ML20127N881

LLRW Shipment Insp Repts 50-352/PA-92-02 & 50-353/PA-92-02 on 921116-18.No Violations or Deviations Noted.Major Areas Inspected:Licensee LLRW Shipment to Burial Site Including Shipping Documentation,Package Insp & Contamination Surveys

ML20127N881
Person / Time
Site:	Limerick
Issue date:	12/31/1992
From:	Dornsife W, Maingi S PENNSYLVANIA, COMMONWEALTH OF
To:
Shared Package
ML20127N838	List: ML20127N835 ML20127N872 ML20127N881
References
NUDOCS 9302010111
Download: ML20127N881 (9)

Text

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l Pa. Department of Environmental Resources j Bureau of Radiation Protection J

-Division of Nuclear Safety Report Nos. 50-352/PA-92-02 '

50-353/PA-92-02 Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 Licensee Philadelphia Electric Company Correspondence Control Desk P.O. Box 195 Wayne, PA 19087-0195 ,

Facility Name: Limerick Generating Station, Units 1 and 2 Inspection Dates November 16, 17 & 18, 1992 Inspectors: ,#_ ,6 S.P. Maing1, Nucleat/ 2ngineer

/ 3[!92

' Dats Approved by: -

/t1 / fck W. Dornsife, Director .

Dat6 Bureau of Radiation Protection Inspection Summary: Inspection on November 18, 1992-(Inspection Report Nos. 50-352/PA-92-02; 50-353/PA-92-02)

Areas Inspected: Announced inspection of the licensee's low level radioactive waste shipment to the burial cite including: shipping documentation, package inspection,-labeling, marking, placarding, vehicle inspection, radiation and contamination surveys.

Results: No violations or deviations were identified.

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^ 9302010111 930119 PDR ADOCK 05000352 O PDR 4'

DETAILS 1.0 Individuals Contacted 1.1 Licensee Personnel

• K. Cenci, Senior Engineer Radwaste

• L. Wells, Radwaste Supervisor Services

• H. Paust, Radwaste Physicist

• N. Harmon, Radwaste Physicist

• J. Campanini, Radwaste Technical Assistant

• D. Voigt, Quality Verification Inspector

• B. Rutkowski, Health Physics Technician

• G. Roach, Superintendent - Services

• Denotes those had meetings with as part of the exit.

2.0 Scope of the Inspection This inspection was conducted in accordance with the Memorandum of Understanding (MOU) between the Commonwealth of Pennsylvania and the U.S. Nuclear Regulatory Commission. The State inspector reviewed the licensee's low level radioactive waste shipment no.

LG-037-92 to the Barnwell Waste Management Facility according to the attached inspection checklist.

This was the third of the three shipments of the irradiated core components to Barnwell LLRW Disposal Site. The various components had been collected in the Spent Fuel Pool over the period of operations at LGS. Due to the impending closing of the LLRW disposal sites the licensee made the timely decision to clean up -

the spent fuel pools of the extraneous materials hanging around in .

the spent fuel pools and shipout for disposal.

These components had been cut and collected in three 3-55 steel liners and were being shipped in CNS-3-55 casks. This shipment contained 26,800 curies of irradtated core components with a waute volume of 3.3 cubic feet packaged in a 3-55 steel liner with a disposable volume of 57.4 cubic feet. The container was shipped in the CNS-3-55-2, NRC certified Type B shipping cask.

4 The inspector observed the receipt inspection of the empty cask and unloading activities of the cask by the licensee staff and contractors. Prior to lowering of the cask into the loading bay for placement of the liner in the cask, the inspector reviewed the pre-use inspection documentation for the liner; certificate of compliance for the cask; cad- handling procedure and observed the licensee perform an inspection cf the cask to ensure that the cask was in a satisfactory material condition for the shipment.

Pursuant to the removal of the cask from the loading bay and to preclude leaching out of the contamination during transit to disposal site, swipe samples were periodically taken after de:ontamination for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, to validate stabilization.

The inspector witnessed the loading of cask on the trailer, placement and bolting down of the personnel barrier and placement of the security seals.

The inspector observed licensee personnel perform the radiological survey of the shipment and performed independent radiological survey of the shipping cask with the liner before and after installation of the personnel barrier. The highest reading detected at contact with the personnel barrier mounted over the cask was 22 mR/hr and no removable contamination was detected from the smear samples taken at the representative locations on the surface of the barrier and the vehicle. The inspector witnessed the Quality Verification Representative review the shipment documentation and physical transfer of shipping documentation to the driver.

A visual inspection of the vehicle was performed to ensure that the vehicle was in acceptable condition for transport.

The inspector performed an independent verification of the licensee's calculations for waste classification for DOT TYPE and

~ Burial Class determination. The shipping papers were reviewed for completeness and accuracy. No discrepancies were noted.

3.0 Exit Meeting The inspector met with the licensee representatives denoted in Section 1.0 at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection.

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PENNSYLVANIA DEPARTMENTOF ENVIRONMENTAL RESOURCES

, BUREAU OF RADIATION PROTECTION DIVISION OF NUCLEAR SAFETY ~

LOW LEVEL R ADIO ACTIVE WASTE StilPMENT ,

INSPECTION REPORT

' REVISION I 50-352/PA-92-02 Report No. 50-353/P A-92-02 A. General Information L Date ofinspection 11-16,17 & 18, 1992

2. Name of Shipper I,imerick Generating Stntion

3. Name of Carrier Chem Nuclear Systems, Inc.

4. Destination 11arnwell Disposal Site, SC 5, Verify Advanced Notification to the Consignee Yes, and notifiention updated.

[ Fissile materials, and Type B or highway route controlled quantities - 49 CFR 172.22(c)1

6. Verify Advanced Notification to the State (s) Yes to PA; MDs _W VA: VA: NC; SC and NRC

[(Type B packages only - 10 CFR 71.97)]

7. Package (s) Used X Cask CNS 3-55-2 HIC X Liner 3-55 Stcel liner Drums Boxes

! Other(Specify)

8. Number of Packages one

9. Method ofShipment A. X Exclusive Use B. _ Non Exclusive Use

! 10. Transport Vehicle Open X Closed with personnel barrier bolted over the cask. _

B. Shipping Documentation Checklist

1. X Shipping papers present(49 CFR 172.200,201,202,203) l 2. X Proper shipping name and hazard class (172.202(a)]

3. X Proper I.D. number (172.202(a)J C #

4. X Waste Description h!$[ rfel EcfE,"v0100N[lkIO{kOr'3 iO!l}"sYu$N bh total quantity by weight (lbs)(172.202(a)] Liner 7582.2 volume (cu. ft.)(172.202(a)) 57.4 cuble feet . activity (Ci)(172.203(d)l "26,800 _

19. ' 'X - Radioauclides identmed (10 CFR 20,311(b) & 49 CFR 172.203(d)l:

" X l6. Total quantity of radionuclides S3, C 14, Tc-99 and I-129 shawn (10 CFR 20.311(b)) -

7. X Waste classified and characterized properly (61.55,61.56 and BTP) -

(Perform a review of documentation for classification and characterization to determine if '

= classification is correct and reasonable)

8. - X _

. Description of chemical / physical form (172.2.03(d))

L 9. ' Y-Ill - Category oflabel applied to each package (172.203(d))

10. NA T.I. assigned to each package bearing Y II or Y !!!(172.203(d)] '

11. X- = Shipper's certification (172,204(a)) '.

12. X Instructions to carrier provided (173.441(c),173.425(b)] (exclusive use only)

C. Packaging / Package Inspection

a. Packaging Compliance X Are authorized packages used? (173.415,173.416]

Package types used:

NA LSA strong tight (173,425(b))

DOT 7A, Type A .

NA

- Performance test records on file? [173.415(a)]

NRC Certified X

Current NRC COC's on file? [10 CFR 71.12(c)]

X Registered with NRC NMSS as user? [71.12(c)) -

(Prior to the licensee's first t.se of the package) -

b. Security Seals and Pack' age Integrity X Security seals (173.412(b)](LSA-Exclusive use, closed vehicle exempt)

X Lids secure (173.475(c)]

X No visible damage or leakage (173.425(b))

X packages surveyed for radiation (173,441] and contamination (173.4431 7

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D.-' -Labeling, Siarking and Placarding Checklist

1. 'a. Labeling X Packages labeled W-1, Y-II, Y III(172.403(b),(c)) Y-Ill (LSA - Exclusive use exempt)

X

" Contents" a nd " Activity" en tered [172.403(g))

X Transport Index afTixed on Y-!!. Y-III labels [172.403(g))

b. Starking X Packages marked properly, i.e., proper shipping name, identification number, DOT Spec.

number, NRC COC number, consignee or consignor's name and address, etc. (172.301,304,306)

X Type A/ type B package marked " Type A"or" Type B"[172.310(a))

X

- Gross weight marked if package exceeds 110 pounds (172.310(all '

X Waste class marked A-B-C stable / unstable [10 CPR 20.311(d)(2)]

NA LSA Exclusive use package marked " RADIOACTIVE-LSA"[173.425(b)]-

c. Placarding X Placards on each end and sides of vehicle for Y III, LSA exclusive use and highway route ,

controlled quantity [172.504(a), 506, 507,173.425(b))

E. Vehicle Inspection Checklist X

Verify that vehicle was monitored and inspected by the licensee upon arrival.

X Shipment blocked, braced, tied down in vehicle [173.425(b)]

X Ensure that the licensee surveys the shipment adequately using proper instruments. Review the licensee's survey map (s) to verify that all the required readings are performed and they are in ~

reasonable agreement with inspector's. "

P. ~ Radiation / Contamination Survey [49 CFR 173.441,173.443]

a. Exclusive Use Vehicles 0.1 Not exceed 2 mR/hr in any occupied position in the vehicle 3.8 Not exceed 10 mR/hr at 2 meters (6.6 ft) from the vehicle I' 19.0 Not exceed 200 mR/hr on outer surface (including upper or lower) of the vehicle 22.0 Not exceed 1,000 mR/hr on the external surface of the package (closed transport vehicle)

NA Not exceed 200 mR/hr on the external surface of the package (open transport vehicle)

b. Non-Exclusive Use Vehicles L NA Not exceed 10 mR/hr n 1 meter (3.3 ft) from package NA' Not exceed 200 mR/hr on the external surface of the package 3-

Highsst Contamination Dstectsd

. c. i Not exceed 22 dpm/cm2 (beta & gamma) ~'

- _ (Wipe sample for 300 cm2)

Highest Contamination Detected 52 CPM Background Reading 39 CPM Difference /Above Background 13 CPM-Divide by Instrument Efficiency (0,10) 130-Divide by(300 cm2) _

0.43 DPM/CM2 RADIATION / CONTAMINATION SURVEY (transport vehicle)

Surfaco 22 - mR/hr 2 meters 38 - mR/hr Cab / Sleeper Surface (bottom) Surface 11 mR/hr 0.1 mR/hr 19 mR/hr 2 meters 0.8 mR/hr -

Surface 22 mR/hr <

2 meters 3 0 ,,, mR/hr.

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• Results cfInspsetien -

I. Violations /Non Ccmpliance Within the scope of this inspection, no violations were observed.

II. Comments Instruments Used Instrument (s) Serial Calibration Expiration Tvoe No. Date Dose Rate Eberline ESP-2 00309 2-24-93 U E~2 Instrument Contamination Eberline ESP-2 00309 2-24-93 Instrument IIP-210' Inspector's Name S. P. Maingi l

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