ML18102A410

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Summary of 960917 Meeting W/Listed Attendees to Discuss Characterization of Radionuclides in Sg,Proposed Transportation Mode & Route & Packing of Sg.Handouts Provided by Pse&G Encl
ML18102A410
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/18/1996
From: Robert Lewis
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Easton E
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9609240327
Download: ML18102A410 (41)
v • d • e


Text

.

i September 18, 1996 NOTE TO:

Earl Easton, NMSS/SFPO FROM:

Robert J. Lewis, NMSS/SFPO

SUBJECT:

MEETING TO DISCUSS TRANSPORTATION OF SALEM ORIGINAL STEAM GENERATORS On September 17, 1996, staff from the Spent Fuel Project Office attended a meeting between Public Service Electric & Gas Company (PSE&G), its contractors, and the U.S. Department of Transportation (DOT).

PSE&G has submitted a request to DOT for exemption from certain DOT packaging requirements, for shipment of the four original steam generators (SGs) from the Salem power plant to the Barnwell, South Carolina disposal site. A representative from the State of New Jersey was also in attendance, and the relevant Region 1 health physics inspector participated by phone.

Items discussed at the meeting included ch,aracteri zat ion of the radi onucl ides in the SG, the proposed transportation mode and route, and the packaging of the SG.

A list of attendees to the meeting, and the handouts provided by PSE&G at the meeting are attached.

Attachments:

As stated Distribution:

  • . NRC F /C PUBLIC SFPO SShankman OFC SFPO/TSSS I c NAME Vv'--RLewis/lg DATE 9/('I) /96 C = COVER S:\\PROJ\\RXL\\SALEM.NOT E = COVER & ENCLOSURE OFFICIAL RECORD COPY N = NO COPY

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  • *,Salem Ul.it 1 Old Ste#m Generator

.,. IJ' Off Site Disposal Process --

~ -

September 17, 1996 - 10:00 am Doubletree Hotel Framatome Office - Suite #525*

1700 Rockville Pike Rockville, MD

* 'Salem ulit 1 Old Stelm Generator Off Site Dis osal Process Introduction and Project Overview Jerry Burford PSE&G Radiological Characterization of the Salem Unit 1 Old Steam Generators Peter Tuite WMG Surface Decontamination and Coating of the SIG Herb Cruickshank PSE&G Packaging/Sealing S/Gs,

  • One Foot Drop Calculations, and Assumptions Dr. C.Y. Chiou Raytheon Removing the Old Steam Generators from Containment and Onsite Transportation Transport from Parking Area to Barge and Barge Preparation Transport from Salem to Barnwell SC Bob Killen Raytheon Hisham Shamkani Chem.

Nuclear Hisham Shamkani Chem~

Nuclear

'Salem ulit 1 Old Stelm

  • Generator Off Site Dis osal Process Brief Historical Overview
  • *In the fall of 95, PSE&G discovered excessive tube degradation in Unit 1 Steam Generators
  • ** Subsequent ev*atuations dictated Steam Generator replacement as the preferred alternative to other repair options
  • Unit 1 Steam Generators will be removed and. placed in the low level waste storage building and, if required, a temporary parking area

".. Salem dlit 1 Old Stelm Generator Off Site Dis osal Process ---~=-

Compressed Schedule

-1 year vs. 3 to 4 years 30May96 25Sep96 - 150ct96 260ct96 - 07Nov96 11 Nov96 - 27 Jan96 First Quarter '97 Second Quarter '97 Start of Activities at Seabrook Site and at Salem Site Complete Prep Activities at Seabrook and Ship Generators to Salem Lift, Remove and Transport Old Steam Generators to Barge or Parking Location(s)

Transport, Rig, Lift, and install Replacement Steam.

Generators in Unit 1 Final system modifications, maintenance, and flushing Systems testing, turnover and Unit 1 return to service

  • 'Salem u!lit 1 Old Stea\\.

Generator Off Site Dis osal Process Important Highlights

  • PSE&G determined that the best/most suitable long-term alternative for the Steam Generators was to ship off-site for disposal
  • Local offic_ials concur with this disposal alternative
  • Local officials understand our possible need to place old generators in a temporary parking area
  • They also understand our ~ommitment to start shipment as expeditiously as possible

... soon after Mid-October

  • Mid-June and Early-July.... numerous phone calls with NRC, DOT, NEI and SGR utilities on shipment issues

~

  • ,
  • Salem ulit 1 Old Steam Generator Off Site Dis Important Highlights (Continued)~Allm
  • July 18, 1996 PSE&G attends the DOT lnteragency Working Group on the Transport of Radioactive Materials

- Provided overview of Project

- Radiological SG Characterization Data

- Discussed disposal considerations and need for IP-2 p~ckaging exemption

  • Week of August 12, 1996 - NRC Region I Inspection of ALARA and RAD-PRO planning activities

- Inspector performed a review of

  • exemption submittal and questioned analysis that concluded that generators were SC0-11

-Additional characterization work was done and forwarded to Inspector

. Salem Ulit 1 Old Stelm Generator Off Site Dis osal Process Important Highlights (Continued)

  • Subsequent phone calls regardi~g SC0-11 and 1 foot drop calculations
  • PSE&G asks DOT to host a meeting to discuss issues relating to the:

.Radiologi~al Ghar_acterization of th~

  • Salem Unit *1 SGs,.

SG packaging and one foot drop calculations, Offsite shipping and disposal process

  • by Chem Nuclear, and to Reaffirm our* need for expedited processing of our requested packaging exemption

Salem Steam Generator Characterization And.

Classification PSE&G

.... i

"~HOl..I!: co~

BOTrCl.I BLO'MlO~ ?IPE eorrou 5LOWDO'M'I CONHEC'IION t------COOl.ANT CHIJJSER PRIMARY MAHWAY

Steam Generator Surface A1.. eas Westinghouse Series 51 Primary Side Area cm2 Percent

  • Tube Bundle
  • 4.51 E+07 95%
    • Tube Sheet
  • 2.23 E+06 4.6%
  • Channel Head Bowl 1.40 E+05 0.3%
  • Divider Plate 7.10 E+04 0.1%

.e

  • *Total 4.75 E+07 PSE&G

EPRI Report NP-3107

  • Ref. Plant FPL Series 44

- Crud levels on Bowl and Tubesheet the same_

e

- Divider Plate 50% less than Bowl

- Tubes in Tubesheet axially non-uniform

- Tube bundle 14 times less than bow 1 PSE&G

EPRI Report NP-3107

.Impact.on 1996 Work

  • No Isotopic empirical data
  • Based entirely on Turkey Pt which is reported as atypical (see CORA plot)
  • Channel head bowl to tube bundle ratio of 14 not

. representative

  • Todays water Chemistry very different from 1980 water chemistry resulting in more uniform distributions PSE&G

110 12 LEGEND:

0} GAMMA RAV SOURCE STRENGTHS CALCULATED FROM STEAM GENERATOR 11 100

b.

TUBE SURF~CE SPECIFIC ACTIVITIES DETERMINED BY C.A. BERGMANN.

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D.W. PERONE, AND J. ROESMER UNDER EPRI RP026*2 10 0 f-90 I(

0 GAMMA RAV SOURCE STRENGTH FROM TABLE 4-1 AND TABLE4*5 u '

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Comparison of Steam Generator Tube S_us*fac:e Source Strengths

Salen1 Characterjzatio11 Methodology Dose To Curie Conversion

  • Contamination Assumed Uniformly Distributed (Based on Westinghouse Discussions)
  • Tube Bundle Source Region
  • Point Kernel Dose to Curie Conversion using MegaShield'
  • Same Methodology as Yankee and Trojan PSE&G

Salem Empirical Data

  • YAEL Part 61 Radiochemical Analysis of Sample e
  • Radiation Surveys of Individual Tubes

- 160 to 200 mR/hr @ contact

- 150 mR/hr maximum

- 60 to 70 mR/hr average PSE&G

Salem Steam Generators Relevance of EPRI Report Findings

  • Consider non-uniform distributions relative to Tube Bundle
  • CORA computer program plot can be used as
  • basis for consideration -of non-uniformity
  • Realistic Channel Head Bowl to Tube Bundle ratio then about 5 maximum PSE&G

I Salem Steam Generators Characterization Results

  • Radionuclide Activity

~

- Worst Case Steam Generator #11 - 143 Curies

  • . Inacces*sible Contamin.ation Level

- Tube Bundle (95% Area) - 3 uCi/cm2

  • Maximum Inaccessible Contamination Level

- Channel Head Bowl - 15 uCi/cm2 PSE&G

Salem Steam Generator DOT

.Classification Results

  • Greater Than Type A Quantity of SCO II Material
  • Reportable Quantity of Radioactive Material
  • Radiation Level Less Than 1 R/hr at. 3 meters from Unshielded Surface
  • Ship for Disposal as IP~2 Package PSE&G I_

STEAM GENERATOR SURFACE

. DECONTAMINATION

  • Remove loose paint from exterior surfaces
  • Perform contamination survey to quantify exterior loose surface contamination
  • Decontaminate exterior surfaces prior to coating to less than. 2200 dpm/100cm2

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Salem Steam Generator Transportation Safety Features D Steam Generator Handling/Tie-Down e Tie-downs desig~ed to meet ANSI 14.24 requirements 9

  • Jacking and cribbing used to limit potential drop distance to less than 6 inches D Security Features
  • Full time HP personnel escort
  • Police escort "during land transportation
  • Communications with project personnel every two hours

Salem Steam Generator Transportation Safety Features D Transportation Features

  • Barge Dual tug redundancy with redundant radar systems 21 individual water tight compartments (vs. standard 10-12 compartments) in barge *design

-. Special roll on I roll off design with notch and cutout for transition ramp ABS-certified load line

  • Land Transport
  • Speed limited to 5 mph Hydraulic platform with continuous leveling capability

IA!A NRC A Aft ANSI TIEDOWN REQUIREMENTS AND REGULATIONS TRUCK RAIL BARGE Piece* re*pon*lblllty onto the curler.

R*ll'llr** thet cHk function not b* lmpelred If ettechment point* on the c**k tell 10CFR71.45 Do** not epeclfy tledown requirement*, but doea regulet* the c**k *ll*chment point*

  • Th*** loed orlterl* are elmulteneouelr applled to th* cHk e...ter*et-*ewlty (e.g.) without Meterl*I yleldlng.

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