ML20217M219

Application for Amend to License SNM-1227,adding Cylinder Recertification Facility as Location of Authorized Activity

ML20217M219
Person / Time
Site:	Framatome ANP Richland
Issue date:	08/04/1997
From:	Edgar J SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
JBE:97:129, TAC-L30997, NUDOCS 9708220087
Download: ML20217M219 (11)

Text

-_

1. [A/w SIEMENS

' 3" "

Fw e

g August 4,t 1997 -

JBE:97:129 '

U.S. Nuclear Regulatory Commission L Attn.: Mr. M.- F. Weber, Chief Licensing Branch

-Division of Fuel Cycle Safety and Safeguards, NMSS

_. Washington, DC 20555

Subject:

UF. Cylinder Recertification Facility Ref.:.

Letter, J. B. Edgar to K. J. Hardin, dated April 24,1997 in the referenced letter Siemens Power Corporation (SPC) described its proposed UF. Cylinder Recertification Facility (CRF) as well as the recertification process. The purpose of this letter is to request an amendment to SPC's license to add the CRF as a location of an se.norized activity.

Safety Considerations Criticality safety, radiation protection and environmental protection will be provided as described

in the appropriate chapters of SPC's license application. Specifically:

. - Criticality Safetv: The basis for criticality safety is mass control of uranium in the cylinders and concentration control of the ' uranium in the hydrostatic test water expelled from the cylinders. These controls are further described in Chapters 4 and 14 of SPC's license

. application. The cylinders are intemally washed and decontaminated in another facility prior to recertliication. The cylinder washing / decontamination procedure complies with ANSI

- N14.1-1995, Appendix B. Prior to the cylinder wash process the mass of uranium in a

. cylinder is confirmed to be less than 15 kgUF. and the amount of water added is lim;ted to five gallons for each wash. Cylinders are washed until the wash water contains less than 5000 ppm uranium at which time the cylinders are examined internally for leftover concentrations _of uranium with a boroscope (and further cleaned if such concentrations are found), steam cleaned and then hot air dried,+The wash / decontamination process results in cylinders with some removable inte.nal contamination amounting to insignificant quantities of uranium._ After hydrostatic testing, the 230 gallons of water, expected to contain a maximum of 25 ppm uranium, will be pumped via a sump receiver tank (7 %" ID x 72" long) either to Lagoon 3 or SA._ The water will be sampled prior to discharge to the laguon.

The CRF will be monitored by SPC's criticality alarm system.

L l

'9708220087 970904 ing PDR-ADOCK 07001257*

C PDR M,,.

w

___ = _ _

I h7tr. M. F. Web;r, Chief JBE:97:129 August 4,1997 Page 2 3

• Radiation Protection: The uranium will be contained inside UFe cylinders which have previously been washed. Routine monthly surveys as well as surveys on incoming and outgoing cylinders will be performed. A change room will be provided. Surveys and change room usage will be as described in Chapters 3 and 12 of SPC's license application.

Environmental Protection: SPC's environmental monitoring program described in Chapters 5 and 13 of SPC's license application applies to this operation. Closed cylinders with internal contamination will be brought into the f acility. As discussed in the process description in the referenced letter, the water used for hydrostatic testing will be collected in a sump tank and discharged to a lagoon. This liquid stream is fuily compatible with the construction and operation of SPC's surf ace impoundment system. The lagoons themselves are equipped with multiple liners and an interstitialleachate collection / leak detection system. That system and a downgradient groundwater monitoring network are sampled on a montHy basis as a condition of SPC's NRC license.

The concrete ficor of the CRF will be coated for sealing and ease of decontemination; will be sloped so that any water will flow to the drain and then into a floor sump tank (7 %" IDx24" long) to be pumped to a lagoon; and is diked as an extra precaution to confine water on the floor. There will be no sewer connections from the CRF. Exhaust air will be double HEPA-filtered as shown in the enclosed Figure 11-10.38. Please note that the enclosed diagram of the CRF ventilation system is slightly changed from the preliminery design provided with the referenced letter.

With regard to fire protection, the f acility will be constructed to be noncombustible and will be equipped with fixed temperature / rate-of-rise detectors which trigger the fire alarm. There will also be manual fire alarms and portable fire extinguishers in the f acility.

With regard to chemical safety, there will be no hazardous chemicals used in this facility. Water will be used to hydrostatically test cylinders and nitrogen will be used to air test the cylinders for leaks. Af ter pressure testing with nitrogen, depending upon customer requirements, the cylinders are either shipped with a 5 psig nitrogen atmosphere or evacuated to neDative 25 inches of mercury.

Because of the low combustible loading, the lack of hazardous chemicals and low uranium content in the CRF, SPC does not intend to do formal fire or chemical hazards analyses.

Enclosed in support of this amendment request are six copics of revised pages 1-10, 4-17, and 10-50a,10-50b, and 10-114a. We expect to have beneficial use of the CRF in October of this_ p

. year. _Once the CRF is built, the various site plans in Chapter 10 of SPC's license application will be updated to show its location and the process description and safety analysis will be added to Chapter 15.

4 h -~

?, - Mr. M. F. W ber, Chiifl JBE:97:129 August 4,1997 Page 3-

.f-

-,4.

. lf you require additional information, please call me at 509 375 8663.

-Very truly yours; l

Mm B. Edgar-

= Staff Engineer, Licensing csk Enclosures -.

cc:.NRC Region IV WCFO u

T v.

A SiemenS Power COrpdration - Nuclear Division sus.2 3PECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 I

PART I-LICENSF CONDITIONS nev.

36 TABl.E l 1.1 Specific L ;ations of Authorized Activities (Cont.d)

Location SNM Authorized Activity laundry Facility Uranium Compounds (up to Cleaning of contaminated 5 wt% U-235) protective clothing and equipment.

UF. Cylinder Storage UF, (up to 5 wt% U-235) '

Outside storage of UF.

Areas cylinders (full and empty).

Packaged Fuel UO (up to 5 wt% U 235),

Outside storage of fuel packed Storage Areas for shipment; the transport containers are closed, sealed and properly labeled for shipment.

I Packaged Waste Uranium Compounds (up to Outside storage of l

Storage Areas 5 wt% U-235) contaminated materials (including low level waste and incinerator ash) which are packaged, sealed, labeled and externally free of contamination.

I Process Chemical Uranium Compounds (up to Transfer, mixing, sampling, Waste Storage 5 wt% U-235) storage and solar evaporation Lagoon System of contaminated liquid wastes.

Retention Tanks Uranium Compounds (up to Interim storage of potentialli 5 wt% U-235) contaminated liquid wastes.

High Uranium Solids Uranium Compounds (up to Transfer of uranium bearing Pond 5 wt% U-235) solids, leaching for uranium recovery.

I Solids Trench Uranium Compounds (up to Transfer and storage of j

j 5 wt% U-235) contaminated solids awaiting 1

leaching or bu ial.

The locations described in this table are shown on the site plan, Figure 11-I 10,1 l

l u,easc im.wm eus.

vctober zu,1suc

..ca ne.:

1-9 l

sPC No-3330.947 (R.'/07t92)

Siemens Power Corporation - Nuclear Division eup.a SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70-1257 PART I-LICENGE CONDITIONS nEV.

TABLE l 1.1 Specific Locations of Authorized Activities (Cont.d)

Location SNM

.A_uthorized Activity Lagoon Uranium Uranium Compounds (up to Recovery of uranium from Recovery 5 wt% U-235) waste solutions.

Ammonia Recovery Uranium Compounds (up to Removal and recovery of Facility 5 wt% U 235) ammonia from uranium contaminated liquid wastes.

Lagoon SA IX Uranium Liquid Wastes (up Filtration and ion exchange of Process ARF Building to 5 wt% U 235 and less uranium liquid wastes, than 140 gull concentrations in filters and resins)

Any Permanent or Uranium solid waste (up to Sorting and compaction.

j Portable Building 5 wt% U-235) l having HEPA filtration and Isokinetic sampling.

Operations Scrap Uranium Cempounds (up to Storage of closed and Warehouse 5 wt% U 235) externally free of-significant-contamination containers of product and scrap materials; and the unloading of such containers from and the loading i

of such containers into shipping containers.

UF, Cylinder Uranium Compounds, solid Cylinder recertification Recertification and in water solution (up to activities, including hydrostatic Facility 5 wt% U-235) strength testing, wall thickness measurement, internal examination, and pressure tes tir.g.

The locations described in this table are shown on the site plan, Figure 11-10.1 AMENOMENT APPUCATm DAfi.

PAGE NO.:

Augutt 4,1997 1-10 j

SPC No 3330M7 (R t/07/02)

SiemenS Power Corporation Nuclear DiviSioti eur.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART ll SAFETY DEMONSTRATION nev.

10.3.13 $ Cvilnder Recertification Facility (CRF) HVAC System The general features of the CRF HVAC system include a combination of a once-through airflow and recirculation supply system (KG6) and a double HEPA filtered exhaust system (K67). A simplified schematic diagram of the HVAC system is shown in Figure 11-10.38, 10.3.13.1 K66 Air Supply and Recirculation System The K66 air supply and recirculation system supplies approximately 450 ft / min, of outside air and also recirculates approximately 2350 f t'/ min. of builoing eir.

l Recirculated air is passed through a roughing filter and a single HEPA filter with an i

installed efficiency of 99.95% for 0.8 micron DOS cold-generated aerosol, Provision is made in the K66 recirculation system for continuous alpha radiation monitoring of recirculated air upstream of the HEPA filter bank. The alpha air monitor is set to alarm and annunciate when alpha activity exceeds 40 DAC-hr.

i l

10.3.13,2 K67 Air Exhaust System l

Air supplied to the CRF, plus infiltration, is exhausted through the K67 exhaust I

system. The double HEPA filter arrangement in this system consists of the final HEPA filter bank and upstream primary HEPA filter bank.

The K67 system exhaust air (approximately 950 ft'/ min.) r.a ses from the two stage HEPA filter bank through the main exhaust fan, past a out air monitor (measuring i

airflow quantities) and is discharged from a stack extending 20 ft above ground on the i

j south side of the building. The K67 exhaust system has one fan which is connected j

to normal power. All final HEPA filters are in-place tested to be 99.95% minimum l

efficient for O.8 micron dos cold-generated aerosol i

10.3.13.3 System Contr_qh The HVAC systems are controlled with temperature, pressure and flow sensor i

actuating valving and damper positions to hold temperatures, pressures, and pressure differentials constant in the various building areas. The K66 supply air system is interlocked with the K67 exhaust system to prevent operation of the K66 supply air system without the K67 exhaust system operating. Pressure sensors are provided to maintain a minimum negative differential pressure of 0.05 inch water gauge in the building relative to the atmosphere.

l l

AMENOMENT APPUCAT1ON DATL PAGE NO.:

August 4,1997 10-50a sPc-rio.3330 947 [P 007 92)

~

Siernens Power Corporation - Nuclear Division eup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO, SNM 1227, NRC DOCKET NO. 701257.

PART 11 - S,tFETY DEMONSTRATION nev.

The K66 supply fan is interlocked so that a loss of exhaust duct flow (exhaust fan failure) or a signal from the exhaust duct heat detector will shut down the K66 air supply system.

An automatic visual alarm is activated when the recirculation system is inoperable.

10.3.13,4 HEPA Filter Bank The final HEPA filters are enclosed in a sheet metal housing that, in turn, is mounted on structural steel legs fastened to a concrete slab. The HEPA filters are rated at 1000 ft'/ min at one inch water gauge pressure drop and are mounted in welded steel frames, Continuous air samplers are installed downstream of the filter bank, Visual indicators for reading the pressure drop across the filters are permanently installed, and means are provided for in-place DOS testing.

The HEPA filter medium is 100 % moisture-resistant fiberglass, pleated over corrugated separators and sealed in fire-resistant plywood frames, The individual i

filters are certified to remove 99.97% of 0,: micron particles and meet or exceed Military Specification MIL F-51079, I

i

~

l l

w.osnumenon cas; nas no.:

August 4,1997 10-50 b i

sPc-ND.3330 947 ( A-1/07/92)

4 -

CD (f)

E

- T gr a

mO 3-E t

g

.>2 CD

}

Tm ZCT ci t

h (o S

5 g

Table 3-4.1 (Cont *d) m.D g

y, COMPONENT CONTROL TYPE OtSCUSS!ON OF ANY SPECIAL -

"U O O-CONTROLS USED / ADDITIONAL g

EXPLANADON OF CONmOL TYPE y0

-t O GEO VOL FNA NAA CCU CCM MCU MCM PPC ARA SPA mQ C*-

t 2

i

> o" c

.o o

r-3 g

UF Cylinders X

X X

X g,

-g dur% cr ada

-i 5z u

wash and 7

mc g

recertitcah o

Operations (W go~

g CD CD N

diarneter or less) m M D)

Z z'

Vaporization X

X Redundant devices prevent Assae m

o O M

chests (ADU sokason from exceedog a safe O

(/)

process fines) geometry inside the vaporization O

z 9.

5

- i: 8 Vaporization X

No credible pathway exists to get 3

"m chests and Essue solution into the dry O

is) autoctaves (dry conversion vaporization chest or Z

.N O

conversion) autoclaves.

Z Unfavorable X

X X

g i,,

O i

scrubber systems /hquid l

b separators 7m

-l z

I y

O 9

4 y

i

?

'k 3

I

~

m

-N ro i

f

)

mm5'

$m i

3 i

I

~>D 2

r m z

Z I

Table 14.1 (Cont'd )

Og 3

C O

{

CONTAOL TYPE cot 41ROLS USED / AN)IIlONAL g

DISCUSSK)td OF ANY SPECIAL 9

COMPOf!Effr EXPtN4ATIOr4 OF cot 4 TROL TYPE y,b g

2

?

GEO VOL ff1A flAA CCt1 CCM MCU MCM PPC ARA SPA C

> "O -

--i O I

2 ITI y Te O Cylindrical

>3 O

Tanka. Futers

[

F ft and Other e.

O I?quipment X

Uses may include dissolution of y

37 g

7 fil C

< 8 4" nondnal X

penets.

Z ~O m

t-ID

(/) g p

Cylindrical tanks, filters, and other g

III D3 e<ydpment less than ttds dimenskm m

_a Z

Z' e

are e8.so appropelateh spaced to rn O O g

assure neutron Irstoractions with R'

other equipmerd w!E sesult in O

O 5*

acceptable k,,

Fa5ure of geomehy 0

g.

or specing tsetween t'med places of 7

3 equkwnerd is controsed by design O

e b

(

X Uses are smitad to tiomogeneous O

M 5 9 29 nominal X

solutions / slurries such as UO~

iD powders, UOf, arx1 ADt1 h

Z I

T Cyttadalcal tanks, idlers, erut other O

equipment loss than this d4nonskm O

are also appropriately spaced to O

/

assure neutson Interactions witti O

h other equipment wul sesult in X

acceptable k,.

Falkme of geometry g

or spacing between fined pieces of equipment is conuoned by design a

h 9

l l g N

t l

ai m

U' m h

YC w

e

?

( 5 n

y ti s

9

1

.~...

UF6 CYLINDE VENTILATIO{

BUILDING VACUUM CONTROL r------------------~~---------~~-----------~~"

I i

l l

l 1

HIGH RADIATION F AN SHUTDOWN g

i I

I 1

l l

l rt FLOW l

l I

2800 CFM SUPPLY i

i s

I i

l l

SUPPLY I

i FAN K-66 I

I I

I 2350 CFM RECIRC I

i I

I I

I JL I

I I

I I

i 1!

I I

I I

I I

I i

l RADIATION ROOM AIR l

l DETECTOR SAMPLING HEADS l

L___________

IIIII b

DIFFERENTIAL PRESSURE

(-0.05 in wg)

JL CHANGE ROOM JL 2

s e

L L

u u

if 950 CFM EXHAUST o

o O

9 z

2 9

9 2

E e

e W

=!

=!

~

~

NOTES:

1.ALL FILI

2. COOLER

3. HEATER

4. SMOKE

5. FANS H

fECERTIFICATION F ACILITY EMF-2 R Page 10114e SYSTEM FLOW DIAGRAM August 4, 1937 1

ONDENSER OUTSIDE M 4

=

4 00

1. 5

!---- Ity 85X 30X h

uh FILTER FILTER U

ANSTEC APERTURE 4

CARD COOLEN HEATER HEPA 30X AWie on FIL TER FILTER f*

Card

=

DISCHARGE AIR N

950 CFM ACUUM AIR PLING SYSTEM g

v FLOW U

METER FLOW CONTROL VACUUM N

PUMP

[~~~~~

i i

l I

i i

l EXHAUST EXHAUST 30Z HEPA HEPA FAN K-67 STACK FILTER FILTER FIL TER 30' if DP'S ARE MONIT0 RED.

TEMP CONTROLLED.

TEMP CONTROLLED ECTOR IN SUPPLY DUCT.

VARIABLE SPEED DRIVE.

FIGURE 'l1-10.38

_ _ _ _ _ _ _ _ _ _ _ _