ML20135F587

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Submits Rev 7 to USEC-01,application for Us NRC Certification,Paducah Gaseous Diffusion Plant
ML20135F587
Person / Time
Site: Paducah Gaseous Diffusion Plant
Issue date: 03/07/1997
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-97-0031, GDP-97-31, NUDOCS 9703130117
Download: ML20135F587 (13)


Text

6 United States Enrichment Corporation 2 Democracy Center 6903 Rockledge Drive Bethesda. MD 20817 Tel. (301) 564-3200 Utiiteel $lates Eiirieb:. erit Corpiratiori JAMES H. MILLER Dir: (301) 564-3309 VICE PRESIDENT, PRODUCTION Fax: (301) 571-8270 March 7,1997 Dr. C-1 J. Paperiello SERIAL: GDP 97-0031 Din -

J, Office of Nuclear Material Safety and Safeguards Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Paducah Gaseous Diffusion Plant (PGDP)

Docket No. 70-7001 Transmittal of Revision 7 to Paducah Certification Application

Dear Dr. Paperiello:

In accordance with 10 CFR Part 76, the United States Enrichment Corporation (USEC) h,:reby submits twenty (20) copies of Revision 7 (March 7,1997) to USEC-01, Application for United States Nuclear Regulatory Commission Certification, Paducah Gaseous Diffusion Plant.

Revision 7 incorporates changes to Technical Safety Requirement (TSR) Basis statements to clarify the applicability of certain codes and standards. These changes have been reviewed in accordance with the requirements of 10 CFR 76.68 and have been determined not to require prior NRC approval.

Revision bars are provided in the right-hand margin to identify the changes.

Should you have any questions or comments on Revision 7, please call me at (301) 564-3309 or Steve Routh at (301) 564-3251.

Si grely,

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y (: GQf J-es H. Miller ice President, Production 9703130117 970307 PDR ADOCK 07007001 l$!]yK3[i%l'$$$l[$$$

PDR Offices in Paducah, Kentucky Portsmouth. Ohio Washington. DC

Dr. Carl J. Paperiello March 7,1997 GDP 97-0031 Page 2 e

Attachment:

USEC-01, Application for United States Nuclear Regulatory Commission Certification, Paducah Gaseous Diffusion Plant, Revision 7, Copy Numbers 567 through 586 l

Enclosure:

Affidavit cc:

NRC Region III Office Copy Numbers 442,664 NRC Resident Inspector - PGDP Copy Number 697 NRC Resident Inspector - PORTS Copy Number 665 Mr. Joe W. Parks (DOE)

Copy Numbers 641 through 644

OATH AND AFFIRMATION I, James H. Miller, swear and aflirm 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 7 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 tme and correct to the best of my knowledge, information, and belief.

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Ja

. Miller Subscribed to before me on this I day of)f/AM,1997.

MJ WMdaenu Notary Public BERNICE R. LAWSON NOTARY PUBllC STATE OF MARYLAND Certificate filed in Montgomery County Commission Expires August 1,1997

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' (y, NRC Certification Application Paducah Gaseous Diffusion Plant (USEC-01) i Revision 7 Remove / Insert Instructions Remove Pages Insert Pages Technical Safety Requirements - Volume 4 Do not remove section tabs List of Effective Pages List of Effective Pages ii, iii ii, iii Section 2.1 Section 2.1 j

2.1-4, 2.1-50 2.1-4,2.1-50 Section 2.2 Section 2.2 2.2-3, 2.2-9 2.2-3, 2.2-9 Section 2.3 Section 2.3 2.3-50 2.3-50 Section 2.4 Section 2.4 2.4-4, 2.4-12 2.4-4, 2.4-12 Ah O

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' TSR-PGDP.

March 7,1997 Rev.7 4

i LIST OF EFFECTIVE PAGES

  • O Pages Revision Pages Revision ii 7

2.1-24 6

iii 7

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' TSR-PGDP '

March 7,1997-

.Rev.7

'i Pages Revision.

Pages Revision 2.2-17.

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iii

" TSR-PGDP March 7,1997 Rev.7

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SECTION 2.1 SPECIFIC TSRs FOR TOLL TRANSFER AND SAMPLING

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FACILITY C-360 2.1.2 SAFETY LIMITS 2.1.2.1 AUTOCLAVE SHELL PRESSURE SL 2.1.2.1: The autoclave shell pressure shall not exceed 165 psig.

APPLICABILITY: Modes: All BASIS:

The autoclaves are designed and manufactured under ASME Boiler and Pressure Vessel code l

standards. As ASME pressure vessels, the autoclaves were hydrostatically tested at 150 percent l

of their 150 psig MAWP. The ASME code requires that the pressure transient during relief from this type vessel not exceed 110% of MAWP. Thus, the safety limit is established at 165 psig (110% of MAWP). [SAR Section 3.6.3 and 4.3.5.1.1; USQD 92-034]

2.1.2.2 UF CYLINDER TEMPERATURE 6

SL 2.1.2.2: Cylinder temperature shall not exceed the values listed in the table below.

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V Cylinder Category Temperature Safety Limit A

250 F B

245*F APPLICABILITY: Modes: All BASIS:

The only time that the potential exists for a UF cylinder rupture is during the heating of the 6

cylinder. During the heat-up cycle the UF expands in volume. Ullage (or void volume) is lost 6

due to heating a cylinder to an excessive temperature based upon the amount of UF in the 6

cylinder. A cylinder is assumed to fail at some point above its safety limit.

O 2.1-4

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' TSR,PGDP-March 7,1997 Rev.7 i

i p SECTION 2.1 SPECIFIC TSRs FOR TOLL TRANSFER AND SAMPLING 1

1 FACILITY (C-360) 1:

2.1.5 GENERAL DESIGN FEATURES j

2.1.5.6 HYDRAULIC LIFTS - LIFT CAPACITY i

DF 2.1.5.6: Hydraulic lifts that handle cylinders containing liquid UF are designed with a 3

minimum capacity of 20 tons.

SURVEILLANCE REQUIREMENTS:

Surveillance Frequency

{

SR 2.1.5.6-1 Visual inspection to meet ANSI A17.1 Quarterly requirements.

l SR 2.1.5.6-2 Load test at 100% of rated capacity in Five Years accordance with ANSI A17.1.

4Property "ANSI code" (as page type) with input value "ANSI A17.1.</br></br>4" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. BASIS:

1 i '

_ This design feature minimizes the possibility of the " liquid cylinder rupture" accident scenario

[SAR Section 4.3.5.1.2]. The surveillance requirements are based upon ANSI A17.1,1974, l

Rule 1005.4.

2.1.5.7 HYDRAULIC LIFTS - INTERLOCK WITH SCALE CART AIR SUPPLY l

DF 2.1.5.7: The interlock switch between the levelator and the operating floor scale cart air j

supply prevents scale cart movement if the levelator is not in its full upright L

position.

i SURVEILLANCE REQUIREMENTS:

i Surveillance Frequency I

SR 2.1.5.7-1 Functional test to ensure operating floor scale -

Quarterly l-cart will not move unless the levelator is in the "up" position.

BASIS:

i This design feature is one line of assurance against rolling a liquid-filled cylinder off the

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operating floor. [SAR Section 4.3.5.1.2]

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~ TSR-PGDP March 7,1997 Rev.7

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SECTION 2.2 SPECIFIC TSRs FOR UF. FEED FACILITIES (C-333-A AND V

C-337-A) 2.2.2 SAFETY LIMITS 2.2.2.1 AUTOCLAVE SHELL PRESSURE SL 2.2.2.1: The autoclave shell pressure shall not exceed 220 psig.

APPLICABILITY: Modes: All BASIS:

]

The autoclaves are designed and rnanufactured under ASME Boiler and Pressure Vessel code l

standards. As ASME pressure vessels, the autoclaves were hydrostatically tested at 150 percent l

of their 200 psig MAWP. The ASME code requires that the pressure transient during relief from this type of vessel not exceed 110% of MAWP. Thus, the safety limit is established at 220 psig (110% of MAWP). [SAR Sections 3.2.3 and 3.6.3; USQD 92-034]

2.2.2.2 UF CYLINDER TEMPERATURE SL 2.2.2.2: Cylinder temperature shall not exceed the values listed in the table below.

,)

%J Cylinder Category Temperature Safety Limit A

250*F B

245*F APPLICABILITY: Modes: All BASIS:

The only time that the potential exists for a UF cylinder rupture is during the heating of the 6

cylinder. During the heat-up cycle the UF expands in volume. Ullage (or void volume) is lost 6

due to heating a cylinder to an excessive temperature based upon the amount of UF in the 6

cylinder. A cylinder is assumed to fail at some point above its safety limit.

2.2-3

' TSR-PGDP March 7,1997 Rev.7 f]

SECTION 2.2 SPECIFIC TSRs FOR UF. FEED FACILITIES (C-333-A AND j

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C-337-A) 2.2.3 LIMITING CONTROL SETTINGS, LIMITING CONDITIONS FOR OPERATION, SURVEILLANCES 2.2.3.2 AUTOCLAVE PRESSURE RELIEF SYSTEM (conthined)

BASIS:

This system prevents catastrophic failure of the autoclave, and subsequent uncontrolled UF6 release, by allowing small (relative to the release associated with autoclave rupture), controlled releases in the unlikely event of concurrent UF release and excessive autoclave water inventory.

6 The ASME Boiler and Pressure Vessel (B&PV) Code requires that overpressure relief be l

provided by a device stamped at or below the MAWP and sized such that the subsequent transient pressure will be limited to a maximum of 110% of MAWP when a single relief path is used. The ASME B&PV Code allows rupture discs to have a i 5% burst tolerance. Rupture l

discs stamped at MAWP will therefore burst at or below 105% of MAWP. Thus, the LCS is set at 105% of MAWP. To comply with these standards, pressure relief devices are purchased and installed with stamped ratings at or below the LCS. [SAR Section 4.3.1.1.1]

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2.2-9

TSR-PGDP' March 7,1997 Rev.7 SECTION 2.3 SPECIFIC TSRs FOR PRODUCT AND TAILS WITHDRAWAL l\\

FACILITIES 2.3.5 GENERAL DESIGN FEATURES 2.3.5.5 SCALE CART DESIGN DF 2.3.5.5: The scale carts are designed with a muumum capacity of 20 tons and have a " low boy" design.

SURVEILLANCE REQUIREMENTS:

Surveillance Frequency SR 2.3.5.5-1 Visual inspection of the scale cart for structural Biennially damage, degradation, cracks, distorted members and loose fasteners.

BASIS:

This design feature minimizes the possibility of the " liquid cylinder rupture" accident scenario.

[SAR Section 4.3.3.1.5 and 4.3.4.1.5]

fl 2.3.5.6 UF CONDENSER AND ACCUMULATOR MINIMUM WALL THICKNESS 6

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DF 2.3.5.6: The withdrawal area UF condensers and accumulator vessels have the minimum 6

required metal thicknesses in accordance with ASME requirements.

SURVEILLANCE REQUIREMENTS:

Surveillance Frequency SR 2.3.5.6-1 Visual inspection, including thickness Five Years measurements, shall be taken on the withdrawal area UF. condensers and UF accumulators at least 6

every five years in order to verify the vessel wall has not been reduced below minimum required metal thicknesses.

BASIS:

Ensuring the vessel integrity of the UF. condensers and accumulators helps prevent a UF6 release. The minimum thicknesses for the condensers and accumulators, surveillance frequency, and monitoring points were established in accordance with the National Board Inspection Code l

(NBIC). Inspections are conducted in accordance with the current revision of the NBIC. [SAR l

Section 4.3.3.1.2 and 4.3.4.1.2]

2.3-50

TSR-PGDP' March 7,1997 Rev. 7 O

SECTION 2.4 SPECIFIC TSRS FOR ENRICHMENT CASCADE FACILITIES

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4 2.4.2 SAFETY LBIITS 2.4.2.2 COOLANT (R-114) OVERPRESSURE PROTECTION SYSTEMS (continued) l BASIS:

Overpressurization and rupture of the coolant system into the UF system could result in the 6

subsequent loss of UF containment due to overpressurization of the UF enrichment system.

6 6

There is reasonable assurance the integrity of the coolant system will not be breached at the ASME Boiler and Pressure Vessel (B&PV) Code,Section VIII, maximum allowable pressure l

during the relief transient (110 percent of the Maximum Allowable Working Pressure [MAWP])

[SAR Section 4.3.2.1.3 and 4.3.2.4.1].

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2.4-4

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TSR-PGDP March 7,1997 Rev.7

> /T SECTION 2.4 SPECIFIC TSRS FOR EN'RICHMENT CASCADE FACILITIES

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2.4.3 LIMITING CONTROL SETTINGS, LIMITING CONDITIONS FOR OPERATION, SURVEILLANCES 2.4.3.4 R-114 COOLANT OVERPRESSURE CONTROL SYSTEM (continued)

SURVEILLANCE REQUIREMENTS:

Surveillance Frequency SR 2.4.3.4-1 Visually inspect the R-114 cell coolant Quarterly overpressure control system manual isolation valve to ensure it is sealed l

open.

SR 2.4.3.4-2 Visually inspect the cavity vent port Quarterly between tandem-mounted rupture discs to ensure it is open to atmosphere.

BASIS:

The ASME code requires that overpressure relief be provided by a device stamped at or below O

the MAWP and sized such that the subsequent transient pressure will be limited to a maximum I U of 110% of MAWP when a single relief path is used. ASME Boiler and Pressure Vessel l

(B&PV) code allows rupture discs to have a 5% burst tolerance. Rupture discs stamped at l

MAWP will therefore burst at or below 105% of MAWP. Thus, the LCS is set at 105% of MAWP. To comply with these standards, pressure relief devices are purchased and installed on the cascade cell coolant condensers with stamped ratings at or below the LCS. [SAR Section l

4.3.2.4.1]

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2.4-12