ML110050336

Paducah Gaseous Diffusion Plant (Pgdp), Transmittal of Revisions 124 and 125 to Certification Application USEC-01

ML110050336
Person / Time
Site:	Paducah Gaseous Diffusion Plant
Issue date:	12/28/2010
From:	Toelle S U.S. Enrichment Corp (USEC)
To:	Catherine Haney Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
GDP 10-0055
Download: ML110050336 (16)

Text

A Global Energy Company December 28, 2010 GDP 10-0055 Ms. Cathy Haney Director, 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, Certificate No. GDP-1 Transmittal of Revisions 124 and 125 to Certification Application USEC-01

Dear Ms. Haney:

In accordance with 10 CFR 76, the United States Enrichment Corporation (USEC) hereby submits Revisions 124 and 125 to the USEC-0l certification documents for the Paducah Gaseous Diffusion Plant. These revisions include the following changes:

• Revision 124 incorporates Technical Safety Requirements (TSR) changes that were previously submitted for your review in accordance with 10 CFR 76.45 and approved in your letter dated October 28, 2010, as Amendment 6 to Certificate of Compliance GDP-1. Revision 124 was effective October 28, 2010.

• Revision 125 incorporates Technical Safety Requirements (TSR) changes that were previously submitted for your review in accordance with 10 CFR 76.45 and approved in your letter dated November 17, 2010, as Amendment 7 to Certificate of Compliance GDP-1. Revision 125 was effective December 17, 2010.

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

IsEC Inc.

K 6903 Rockledge Drive, Bethesda, MD 20817-1818 Telephone 301-564-3200 Fax 301-564-3205 www.usec.com

Ms. Cathy Haney December 28, 2010 GDP 10-0055, Page 2 Should you have any questions regarding this matter, please contact me at (301-564-3250). There are no new commitments contained in this submittal.

Sincerely, Steven A. Toelle Director, Regulatory Affairs

Enclosures:

1. Oath and Affirmation

2. USEC-01, Application for United States Nuclear Regulatory Certification, Paducah Gaseous Diffusion Plant, Revision 124.

3. USEC-01, Application for United States Nuclear Regulatory Certification, Paducah Gaseous Diffusion Plant, Revision 125.

Commission Commission cc: R. DeVault (DOE)

D. Hartland, NRC Region II J. Calle, NRC Region II T. Liu, NRC Project Manager NRC Senior Resident Inspector - PGDP USEC-01, Copy Number 641 (w/o)

USEC-0 1, Copy Numbers 442,664 USEC-01, 2 copies USEC-01, Copy Number 697 GDP 10-0055 Oath and Affirmation

OATH AND AFFIRMATION I, Steven A. Toelle, swear and affirm that I am the Director, Regulatory Affairs, of the United States Enrichment Corporation (USEC), that I am authorized by USEC to sign and file with the Nuclear Regulatory Commission Revisions 124 and 125 to the USEC Application for United States Nuclear Regulatory Commission Certification for the Paducah Gaseous Diffusion Plant (USEC-0 1), as described in USEC Letter GDP 10-0055, 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.

Steven A. Toelle On this 28th day of December, 2010, the person signing above personally appeared before me 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 hereof I hereunto set my hand and official seal.

ROIN U"8 PMMVoery Conty

[Roxine Behrens, Notary Public My Commission Expiros Sep 14. 2011 State of Maryland, Montgomery County My commission expires September 14, 2011 GDP 10-0055 USEC-01 Application for the United States Nuclear Regulatory Commission Certification Paducah Gaseous Diffusion Plant Revision 124 (October 28, 2010)

APPLICATION FOR NUCLEAR REGULATORY COMMISSION CERTIFICATION PADUCAH GASEOUS DIFFUSION PLANT (USEC-01)

REMOVAL/INSERTION INSTRUCTIONS REVISION 124 - October 28, 2010

!I Remove Pages Insert Pages VOLUME 4, List of Effective Pages:

List of Effective Pages:

ii, iv ii, iv Section 3.0:

Section 3.0:

3.0-3 3.0-3

TSR-GDP Rev. 124 October 28, 2010 LIST OF EFFECTIVE PAGES Pages iv 111 iv v

vi vii Vixl ix x

xi xii 1.0-1 1.0-2 1.0-3 1.0-4 1.0-5 1.0-6 1.0-7 1.0-8 1.0-9 2.0-1 2.1-1 2.1-2 2.1-3 2.1-4 2.1-5 2.1-6 2.1-7 2.1-8 2.1-9 2.1-10 2.1-11 2.1-12 2.1-12a 2.1-13 2.1-14 2.1-15 2.1-16 2.1-17 2.1-18 2.1-19 2.1-20 2.1-21 2.1-22 2.1-23 2.1-24 Revision Pages 124 122 124 11 5

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TSR-GDP Rev. 124 October 28, 2010 Pages Revision 2.4-10 2.4-11 2.4-12 2.4-13 2.4-14 2.4-15 2.4-16 2.4-17 2.4-18 2.4-19 2.4-20 2.4-20a 2.4-21 2.4-22 2.4-23 2.4-24 2.4-25 2.4-26 2.4-27 2.4-28 2.4-29 2.4-30 2.4-31 2.4-32 2.4-33 2.4-34 2.4-35 2.4-36 2.4-37 2.4-37a 2.4-38 2.4-39 2.4-40 2.4-41 2.4-41 a 2.4-4 1b 2.4-42 2.4-43 2.4-44 2.4-45 2.4-45a 2.4-45b 2.4-46 2.4-47 5

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TSR-PGDP October 28, 2010 Rev. 124 SECTION 3.0 ADMINISTRATIVE CONTROLS

b.

Individuals who perform training, health physics, quality assurance, nuclear criticality safety, and/or other safety functions shall have sufficient organizational freedom to ensure their independence from operating pressures.

3.2.2 FACILITY STAFF

a.

Minimum staffing requirements for each facility are shown in Table 3.2.2-1.

These staffing levels do not apply under conditions requiring facility evacuation.

b.

Administrative procedures shall be developed, implemented, and maintained to limit the working hours of facility staff who perform safety functions (e.g.,

operators, health physics personnel, maintenance personnel), in accordance with the following guidelines.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have personnel work an 8-hour or 12-hour workday [i.e., a nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (can be as much as 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) work week].

In the event that overtime must be used on a temporary basis, the following guidelines shall be used:

1. An individual should not be permitted to work more than 16 straight hours, excluding shift turnover;

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time;

3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods; the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> may include shift turnover

4. Except during outage periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized in advance by the General Manager or his designee, in accordance with approved administrative procedures and with documentation of the basis for granting the deviation. Routine deviation from the above guidelines is not authorized.

Management will assess on a monthly basis the application of overtime for facility staff who perform safety functions to ensure consistency with the overtime guidelines stated above.

3.0-3 GDP 10-0055 USEC-01 Application for the United States Nuclear Regulatory Commission Certification Paducah Gaseous Diffusion Plant Revision 125 (December 17, 2010)

APPLICATION FOR NUCLEAR REGULATORY COMMISSION CERTIFICATION PADUCAH GASEOUS DIFFUSION PLANT (USEC-01)

REMOVAL/INSERTION INSTRUCTIONS REVISION 125 - December 17, 2010 Remove Pages Insert Pages VOLUM.E.4.

List of Effective Pages:

List of Effective Pages:

ii, iv ii, iv Section 2.4:

Section 2.4:

2.4-10, 2.4-11,2.4-12 2.4-10,2.4-11,2.4-12

TSR-GDP Rev. 125

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TSR-PGDP Rev. 125 December 17, 2010 SECTION 2.4 SPECIFIC TSRS FOR ENRICHMENT CASCADE FACILITIES 2.4.3 LIMITING CONTROL SETTINGS, LIMITING CONDITIONS FOR OPERATION, SURVEILLANCES 2.4.3.4 R-114 COOLANT OVERPRESSURE CONTROL SYSTEM LCS 2.4.3.4: The R-114 coolant rupture discs shall actuate at or below the location-specific values tabulated below:

Equipment Specification LCS (psig)

C-331, C-333, C-335, and C-337 Cascade Cell Coolant 315 (300 psig MAWP)

C-337 "B" Boosters, 315 (300 psig MAWP)

C-331 and C-335 Surge and Waste Boosters C-335 "A" Boosters, C-333 "B" Booster, C-331 #3 Low Speed 315 (300 psig MAWP)

P&E Pump, C-331 and C-333 High Speed P&E Pumps, C-335 and C-337 Dual Speed P&E Pumps C-3 10 Cascade Cell Coolant 210 (200 psig MAWP)

C-331 "A" Boosters, C-331 #1 & #2, C-333, and C-337 Low 210 (200 psig MAWP)

Speed P&E Pumps LCO 2.4.3.4: The R-1 14 coolant overpressure control system shall be operable.

APPLICABILITY: Modes: Cascade 1*, Cascade 2* (* - Only when process motors are energized and an R-1 14 negative has not been established on the affected cell[s].)

2.4-10

TSR-PGDP December 17, 2010 Rev. 125 SECTION 2.4 SPECIFIC TSRS FOR ENRICHMENT CASCADE FACILITIES 2.4.3 LIMITING CONTROL SETTINGS, LIMITING CONDITIONS FOR OPERATION, SURVEILLANCES 2.4.3.4 R-114 COOLANT OVERPRESSURE CONTROL SYSTEM (continued)

ACTIONS:

Condition Required Action Completion Time A.

R-1 14 coolant overpressure A.1 An operator shall continuously monitor Immediately control systern inoperable for the R-1 14 system pressure/temperature in reason other than B or D below, order to take action to lower pressure.

B.

The R-1 14 coolant B. I Ensure the valve is open.

Immediately overpressure control system AND manual isolation valve found B.2 Reseal the valve.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> unsealed or closed.

C.

Action item B not C. 1.

An operator shall continuously monitor Immediately satisfactorily completed.

the R-114 system pressure/temperature in order to take action to lower pressure.

D.

The cavity vent port between D. 1 Restore opening.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> tandem-mounted rupture discs

( not all locations have this eature) is discovered not open to atmosphere.

E.

Action item D not E. 1 An operator shall continuously monitor Immediately satisfactorily completed.

the R-114 system pressure/temperature in order to take action to lower pressure.

2.4-11

TSR-PGDP Rev. 125 December 17, 2010 SECTION 2.4 SPECIFIC TSRS FOR ENRICHMENT CASCADE FACILITIES 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-1 14 coolant Quarterly overpressure control system manual isolation valve to ensure it is sealed 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 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. ASME Boiler and Pressure Vessel (B &

PV) code allows rupture discs to have a + 5% burst tolerance. Rupture 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 on the cascade cell coolant condensers with stamped ratings at or below the MAWP.

If the R-114 coolant overpressure control system is inoperable per Conditions A, C, or E, the Required Actions for an operator to continuously monitor the R-114 system pressure/temperature as allowed by ASME code will be in accordance with procedures to provide pressure relief protection during the time when the system is inoperable. The procedure shall ensure that when the system does not have an operable pressure relief path, an operator shall continuously monitor the pressure/temperature conditions of the R-1 14 system and shall be capable of responding promptly to reduce the pressure. [SAR Section 3.15.3.4.2]

2.4-12