ML20113F105

Requests Addressee Name Change on Mailing Labels

ML20113F105
Person / Time
Site:	Pilgrim
Issue date:	06/28/1996
From:	Keene J BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-2.96-062, BECO-2.96-62, NUDOCS 9607080327
Download: ML20113F105 (1)

Text

~ .s Bostors Edisors Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360-5599 June 28, 1996 BECo Ltr. #2.96-062 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 Name Chance of Mailina Labels Enclosed is a typical Certificate of Compliance for a shipping package routinely issued by the NRC and received by Pilgrim Nuclear Power Station (Docket No. 50-293, License No. DPR '

35). Please change the addressee from Mr. E. T. Boulette to the Regulatory Affairs Manager for these documents sent to PNPS.

E effrey W. Keene Regulatory Affairs Manager PMK\pkk\radmisc/namechg

Enclosure:

Sample Certificate of Compliance cc: Mr. William D. Travers, Direc+.or Spent Fuel Project Office ,

Office of Nuclear Material Safety and Safeguards /

1 White Flint North -

11555 Rockville Pike Rockville, MD 20852 060036 9607080327 960628 PDR ADOCK 05000293

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,, . . ..,k UNITED STATES

!* NUCLEAR REGULATORY COMMISSION

, ., wAsHINGT088. D.C. asse6 com

%, February 13, 1996 Mr. Curt Lindner Chen-Nuclear Systems, Inc.

140 Stoneridge Drive Columbia, SC 29210

Dear Mr. Lindner:

As requested by your application dated January 23, 1996, enclosed is Certificate of Compliance No. 9176 Revision No.12 for the Model No.

CNS 14-215H package. This certificate supersedes, in its entirety, Certificate of Compliance No. 9176, Revision No.10, dated May 20, 1993.

Changes made to the enclosed certificate are indir.ated by vertical lines in the margin.

Those on the attached list have been registered as users of the package under the general license provisions of 10 CFR 571.12 or 49 CFR 6173.471.

The approval constitutes authority to use the package for shipment of radioactive material and for the package to be shipped in accordance with the provisions of 49 CFR $173.471.

Sincerely, 1 /

\b/ f William D. Travers, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket No.: 71-9176

Enclosures:

1. Certificate of Compliance No. 9176, Rev. No. 11

2. Approval Record cc w/ enc 1: Mr. Janei K. O'Steen, Department of Transportation Registered Users l

n M W i r O.

.k , ((W.7 ##V 4 . . . . . . .

g,.:-------------,.,------------------------------------

"*" CERTIFICATE OF COMPLIANCE 2

1 C'*" FOR RADIOACTIVE MATERIALS PACKAGES e nevisiow wuween ..pacuos icexTwication wuween e paoswuween . toru =vuesaec.H i , . centwicate wuussa IMA /Q17 A /A A I 9176 11 1 I ,

s. PacAams

s. This certificate e issued to certify that the packaging and contents desenbod en item 5 be4ow. meets the apphcable safety standards set forth in Title 10. Code i _

of Federal Reguistions, Part 71,"Peckaging and Transportation of Radioactive MatenaL" l

I b. This certificato does not reisve the consegnor from comphance with any requirement of the regulations of the U.S. Departenant of Transportation or other l appiscabie regulatory agencies. Including the government of any country through or into whech the package will be transported.

I I

a gw; cays;ssuno on me ses or a sanry Anarsis,angigmgec g sy g ic ga ,

l I

l VECTRA Technologies, Inc. NUPAC application dated February 29, 1988, i Brookside Office Park as supplemented.

I Orse Harbison Way, Suite 209 o D-,

I Columbia, SC 29212 C hD ' T wuussa

- .2 /,fy3_ 3 4 I ,iy ooexar to is conditionet upon .fulfusi roments of 10 CFR Part 71, as appiacabee. and coriktione spectfled below.

I t Q O l c -$A l

(a) Packaging lif,/

co

(. f l (1) Model s.: NUPACh . T'14 2 INSI142hSeriesA,LN14-195L, I and Lt SH ~g y; Q l .,) f ;

(2) Descrpion g i ..

[

Steel egaseb sht i l < a H 1 tbFlow spqcific ivity material. The i

th a M S-in

~

l casks (g) rig :i i n I 1 D by 80.25-inch IH I cavity, ew 1k y V .ead th ess ranging from 1.25 to I 1.88 in enc .\0 bdh th' er st hell and 0.88-inch thick I outer st all. T% ' in $k bot re made up of two steel l plates wit ekness of es. e pr cask lid is secured to the i

cylindrical body by eight, 1-1/4-ine t binders. An optional -

)

i secondary lid c red in the pris i nd is secured to the primary i i lid with eight, 3/ c Q tue an Each lid is provided with a l Neoprene gasket seal. 7'm cREs provided with an optional 12 gauge j stainless steel liner (seal welded along all edges), an optional lid vent i

line with pipe plug, and an optional 3/4-inch drain line with pipe plug. The l

casks are provided with four equally spaced lifting / tie-down devices. The  ;

I primary lid is provided with three lifting lugs and the optional secondary l l lid is provided with one lifting lug. The casks gross weights range from  :

I 51,600 to 58,400 pounds.  !

I t l

Model 00, Lead Tk, Top Tk, Botton Tk, Gross Wt, i

i Number jghu inches inches inches counds I NUPAC 14/210L, LN 14-195L 82.25 1.25 4.0 4.0 51,600 I NUPAC 14/210H, LN 14-195H 83.5 1.88 4.0 4.0 58,400 CNSI 14-215H Series A 83.8 1.85 4.0 4.0 58,400 l ,

I I

I l

1 1 )

I k' O22/bI

_ . _ _ _ _ _ _ - - - - - - - - - _--------------------------------==----"

-,---_.----mm________-____---_______________________

• U.S. NUCt.EAA ReOut.Af oRY CO2dS440N 72" I .

CONOmONe (commuod)

I '

I l Page 2 - Certificate No. 9176 - Revision No. 11 - Docket No. 71-9176  ;

I I *

5. (a) (3) Drawing l

Model Nos. NUPAC 14/210L and NUPAC 14/210H  !

l '

l I i i The packages are fabricated in accordance with Nuclear Packaging, Inc., t l Drawing No. X-20-306-SNP, Sheets 1, 2 and 3 Revision No. A.

I The packages may include an optional removable shield insert fabricated in l l accordance with Pacific Nuclear Drawing Nos. PS-121892-1 and PS-121892 i l

submitted on December 21, 1992. l i

I I

I I Model No. CNSI g. A14-215H n ' Srtik AR E G DJ The package is f d in accordance withyet-Nuclear Systems, Inc.,

l Drawing Nos. 2 08, Sheets I and 2, Rev. D, pf8 24500-5, Rev. 2.

l I

I The package A include an optional removable shi nsert fabricated in I accordancewih. em-Nuclear Systems, Inc., g C-119-B-0017, Rev. 3 l ,

I Model NosL/ EN 14- GhdLN14-195H ,

l x . O i I

The pack ggs are fa pli c d q '

J hI.NTech@ogiesCorporation '

l Drawing (. 5025-N- ee d , ' O.

(b) Contents b '

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l

& tl f 4 '[ ' f  ;

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l' lI l

l (1) Type and f o I sol' p uis ] , uw . eting requirements for low  !

(1) Dewate specif $, tiv' y mah r o cont s; or  !

/

l (ii)Activatedhdcomponents e ng the re Qnts for low specific  !

l  !

l activity mat %1, in secondary container (2) Maximum quantity of ma ppche l

Greater than Type A quantity of radioactive material which may contain li i

fissile material provided the fissile material does not exceed the limits in i l

10 CFR 571.53. The decay heat load is limited to 9 watts.

I I 6. (a) For any package containing water and/or organic substances which could ,

4 radiolytically generate combustible gases, determination must be made by ,

l tests and measurements or by analysis of a representative package such that i i

I the following criteria are met over a period of time that is twice the expected shipment time: l l

l (1) The hydrogen generated must be limited to a solar quantity that would be no mere than 5% by volume (or equivalent limits for other inflammable

[1 n

j r l

gases) of the secondary coptainer gas void if present at STP (i.e., no I

more than 0.063 g-moles /ft at 14.7 psia and 70'F); or ,

1

-l (ii) The secondary container and cask cavity must be inerted with a diluent to l assure that hydrogen must be limited to 5% by volume in those portions of np !

i the package which could have hydrogen greater th.'.n 5%.

_ p a_.__aw n ._ . ,____ ...- -_______ .__..___.___...

0 003M

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• • • CoNolTioNS (coatsnwd) j '"

Page 3 - Certificate No. 9176 - Revision No. 11 - Docket No. 71-9176 l i

6. (a)(continued) i For any package delivered to a carrier for transport, the secondary container II must be prepared for shipment in the same manner in which detemination for gas generation is made. Shipment period begins when the package is prepared l

]

(sealed) and must be completed within twice the expected shipment time. ,

i '.

i 4 (b) For any package shipped within 10 days of preparation, or within 10 days i i

after venting of drums or other secondary containers, the detemination in (a) above need not be made, and the time restriction in (a) above does not

7. Maximu gr s weight of ts s o ainers, shoring, and optional i shield insert is limi 0,000 pounds,

8. Except for close ng contents, shoring must be pla between secondary i

l containers and t ask cavity to minimize movement dg normal conditions of f transport. , g su used g lifting the cask, and

! 3

9. The lid and thinQhield tin s j mustbecover)d., intrans , fg g

10. The cask must I provided it -b Y

' drain lin a lid vent line as i l

tp ak t the package.  ;

shown in the p wing o provide a l 11. InadditiontNher f t b > 1 t 1 Park

Prior to 's ,g

• e lid Ds if opened (or if l (a) ' s must be replaced with 4 The security is , m . e .

new seals h / e r eve velve (12) months, which everoccur'ynspetionCavity d

. vent nes be sealed with appropriate s applied to e pipe plug ds.

(b) Each packaging must g th Ac ept cepstsandMaintenanceProgramof:

Model Nos. NUPAC 14/210L and NUPAC I4/210H Section 8.0 of the application.

Model No. CNSI 14-215H Series A f o

Chem-Nuclear Systems, Inc., Document No. CNSI 9176-S1, Rev.1, Section 4.0. L Model Nos. LN 14-195L and LN 14-195H [

t LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and b t

WM-013, Rev. F.

P (c) The package shall be prepared for shipment and operated in accordance with [

the Operating Procedures of  ;

e Model Nos. NUPAC 14/210L and NUPAC 14/210H r j

---

_igflon S7.0 of the application.----___--_____________--_______________,,,,,s .

- l I

______.____________,_______L____________________y

• U.S. NUCUEAA REGut. ATOMY COM3SS60N

I, $ ",** CONOmONS (conhnved)

' 'i I

l I Page 4 - Certificate No. 9176 - Revision No. 11 - Docket No. 71-9176 l

s. I y

11. (c)(Continued) l Model No. CNSI 14-215H Series A g

! I Chem-Nuclear Systems, Inc., Document No. CNSI 9176-S1, Rev. 1, Section 3.0. !l l l <

I

! Model Nos. LN 14-195L and LN 14-11M1 l l

! LN Technologies Corporation Procedures WM-025, Rev. C. l

12. The ratchet binders on the cask li m torqued to 100i10 ft-lb. f l l

13. The cask body and each c bQstbemar ac ordance with 10 CFR 671.85(c).

I 14. The packages author y this certificate must be t b orted on a motor vehicle,  ! !

I railroad car, aircrW inlandwatercraft,orholdordQc of a seagoing vessel Ig j assigned for the 4 use of the licensee. p

15. Thepackagesaut@ize is certificate are appddforuseunderthe ;l l

i generallicenseQtovisio A

CFR 71.12. g :l l k ,

Q I

} }

I 16. Expiration dat May 31, l g y { . I Nuclear Packaging, N ., a

! ott'43L u F t i u 9,[ .

l Supplements dated: hl1 , r :

L [ O i, l i

f Pacific Nuclear supple r, s

'O ,

n #ys(dafed:

ember d 21, 1992.

I

' February d April 21, 1988; I Chem-Nuclear Systems, Inc plements da 1 January 18, and April 29, I and January 23, 1996. ly l

NUS supplement dated: November 2 9k f k February 16, 1988. lll '

i LN Technologies Corporation supplement dated: ,

I l ,

I Scientific Ecology Group, Inc., supplement dated: April 30, 1993. in 1 i ,

I FOR THE U.S. NUCLEAR REGULATORY C0tEISSION . fli ,

I -

h f William D. Travers, Director i I.

I Spent Fuel Project Office l l Office of Nuclear Material Safety I and Safeguards l l

i i I

I I I I Date: M G ITk l l I

I L ______y,.__y___.__,______________________________ M

1 -

pweu

• a UNITED STATES 3

j j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20MNm01 o% ***** / .

APPROVAL RECORD Model No. CNSI 14-215H j Certificate of Compliance No. 9176 Revision No. 11 By application dated January 23, 1996, Chem-Nuclear Systems, Inc., requested

an amendment to Certificate of Compliance No. 9176, for the Model No.

CNSI 14-215H Series A package. The applicant submitted Drawing No.

C-119-B-0017, Revision No. 3, for the optional shield insert. The changes to 1 the shield insert include:

a. Increasing the maximum shield length from 78-3/8 inches to 79 inches;

b. Decreasing the minimum 3-point lifting lug hole size from 1/2 inch to 3/8 inch;

c. Decreasing the minimum wall thickness from 3/4 inch to 1/2 inch; and i

d. Changing the longitudinal weld on the insert from double-sided, full penetration, MT inspection to double-sided, 1/4 inch, visual inspection.

In addition, The changes will not increase the maximum weight of the package.

since the liners are optional, the thinner liner will not affect the ability of the package to meet the shielding requirements for normal conditions of transport. These changes will not have an effect on the ability of the package to meet the requirements of 10 CFR Part 71.

The certificate holder has been changed from Pacific Nuclear Systems, Inc., to VECTPA Technologies, Inc., due to a corporate name change. VECTRA Technologies, Inc. has been issued Quality Assurance Program Approval for Radioactive Materials Packages No. 0192, under Subpart H of 10 CFR Part 71.

\

William D. Travers, Director Spent Fuel Project Office Office of Nuclear Material Safety  ;

and Safeguards Date: 5L \3 Ob l

i