ML20203C253

SER Accepting Amend 8 to License SNM-1227

ML20203C253
Person / Time
Site:	Framatome ANP Richland
Issue date:	12/09/1997
From:	NRC
To:
Shared Package
ML20203C238	List: ML20203C234 ML20203C240 ML20203C253
References
NUDOCS 9712150266
Download: ML20203C253 (4)

Text

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t f....sk o* UNITED STATE 8 g 3' NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. =' "I

% December 9, 1997 DOCKET: 70 1257 LICENSEE: Siemens Power Corporation Richland, WA

SUBJECT:

SAFETY EVALVATION REPORT: AMENDMENT APPLICATION DATED AUGUST 4,1997. UF CYLINDER 6

RECERTIFICATION FACIt.lTY (CRF)

BACKGROUND in a letter dated August 4, 1997, and with supplementary information dated Movember 14, 1997, and information previously submitted on April 24, 1997.

Siemens Power Corporation (SPC) applied for a license amendment to add the UFs

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Cylinder Recertification Facility (CRF) as a location of an authorized activity. The license amendment adds recertification to a previous ,

authorization by including the statement "UFs cylinders during cylinder wash and recertification operations (30" diameter or less)" in Table 1-4.1 of SNM-1227, which lists the major system components used at SPC and the type of criticality control for each component. The application and supplementary information describes the criticality safety controls to be used.

ElSCUSSION The staff has reviewed the information submitted by SPC Md has performed a technical assessment of the nuclear criticality safety, fire protection, and environmental protection associated with the use of this facility. This facility will house the process of recertifying UFs cylinders, as described below, after they have been internally washed in the 00 2 building.

UFs is shipped in model 30B cylinders which conform to American National Standards Institute (ANSI) N14.1 or to the tinning requirements specified in NRC's Certificate of Compliance No. 9196 for model UX-30 packages. One of the requirements in this standard for a cylinder in use is periodic (every 5 years) inspection and recertification to confirm that the cylinder's mechanical characteristics remain consistent with the specifications required to allow transport of UFs.

This inspection and recertification will take place in the new CRF and will be operated on a batch basis with a maximum of 11 cylinders per batch. P.-ior to the inspection, the inside of the cylinders will be washed in the U02 building

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. 2 to remove the UFs heel that remains in the cylinder after the contents have been introduced into SPC's fuel fabrication process. ,

The recertification process proposed for the CRF includes the following steps:

1. The cylinder, after internal and external visual examination, is filled with approximately 870 (230 gallor.s) liters of water and hydrostatically strength tested at 400 psig.

2. After the cylinder is drained from toe hydrostatic test, it is dried and internally inspected with a boroscope.

3. The wall thickness of the cylinder is then measured using ultrasonic testing equipment in accordance with ANSI N14.1.

4. The valve and end plug are reinstalled, and the cylinder is pressurized with nitrogen to 100 psig and inspected for leaks.

The periodic inspeccion will be conducted by an inspector who has passed the

. written examination sponsored by the National Board of Boiler and Pressure Vessel Inspectors Cylinders that pass the periodic inspection and tests are restamped on the namepl6te with the monta and fear that the inspection and tests were performed.

The facility itself will be a 60 foot by 30 foot pre-engineered metal building with a sloped standard metal roof constructed on a sealed 6-inch thick concrete pad just to the southwest of the UF6 Cylinder Storage F.;cility. The building air filtration and exhaust system will consist of a pad, supply fan.

ductwork, a high efficiency particulate air (HEPA) air filtration unit (certified by the manufacturer t., be c9.97% efficient for removal of 0.3 micron particles), an exhaust fan, an exhaust stack, an isokinetic stack gas sampler. instrumentation, and room air monitoring equipment.

The facility will be operated with the radiation protection, criticality safety, and environmental safety programs as described in Chapters 3. 4. and 5 of SPC's license.

CRITICALITY SAFETY REVIEW This amendment adds recertification to an existing process in Table I-4.1 of the SPC license: _UFs cylinders during cylinder wash and recertification operations (30" diameter or less). The types of criticality controls listed in Table I-4.1 for the new facil1ty will be NAA (neutron absorbing additives).

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. MCU (mass control of uranium). MCH (mass control of moderators), and SPA -

(control of spacing from other fissile units). SPC indicated in its submittal l dated November 14, 1997, that NAA will only be used in the wash process, which  ;

occurs in the 002 building.  ;

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, - In accordance with ANSI N14.1. Appendix B the maximum amount of uranium .

allowed in a cylinder after washing is 94 grams based on a maximum of 5000 ppm uranium (U) in the final five gallon wash. Based on normal operations, the i

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-870 liters (230 gallons) of water used in the hydrostatic testing would.

therefore. contain a maximum concentration of 0.11 g U/1 compared to the ,

minimum critical concentration of approximately 285 g U/1. During normal

operations, if the 11 cylinders in the facility all contained the maximum L amount of 94 g U. there would be approximately 1 kg of U at 5% enrichment in ,

= the entire CRF compared to the minimum critical mass of approximately 40 kg

for 5% enriched uranium. SPC searched normal cylinder washing process data for a period of about 6 months. This empirical data showed 20 grams of .

uranium to be the greatest amount found in a single cylinder after washing. .

Under accident conditions. SPC has postulated a non-washed cylinder that has i been weighed being introduced into the facility. Prior to cylinder washing. 1

- the mass of the heel in a cylinder is confirmed to be less than 15 kg UFs by weighing the cylinder. Therefore, the amount of uranium assumed to be in the cylinder in this accident scenario is 15 kg UF6 . This heel would contain approximately 10 kg U. which is approximately 26% of a minimum critical mass  ;

for 5% enriched uranium. This accident condition is considered unlikely due

to the fact that washed cylinders are distinctively tagged and those to be r

' recertified have had their valves removed and replaced with special plugs .

which are used in the hydrostatic test. As an additional preventive measure.

an operator reviews the follower cards on the cylinders to be recertified 1

prior to recertification to be sure that a supervisor has certified that the

! cylinders are clean and dry. Based on these controls, the accidental introduction _ of multiple non washed cylinders into the CRF is considered extremely unlikely and has not been evaluated.

The si.aff has reviewed the facility description and-safety information <

submitted by SPC. Based on this review, the staff concludes that there is reasonable assurance that an accidental nuclear criticality will not occur, i In addition, the staff has reasonable assurance that a sufficient margin of ,

safety.' exists to prevent a nuclear criticality during both normal and abnormal operating conditions.

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4 FIRE SAFETY REVIEW

• The bF 5 CRF is of non-combustible construction and is located a suitable distance from the UFs cylinder storage and handling facility and other facilities. The design reflects low combustible loading, and the radioactive material will be contained either in the UF cylinders or in water used for the hydrostatic testing. fire detection and fire alarm pull stations provide fire notification to a fully manned guard station. Exit doors are located at each end of the facility for emergency egress. Fire suppression is provided by plant personnel and the local fire department. Portable fire extinguishers are provided for incipient firefighting and fire hydrants are located throughout the plant site. Based on its review, the staff concludes that the facility is adequately designed for fire safety.

ENVIRONMENTAL REVIEW The staff has determined that the following conditions have been met:

1. There is no significant change ir, the types or significant increase in the amount of effleents that may be released offsite.

2. There is no significant increase in individual or cumulative occupational radiation exposure.

3. There is no significant construction impact.

4. There is no significant increase in the potential for or consequences from radiological accidents.

Accordingly, pursuant to 10 CFR 51.22(c)(11), neitner an environmental assessment not an environmental impact statement is warranted for this action.

l CONCLUSION The NRC staff has reviewed the proposed amendment and has determined that the proposed changes will have no adverse effect on the public health and safety or the environment. Therefore, approval of the amendment application is recommended.

The Region IV inspection staff has no objection to this proposed amendment.

Princioal Contributors:

Kimberly J. Hardin Paul Lain Susan D Chotoo

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