ML20035B118

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Summary of 930323 Meeting W/Util in Rockville,Md Re Discussions on Transport of SGs from Plant That Will Be Shipped to Barnwell.List of Attendees & Meeting Handouts Encl
ML20035B118
Person / Time
Site: 07109256
Issue date: 03/30/1993
From: Osgood N
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9303310157
Download: ML20035B118 (36)
v • d • e


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-3 IMTB:NLO IMg 3 0 W 71-9256-l:J MEMORANDUM FOR:

The Files

'FROM:

Nancy L. Osgood, IMTB, IMNS, NMSS

SUBJECT:

MEETING

SUMMARY

REGARDING TRANSPORT OF YANKEE-ROWE STEAM GENERATORS Attendees NRC Yankee Chem-Nuclear FHWA Ross Chappell Jane Grant Mirza Baig Henry Sandhusen Mort f irtile Bruce Holmgren Jim Braun Henry t :s John Parker Charles Witt Lockwood Bros.

Nancy Osgood R. L. Phillips Li Yang Introduction A meeting was held c.. March 23, 1993, in Rockville, Maryland, at the request of Yankee Atomic Electric Company. The meeting was held to discuss the transport of the steam generators from the Yankee-Rowe plant, which is being decommissioned. The components will be shipped to Barnwell for disposal.

Discussion The discussion centered on the attached meeting handouts.

Yankee described the route and the permits that will be obtained. Chem-Nuclear described the handling operations, and the structural analyses of the~ package.

l It was requested that the Federal Highway Administration (FHWA) review the road, bridge and dam, over which the package will be transported. The FHWA stated that they could do a route survey and review calculations of the structures. FHWA estimated that the review would take about two weeks.

The request for FHWA involvemert will be from the NRC.

Original Signed By Nancy L. Osgood Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS.

Attachments: Meeting handouts DISTRIBUTION With Attachments:

NRC PDR NRC File Center CEMacDonald F

Without Attachments:

NMSS r/f IMTB r/f Attendees Meeting Notebook

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-YAEC STEAM GENERATOR TRANSPORT MEETING i

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ATTENDEES:

Nuclear Regulatory Commission Yankee Atomic Electric Co.

Chem-Nuclear Systems, Inc.

- Lockwood Bros.

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. AGENDA FOR MEETING l

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YANKEE ATOMIC ELECTRIC COMPANY AND NUCLEAR REGULATORY COMMISSION i

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INTRODUCTION

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LAST MEETING FOLLOW-UP ITEMS l

STEAM GENERATOR PACKAGE DESCRIPTION TRANSPORTATION i

TRANSFER PROCESS i

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OPERATING PROCEDURES i

CONTAINMENT ACCEPTANCE TESTING l

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4 YNPS COMPONENT REMOVAL PROJECT '93

-STATijS OF CNSI DCF LICENSE-9 State of South Carolina is Agreement State O

DCF is licensed by State for possession of radio-active materials

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YNPS COMPONENT REMOVAL PROJECT '93

-STEAM GENERATOR SHIELDING-t insulation and lagging provide only a small contribution to the shielding.

This effect will be accounted for in the shielding model.

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ROADWAY TRANSPORTATION i

i ROADWAY HAUL ROUTE IS 6+ MILES LONG ROAD TRANSIT IN MASSACHUSETFS BEGINS AT SITE BOUNDARY IN TOWN OF ROWL t

ACROSS NEW ENGLAND POWER COMPANY BRIDGE SOUTH ONTO READSHORO ROAD TOWN OF MONROE, FRANKLIN COUNTY READSBORO ROAD CHANGES TO RIVER ROAD TOWN OF FLORIDA, BERK. SHIRE COUNTY: RIVER ROAD ARRIVE AT RAILROAD NEAR HOOSAC TUNNEL FLORIDA, MASSACHUSETTS 4

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YANKEE ATOMIC ELECTRIC COMPANY COMPONENT REMOVAL PROJECT ROADWAY TRANSPORTATION HAULER: LOCKWOOD BROTHERS, INC.

VEHICLE: HYDRAULIC PLATFORM TRAILER AND TRACTOR TRAILER: 7 LINES OF AXLES - 14 SPLIT AXLES 1'

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COMPONENT REMOVAL PROJECT ROADWAY TRANSPORTATION i

COUNTIES ARE THE LEGAL OWNERS OF READSBORO AND RIVER ROADS FRANKLIN AND BERKSHIRE COUNTIES HAVE JURISDICTION OVER THESE ROADS l

STATE ISSUES OVER. WEIGHT PERMITS ON STATE HIGHWAYS AND ON COUNTY / TOWN ROADS WHICH HAVE:

M BRIDGES OVER 20 FEET LONG - OR CULVERTS OVER 20 FEET WIDE NO SUCH STRUCTURES ON THE IIAUL ROUTE -

NO STATE INVOLVEMENT IN REVIEW PROCESS TOWNS ISSUE OVERWEIGHT PERMITS ON COUNTY AND TOWN ROADS PERMITTING PROCESS IS ESTABLISHED BY EACH TOWN j

YANKEE AND CNSI WILL ANALYZE ALL CULVERTS ALONG THE ROUTE a

ROADWAY CULVERTS ANALYZED IN ACCORDANCE WITH STANDARD SPECIFICATIONS FOR HIGHWAY BRIDGES, 15th EDITION - 1992 THE AMEIUCAN ASSOCIATION OF STATE HIGHWAY &

TRANSPORTATION OFFICIALS APPROPRIATE MEASURES WILL BE TAKEN TO ASSURE CULVERTS ARE NOT DAMAGED BY THE HEAVY HAUL 1

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YANKEE ATOMIC ELECTRIC COMPANY COMPONENT REMOVAL PROJECT ROADWAY TRANSPORTATION i

TOWN OF MONROE:

COUNTY ENGINEER HAS REQUESTED CALCULATIONS WIIICH VERIFY ACCEPTABILITY OF CROSSING ALL ROAD CULVERTS TO BE SUBMITTED BY REGISTERED PROFESSIONAL ENGINEER TOWN OF FLORIDA:

COUNTY SURVEYOR HAS REQUESTED THE SAME i

INFORMATION AN INDEPENDENT SURVEYOR WILL INSPECT THE ROAD BED AND CULVERTS BEFORE AND AITER THE LAST HAUL NO DAMAGE IS EXPECTED; HOWEVER, IF THE SURVEY

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REVEALS ANY DAMAGE RESULTING FROM THE HAULS, THAT DAMAGE WILL BE REPAIRED IN FULL YANKEE WILL PROVIDE STATE POLICE COVERAGE DURING THE ENTIRE TRANSPORT PROCESS 4

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1 SHERMAN DAM SPILLWAY BRIDGE:

APPROXIMATELY 70 FEET LONG 5

OWNED BY THE NEW ENGLAND POWER COMPANY NEW ENGLAND POWER CO. STRUCTURAL ENGINEERING DEPARTMENT WILL REVIEW ~ OUR PLAN FOR TRAVERSING TIUS BRIDGE STRUCTURAL ANALYSIS OF BRIDGE BASED ON:

STANDARD SPECIFICATIONS FOR HIGHWAY BRIDGES, j

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- TRANSPORTATION -

l SAFETY PRECAUTIONS FOR YAEC STEAM GENERATOR TRANSPORT _

i Transportation Route j

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O Transported once; carefully planned route e

Direct route Filled with low density concrete to encapsulate contaminants and l

prevent their dispersal 9

All openings on the steam generators will be completely seal-welded shut.

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Planned, controlled transfers between conveyance modes l

e Hazardous weather conditions avoided j

i Trailer (Road) e Hydraulically leveled trailer, specifically designed for hauling heavy loads

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Trained, experienced personnel operating trailer e

Accompanied by qualified health physics technician l

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SAFETY PRECAUTIONS FOR YAEC STEAM GENERATOR TRANSPORT (Cont'd) l I

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Capability of maintaining communications between train engi-l neer and base of operations j

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9 Qualified, federally licensed train engineer, familiar with the route to be taken j

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impact limiters to be used 8

17 lb/ft' rigid polyurethane foam, encased in thin-j sheet metal covering f

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Toroidal in shape with a rectangular cross-section.

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l Impact Limiter Design Criteria j.

The impact limiter design will insure that:

8 No steam generator containment penetrations-(nozzles, manhole, handhole etc.) will directly im-l 3

pact the flat unyielding surface during the 1-foot 4

drop.

The stresses developed in the shell of f.he steam l

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i Steam Generator Drop Orientations Drop analyses to be performed for one-foot. drop with initial orientation perpendicular to the axis of the steam genera-t tor. Effects of the following scenarios to be considered:

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The steam drum end of the steam generator con-tacts the rigid surface first, the other end follows.

(2)-

The channel-head end of the steam generator con-tacts the rigid surface first, the other end follows.

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Both the ends contact the rigid surface simulta-l neously.

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YNPS COMPONENT REMOVAL PROJECT '93'

-- STRUCTURAL --

IMPACT ANALYSES PROCEDURE:

1 Step 1 The force deflection response of the impact limiter will be established using the CNSI proprietary pro-gram, CASKDROP. Energy absorbed versus the crush depth relation will be established for the l

impact limiters.

I Step 2 Energy balance criteria will be used to estimate the impact limiter crush depth during the three drop scenarios.

Step 3 The crushing pressure obtained from Step 1 will be used to evaluate the shell stresses. Analytical formulas or ANSYS finite element analysis will be used for this purpose.

YNPS COMPONENT REMOVAL PROJECT '93

- STRUCTURAL -

Lifting Attachments (10 CFR 71.45) l

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9 Steam generators not lifted from saddles during transport i

e Structural parts that could be used for lifting rendered inoper-i able.

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YNPS COMPONENT REMOVAL PROJECT '93

- STRUCTURAL -

Package Material Toughness (10 CFR 71.71(c))

S Steam generator package - Category lli container 0

Fracture toughness criteria of Regulatory Guide 7.11 (Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Ves-seis with Maximum Wall Thickness of 4 inches) will be met.

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YNPS COMPONENT REMOVAL PROJECT '93.

-- STRUCTURAL -

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i Table 1 Category I Category II Category III l

Low Greater than Ims than 7

Speci5c 30,000 Ci or 30,000 Ci l

Activity greater than.

and less than i

3,000 A,* or 3,000 A i greater than and less than 3,000 A '

3,000 A 2

2 Special Greater than Between Less than i

Form 3,000 A 3,000 A, and 30 A and i

i or greater than 30 A,~and not less than 30,000 Ci greater than 30,000 Ci 30,000 Ci j

t Normal Greater than Between.

Iess than Form 3,000 A, 3,000 A, and 30 A, or greater than 30 A and not and less than l

2 30,000 Ci greater than 30,000 Ci.

30,000 Ci b

f i

m3

=m

'?

,+

y YNPS COMPONENT REMOVAL PROJECT '93 l

- STRUCTURAL -

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a f

TABLE 6.

Category III fracture toughness requirements and uiteria for ferritic steels with yleid strength no f

greater than 100 ksi.

.}

Required degree of safety Adequate smargle of safh.

(aw Appeedix C)

Regissid amoest of fracture toughness Sumcleat to scetent fracture laitiatlas as salmar defects typical of (see Sec. 5) go'od fabricatios practicus.

[

Thklaess (B) l (IL)

Criteria for sneetle; toeghness requiremeses

.j i

8A to 4.0

  • Without testing, ese may monas!! zed sted acade to "Ilme Grala Pracdee"er better".

I I

See Sec. 51L

[

Or j

  • Show that NDTb < 10'F (B > 0425 in.).

Or

  • Test to show that Df > $0 ft-Ib at 10'T, with test specimec 0415 is.' thick.

a Or

  • Test to show that Cyd > !$ ft-Ib at 10'.

Or j

i

  • Without testing, ese swo!!ed steet, provided the welds bare trees stress reik-ad and 5

inspected by rendestructive evalaatica techniques.

[

i 1

Ims thu CA

  • No requiremests when B is less than 0.4 in.

See Sec. 511 i

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Reference:

Regulatory Guide 7.11 1

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YNPS COMPONENT REMOVAL PROJECT '93

(

-- STRUCTURAL -

Top Head ASTM A-212 Gr B Nozzle Closure Cap (typ.)-l l

(

SA 516 Gr 70 f

J l

i l

~

Upper Vessel j

ASTM A-212 Gr B

{

A 7

t

.h

\\

I dransition Cone

{

f STM A-212 Gr 6

I

)

i Ixwer Vessel

,j-*

ASTM A-212 Gr B 4

l 7

fabe Sheet C5 i

ASTM A-266 Gr II q j

l b5Pr#!N##Ah 4

annel Head Forgin, k

ASTM A-266 GrII l

r i

-t

+"

b YNPS COMPONENT REMOVAL PROJECT '93

-- STRUCTURAL --

Charpy V-Notch and Drop Weight Test Values (References 2.G & 2.7)

Location /

Specified Charpy V-Notch Value at 10 F Actual Charpy V-Notch Value at 10'F Comments Material Ref. Drawing No.

Impact Energy (f t lb)

Ref. Test No.

Impact Energy (ft-lb)

Bottom Head /

492C241 15 EA206 18.5, 22, 20 Forging quenched ASTM A-206 Gr 11 and tempered to (Coolant Channel) enhance impact properties.

Tube Sheet /

402C241 15 E5220 9, 14.5, 20 ASTM A-2GG Gr ll Cylindrical Verral Lower Vessel /

492C435 15 20681 34,37,39 Shell quenched and ASTM A-212 Gr B tempered to enhance impact properties.

Transition Cone /

492C435 15 9152 30,39,45 ASTM A-212 Gr B l

Upper Vessel /

492C435 15 19365 46,34,40 ASTM A-212 Gr B Hemispherical Head /

2G7A477 15 15637 14,16,15 Shell quenched and ASTM A-212 Gr B tempered to enhance impact properties.

i YNPS COMPONENT REMOVAL PROJECT'93 l

- OPERATING PROCEDURES -

GENERAL TRANSPORT SCENARIO l

i PRE-TRANSPORT CHECKS l

9 Notificat;ons 1

States:

Office of the Governor, Chief Radiological Officer i

Local:

Towns, Community, County Officials O

Inspections (Rail Car, Engine, Tie-down)-

Boston & Maine l

Conrail CSX l

e Reporting Requirements Rail: Centralized Traffic Control System l

CNSI: HP Technician l

l i

e Communications j

i Primary Auxiliary O

Weather No inclement weather that may threaten the safety of the rail transport i

ROAD TRANSPORT i

I O

Trailer: Hydraulic platform trailer 210 ton capacity 9

Speed: not to exceed 5 mph 9

Traffic: Escorts will be provided for traffic control i

RAll TRANSPORT e

Car: eight axle flat car 160 ton capacity e

Speed: not to exceed 35 mph l

0 Traffic: Dedicated transport EMERGENCY RESPONSE i

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I f

f YNPS COMPONENT REMOVAL PROJECT '93 l

- CONTAINMENT -

9 Exemption for LSA materials in 10CFR71.52 from quantitative containment requirements I

e 10CFR71.52 raaffirms that the requirements of 10CFR71.43(f):

j (1) no loss or dispersal of radioactive contents, (2) no significant increase in external radiation, (3) no substantial reduction in the effectiveness l

of the packaging G

Chapter 2 shows there will be no significant increase in external radiation, and no substantial reduction l

9 Three successive mechanisms prevent dispersai:

-i 1.

Adhesion of film containing contents 2.

Encapsulation of contents with the low density con-crete 3.

Seal-welded containment barrier

{

Two additional mechanisms even in the unlikely event of a failure-of one j

7 e

Therefore, containment criterion requirements of 10CFR71.43(f) l are met.

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YNPS COMPONENT REMOVAL PROJECT '93

- ACCEPTANCE TESTING -

'O Radiation surveys to be performed to ensure:

(1) contents within parameters established in the SAR i

(2) within regulatory limits of 10CFR71.47 0

Visual inspection to be performed before shipment.

O New welds to inspected per ASME Code, Section Vill, Div.1, and Section V.

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