (TAC NO.1.32035). Revision 17 was implemented effective January 12,1998.
Should you have any questions or comments on Revision 17, please call me at (301) 564-3301 or Steve Routh at (301) 564-3251. There are no new commitments made in this submittal.
Sincerely,
$f"*'
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George P. Rifakes h\\qd Executive Vice President, Operations 9901290006 990120 PDR ADOCK 07007002
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l ll 6903 Rockledge Drive. Bethesda. MD 20817 1818 Telephone 301564-3200 Fu 301564 3201 http://www.mec.com Omces in Livermore. CA Padacah hY Portsmouth. Oil Washington. DC
Dr. Carl J. Paperiello
- January 20,1998 -
ODP 98 0005, Page 2
Attachment:
USEC-02,_ Application for United States Nuclear Regulatory Commission
~
- Certill 41on, Portsmouth Gaseous Diffusion Plant, Revision 17 Copy Numbers 1 through 20
Enclosure:
Affidavit ec:
NRC Region ill Omcc Copy Numbers 21,172
- NRC Resident inspector PGDP Copy Number 22
= Mr Joe W. Parks (DOE)
Copy Numbers 24 through 28 -
8
OATil AND AFFIRMATION l
I, George P. Rifakes, swear and aflirm that I am Executive Vice President, Operations, of the United States Enrichment Corporation (USEC), that I am authorized by USEC to sign and file -
with the Nuclear Regulatory Commission this Revision 17 of the USEC Application for United
- States Nuclear Regulatory Commission Certification, Poitsmouth Gasecus Diffusion Plant (USEC.
02), 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, infomiation, and belief.
l A
George P. Rifi[es On this 20th day of January 1998, the oflicer signing above personally appeared before me, is known by me to be the person whow 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.
. b6LS h.
Ax nt 1/aurie M. Knisley, Notary Public //
State of Maryland, Montgomery Cddnty -
My commission expires March 17,1998 i
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APPLICATION FOR UNITED STATES NUCLEAR REGULATORY COMMISSION CERTIFICATION PORTSMOUTH GASEOUS DIFFUSION PLANT REMOVE / INSERT INSTRUCTIONS REVISION 17 JANUARY 12,1998 Remove Pages Insert Pages VOLUME 1 List of EfTective Pages List of Effective Pages i/il, xvii /xviii 1/il, xvii /xsiii VOLUME 2 List of Effective Pages List of Effective Pages 1/il, xvii /xviii 1/il, xvii /xviii Pgs. 3.8-43/44,3.9 5/6 Pgs. 3.8 43/44,3.9 5/6 VOLUME 4 List of Effective Pages List of Effective Pages ii, iv 11, iv 3.0-10 3.0 10 el f
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SAR PORTS April 15,1997 Rev.8 5.
CNeultry associated with the local alarm.
Note:
This system is fall safe upon loss of the electrical suppon system.
3.8.1.8 X 700. X-710, X 720, X-760, and XT447 Q Boundary Dennidons 3.8.1.8.1 Facilky Cridemiky Accident Alarm System O Funcdon ne Criticality Accident Alarm System monitors the facilities for a nuclear criticality and alarms notifying personnel that humediate evacuation must occur. An electrical support system failure is backed up by rechargeable banery packs, which will support the system for a mimmum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and the loss will result in a trouble alarm, ne portion of this system which alarms notifying the general population outside the irmnediate vicinity is controlled as AQ under Section 3.8.2.23.
See Section 3.6.2 for a description of the system.
Boundarv ne Criticality Accident Alarm System boundary includes the following:
1.
Radiation detection cluster unit; 2.
N Strombos born; 3.
Na supply; 4.
Associated N: piping and tubing; and 5.
Circuitry associated with the local alann.
Note:
This system is fail safe upon loss of the electrical support system.
8.1.9 Liquid UF. Cylinder Q Boundary Definition 3.8.1.9.1 UF, Cylinders Q Function Cylinders utilized to contain UF, have been designed, built and tested to ANSI Nik.1 (subject to the clarifications in Chapter 1, Appendix A) ano a prescribed minimum volumt; specified in USEC-651 This ensures safe containment of UF thrcr ghout the enrichment process, including transport, sampling, feedmg e,.
filling, and storage and prevent a release of liquid UF., The issue of fail safe is not applicable to this, system.
3.8-43 i-J
SAR-PORTS
.ianuary 12, 1998 Rev.17 The 1S and 2S cylinders are not irm:luded as Q due to their small size. These cylinders are classified AQ.
See Section 3.2.1 for a description of the system.
Boundary The UF. cylinder boundary includes the following:
1.
Cylinder; 2.
Cylinder valve; and 3.
Cylinder plug Notes:
a.
The valve protector is AQ, see Section 3.8.2.20, b.
No support systems are required.
3.6.2 AQ Boundary Definitions This section describes the AQ SSCs at PORTS. The AQ function and boundary of each of these SSCs are described in the followirs paragraphs.
3.8.2.1 Nuclear Criticality Safety SSCs AO Func^ ion These SSCs are those identified in NCSAs/NCSEs as required to meet the double contingency principle.
See Section 5.2.
Boundary SSCs and the associated support systems required to meet the double contingency principle are l
maintained within the System Boundary Definition Manuals.
l 3.8.2.2 UF, Process Piping and Equipment AO Fmiction UF. process piping and equipment provides a containment boundary for UF. during the enrichment process.
3.844 I
SAR PORTS January 12,1998 Rev.17
,,'l,3.9.9 Desi, Moul5 cations to Support Q and AQ Boundary Dennitions C
As part of the SAR U:sn activity, an engineering evaluation will be performed to assess the following issues to determine L w%:atioot are necusary to place the plard in a fail safe configuration.
If modifications 'are necessary, cry will b initiated.
Currently the UF, pigtail heaters remain energized upon loss of plant air (reference Sections 3.8.1.1.4, 3.8.1.2.4 and 3.8.1.3.5).
Currently valves located in the autoclave feed lines wili fail as-is (reference Sections 3.8.1.4.4, 3.8.1.4.8, 3.8.1.5.4 and 3.8.1.5.8).
Currently the d=ghter cylindu safety valves located between the cylinder and the pigtail at each autoclave will fail as-ir on loss of air (reference Sections 3.8.1.6.4 and 3.8.1.6.8).
Currently the autoclave UF. drain line valves will fall as-is on loss of electric or air (reference Sections 3.8.1.6.4 and 3.8.1.6.8).
Currently the autoclave smoke detection systems do not fail to a trouble alarm (reference Section 3.8.1.6.4),
3.9.10 Identification of Nuclear Criticality Safety SSCs Section deleted.
l 3.9.11 UF. Smoke Detection :.; stems UF. smoke detection systems (see Sections 3.8.1.2.3 and 3.8.1.3.4) in LAW and TAILS areas may not contain a sufficient number of Q smoke detectors necessary to provide adequate detector coverage.
The associated OSR for these areas took credit for detectors that do not meet current QAP requirements for Q SSCs. As part of the SAR Upgrade activity, an engineering evaluation will be performed to assess datactnr coverage requirements for these areas. This will determme if changes are necessary to improve Q detector coverage in these areas.
3.9.12 Top Purge Assay As described in Section 3.7, the following Compliance Plan items are necessary to address top purge assay issues:
3.9-5 Y
SAR-PORTS July 26,1996 Rev. 4 Additional scenarios will be developed and analyzed for unauthorized removal paths of matenal enriched above 9.99 wt % assay, and any necessary additional controls will be established and implemented to detect and deter unauthorized removal of this material from the cascade and from the X-326 facility.
i Controls and piduras will be developed and implemented to detect and protect against credible scenarios for unauthorized removal of significant quantities of SNM of moderate strategic significance.
Controls and monitoring activities will be developed and implemented to preclude and detect the presence of more than 50 kg SU contained in gaseous UF.,
enriched from 10.00 to 19.99 wt %, within units X-25-7 and X-25-2, interconnecting piping, and the X-326 surge drums.
Additional controls and meedures will be developed and implemented to ensure i
that nuclear criticality safety is addressed for all operating conditions.
Additional controls and monitoring activities will be developed and implemented to preclude and detect the presence of uranium enriched to > 9.99 wt % within the tcp purge cascade in quantities that would lead to exceeding Category III limits ac.oss all USEC-leased and certified ; paces following completion of the HEU refeed program.
1 3.9-6 f
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SAR-PORTS January 12. 1998 Rev.17 SECTION 3.0 ADMINISTRATIVE CONTROLS Report, and Supplemental Environmental Information Related to Compliance Plan
~~
that are included in the certification application.
I d.
All proposed changes to the TSRs, the TSR basis statements, the Certificate of Compliance, or the Compliance Plan; All proposed changes to the plant or the plant's operations, including tests and e.
experiments, that require a written safety analysis in accordance with 10 CFR 76.68.
f.
All nuclear criticality safety evaluations azul 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:
Results of the activities conducted under the provisions of TSR 3.10; a.
b.
Recommended approval or disapproval of items considered under TSR 3.10.5; Determination of whether each item considered under TSR 3.10.5 requires prior c.
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, e.
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 Analysis Report and shall address the following elements:
Adherence with ANSI /ANS Standards Nuclear Criticality Safety Responsibilities Process Evaluation and Approval Identification of SSCs and support systems necessary to meet the double contingency I
principle.
I Design Philosophy and Review Criticality Accident Alarm System Coverage Procedure Requirements i
3.0-10 l
.