ML20202H256
| ML20202H256 | |
| Person / Time | |
|---|---|
| Site: | Portsmouth Gaseous Diffusion Plant |
| Issue date: | 02/10/1998 |
| 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-98-0020, GDP-98-20, TAC-L32034, NUDOCS 9802200338 | |
| Download: ML20202H256 (17) | |
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.4 USEC
. A Global Energy %noany JAMES H. MILLER Dir; (301) 504-3309 VicE PRESIDENT, PRODUCTION Fax: (301) 571-8279 February 10,1998 Dr. Carl J. Paperiello SERIAL: GDP 98-0020 Director, OfTice of Nuclear Material Safety and Safeguards Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Portsmoun Gaseous Diftsion Plant (PORTS)
Docket No. 70-7002 Transmittal of Revision 18 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 18 (Febmary 6,1998) to USEC-02, Application for United States Nuclear Regulatocy Commission Certification, Portsmouth Gaseous Diffusion Plant.
)
Revision 18 incorporates changes to the Technical Safety Requirements (TSRs). These changes were previously submitted for your review in accordance with 10 CFR 76.45 and were approved as Amendment 6 to the Certificate ofCompliance GDP-2 in your letter dated December 8,1997 (TAC NO.
L32034). Revision 18 also includes editorial corrections to the List of Effective Pages for Volumes 1 and 2 of the certification application and to the header for TSR page 3.0-10. Revisica 18 was implemented effective February 6,1998.
Should you have any questions or comments on Revision 18, please call me at (301) 564-3309 or Steve Routh at (301) 564-3251. There are no new commitments made in this submittal.
Sincerel,
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9802200338 980210 ADOCK0700g2
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PDR es H. Miller ce b esident, Preducticn g
6903 Rockledge Drive, Bethesda. MD 20817-1818 Telephone 301-564-3200 Fax 301-564 '201 http://www.mec. corn OfTices in Livern' ore. CA P ducah, KY Portsmouth, OH Washington DC
Dr. Carl J Puw !. llo
' February 10,1998 GDP 98-0020 Page 2
Attachment:
USEC-02, ' Application for United States Nuclear Regulatory Commission Certification, Portsmouth Gaseous Diffusion Plant, Redsion 18, Copy Numbers 1 through 20
Enclosure:
Aflidavit cc:
NRC Region 111 Oflice Copy Numbers 21,172 NRC Resident inspector - PGDP Copy Number 22 Mr. Joe W. Parks (DOE)
Copy Numbers 24 through 28 l
l h
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OATH AND AFFIRMATION I, James H. 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 Commission this Revision 18 of the USEC Application for United States Nuclear Regulatory Commission Certifica* ion, Portsmouth Gaseous DitTusion Plant (USEC-02), that i
I 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.
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James H. Miller On this loth day of February,1998, the officer signing above personally appu. red before me, is known by me to be the person whose name is subscribed to withm the instrument, and acknowledged that he executed the same for the purposes therein contained.
In witness hereofI hereunto set my hand and official seal.
llk
$L!r d Idurie M. Kaisley, Notary Public g
State of Maryland, Montgomery County My commission expires March 17,1998
4 APPLICATION FOR UNITED STATES O
NUCLEAR REGULATORY COMMISSION CERTIFICATION 4
a PORTSMOUTH GASEOUS DIFFUSION PLANT REMOVFJINSERT INSTRUCTIONS REVISION 18 February 6,1998 Remove Pages Insert Pages VOLUME 1 List of Effective Pages List of Effective Pages i & ii i & ii xvii & xviii xvii & xviii VOLUhE 2 List of Erfective Pages List of Effective Paga i & ii i & ii xvii & niii xvii & niii VOLUME 4 List of Effcetive Pages List of Effective Pages ii ii O
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Rev.18 SECTION 2.1 SPECIFIC TSRs FOR X-342, X-343, AND X-344 FACILITIES O
2 2 3 tor'Tixo co" Tao'stTT'xos. 'at'T xo coxorT'oss to OPERATION, SRVEILLANCES 2.1.3.5 Autoclave Shell High Pressure Containment Shutdown APPLICABC ITY:
Autoclave Operational Modes II, IV, VI LCO:
The autoclave shell high pressure containment system shall be operable:
ACTIONS:
Condition Required Actions Completion Time A.
One instrument channel A.1 Restore instrument Prior to initiating a I
inoperable channel to operable status, new Operating l
NOTE Cycle l
The current Operating I
Cvele may be comoleted.
4 B.
Both instrument B.1 Place autoclave in Mode 1 Hour channels inoperable Vll C.
One containment C.1 Restore containment Prior to initiating a l
Os isolation valve on one isolation valve to operable new Operating I
or more autoclave status.
Cycle I
penetration inoperable NOTE l
The current Operating I
Cvele may be completed.
l D.
All containment D.1 Place autoclave in Mode 1 Hour l
isolation valves on any VII one autoclave penetration inoperable E.
Steam leakage around E.1 Place autoclave in Mode 1 Hour I
autoclave loc!ing ring VII 2.1-11
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TSR-PORTS February 6,1998 Rev.18 s
SECTION 2.1 SPECIFIC TSRs FOR X-342, X-343, AND X-344 FACILITIES 2.1.3 LDIITING CONTROL SETTINGS, LBIITING CONDITIONS FOR OPERATION, SURVEILLANCES 2.1.3.5 Autoclave Shell High Pressure Containment Shutdown (continued)
SURVEILLANCE REQUIREMENTS:
Frequency Surveillance Quarterly SR 2.13.5.1 Perform channel functional test to verify the High Pressure Containment system will actuate ht or below 15 asic Semiamually SR 2.1.3.5.2 Calibrate shell high pressure shutdown instrumentation at s 15 osie Quarterly SR 2.1.3.5.3 Leak rate the autoclave by pressurizing the i
autoclave to at least 90 psig and verify that the system pressure loss is less than or equal to 10 psig/hr for each l
of the following autoclave loop containment valve conditions:
i
- 1. Inner loop valves closed and Outer loop valves i
(O cpen I
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- 2. Inner loop valves open and Outer loop valves I
closed OR Perform a leak rate test where the maximum acceptable leakuge shall not exceed 12 scfm at a minimum test pressure of 90 psig for each of the same conditions as stated above.
i Note: Allowable test tolerance to cover instrument drift and uncertainties during normal ooeration = +2 osie BASIS:
The steam used to heat a cylinder within an autoclave is controlled at approximately 5 psig.
Therefore, when the autoclave internal pressure reaches the s 15 psig setpoint, the operating logic assumes that a UF, release has occurred within the autoclave and causes the containment valves to close, preventing an external release of UF.. The 15 psig represents the lowest pressure at which it can be assumed that it is not due to a steam control failure and yet gives the early indication that a UF release is in progress. Testing the containment system at 90 psig is 6
representative of the peak credible accident pressure that could be attained assuming functioning of safety systems, design features and administrative controls to prevent rupture of a cylinder or pd pigtail. The set point value corresponds to the trip set point established under DOE 5481.1B in 1985 and amended by DOE approval in 1995 to allow a 2 psi tolerance to comply with the definition of " Allowable Value" in ANSI /ISA-S67.04-1988 [SAR Section 3.2.1.1.1].
2.1-12
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Rev.18 a
SECTION 3.0 ADMINISTRATIVE CONTROLS
(
Report, and Supplemental Environmental Information Related to Compliance Plan that are included in the certification application.
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 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:
Results of the activities conducted under the provisions of TSR 3.10; n
a.
(
~
b.
Recommended approval or disapproval of items cons!Sred under TSR 3.10.5; l
Determination of whethe.r each item considered under TSR 3.10.5 requires prior l
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, impleIAented, 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 Ide.ntification of SSCs and support systems necessary to meet the double contingency I
principle.
Design Philosophy and Review (q
Criticality Accident Alarm System Coverage
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Procedure Requirements 3.0-10
,