ML20236Y285
| ML20236Y285 | |
| Person / Time | |
|---|---|
| Site: | 07109271, Trojan File:Portland General Electric icon.png |
| Issue date: | 08/08/1998 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20236Y257 | List: |
| References | |
| PGE-1076, NUDOCS 9808120049 | |
| Download: ML20236Y285 (65) | |
Text
PGE-1076 O
PORTLAND GENERAL ELECTRIC COMPANY TROJAN REACTOR VESSEL PACKAGE SAFETY ANALYSIS REPORT ENVIRONMENTAL REPORT f
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August 8,1998 Portland General Electric Company 121 SW Salmon Street Portiand, Oregon 97204 l
O 9808120049 980808
{DR ADOCK 05000344 PDR
I Trojan Reactor l'essel Package - Safety Analysis Report - Environmental Report O
v TABLE OF CONTENTS 1.0 INT R O D U CTI O N.................................................... E-1 2.0 ENVIRONM ENTAL EVALUATION.................................... E-1 2.1 IDENTIFICATION OF THE PROPOSED ACTION.................... E-1 2.2 THE NEED FOR THE PROPOSED ACTION......................... E-3
2.3 DESCRIPTION
OF THE ENVIRONMENT AFFECTED BY THE P RO POS E D A CTI ON............................................ E-3 2.4 ENVIRONM*.NTAL IMPACTS OF THE PROPOSED ACTION......... E-4 2.4.1 EFFECT ON HUMAN ACTIVITIES.......................... E-4 2.4.2 EFFECTS ON TERRAIN, VEGETATION, AND WILDLIFE...... E-5 2.4.3 EFFECTS ON ADJACENT WATERS AND AQUATIC LIFE...... E-5 2.4.4 EFFECTS OF RELEASED RADIOACTIVE MATERIALS........ E-5 2.4.5 EFFECTS OF RELEASED CHEMICAL AND SANITARY WA S T E S.............................................. E-6 2.4.6 EFFECTS ON RADIATION EXPOSURE TO THE PUBLIC....... E-7 2.4.7 CONSEQUENCES OF A NON-CREDIBLE REACTOR VESSEL CONTAINMENT BREACH................................. E-7 2.5 ALTERNATIVE TO THE PROPOSED ACTION...................... E-8
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2.5.1 RADIATION EXPOSURE (ALARA)......................... E-9 2.5.2 NUMBER OF RADIOACTIVE WASTE SHIPMENTS......... E-10 2.5.3 S C H E D U L E............................................. E-10 2.5.4 TOTA L C O S T......................................... E-I l 2.6 ALTERNATIVE USE OF RESOURCES............................ E-13 2.7
SUMMARY
AND JUSTIFICATION OF EXEMPTIONS............... E-13 2.7.1 NRC EXEMPTIONS..................................... E-13 2.7.2 DOT RELATED EXEMPTIONS........................... E-14 2.8 REGUL ATORY GUIDE 7.12 ALTERNATIVE.................. E-15 2.9 STATU S OF COM PLI ANCE..................................... E-16 3.0 RECOVERY PLAN FOR THE TROJAN RVP OVERBOARD AND LAND TRANSPORT DROP SCENARIOS.................................... E-17 3.1 WATE R TRAN S PO RT...............
.............. E-1 8 3.1.1 DEEP WATER RECOVERY.............................. E-18 3.1.2 SHALLOW WATER RECOVERY.......................... E-19 3.1.3 PACKAGE OVERBOARD DAMAGE..................... E-19 3.2 L AND TRAN S PO RT.......................................... E-20 3.2.1 RECOVE RY............................................ E-2 0 3.2.2 PACKAGE DAMAG E.................................... E-21 I
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APPENDIX E-1, CONTINGENCY PLAN FOR PACKAGE RECOVERY i
August 8,1998
Trojan Reactor l'essel Package - Safety Anah sis Report - Environment! Report p
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1.0 INTRODUCTION
This Environmental Report evaluates the environmental impact of the proposed action of shipping the Trojan Reactor Vessel Package (RVP) to an approved disposal site on the Hanford Reservation near Richland, Washington. The report is submitted by Portland General Electric Company (PGE) in response to a request by the Nuclear Regulatory Commission (NRC) in a letter, dated July 9,1998, which transmitted," Trojan Reactor Vessel Package Request for Additional Information." The report is prepared in accordance with 10 CFR 51.45,
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" Environmental Report," to facilitate the NRC's preparation of an Environmental Assessment in accordance with 10 CFR 51.30," Environmental Assessment," for approving the proposed action under an exemption per 10 CFR 71.8," Specific Exemptions." Additionally, this Environmental Report specifically addresses Questions E-1 through E-4 of the request for additional information.
2.0 ENVIRONMENTAL EVALUATION 2.1 IDENTIFICATION OF THE PROPOSED ACTION n
Contingent upon the receipt of required regulatory approvals, the Trojan Reactor Vessel Package i,~)
(RVP) will be shipped as a Type B (as exempted), exclusive use, radioactive material transportation package for the purpose of disposal at the US Ecology low level radioactive waste facility on the Hanford Nuclear Reservation near Richland, Washington.
The defueled reactor vessel will be prepared as a Type B (as exempted) shipping package. The reactor vessel is a large, thick-walled, steel structure measuring approximately 42' 6" long and 17' 1" in outside diameter. It was a Safety Class 1 vessel originally designed in accordance with the requirements of the ASME Code, Section Ill (1968 edition with Addenda throud, Winter 1968). After preparation, the RVP will be shipped approximately 300 miles from the Trojan Nuclear Plant site to the US Ecology disposal facility. During the shipment, the RVP is expected to be outside the Trojan Nuclear Plant site and US Ecology facility boundaries less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
As described in the RVP Safety Analysis Report (SAR), the RVP will be assembled as follows:
A.
Reactor vessel extemal surfaces will be decontan,inated, as necessary, to ensure compliance with 10 CFR 71.87(i) and will be coa.ed to fix any residual contamination.
B.
Reactor vessel external attachments will be removed, sealing 0-rings installed, and the reactor vessel head installed and tensioned using 54 head studs and nuts.
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C.
The reactor vessel void space, with internals installed and intact, will be filled with low density cellular concrete (LDCC) to prevent movement of radioactive material within the reactor vessel. This will stabilize dose rates during transport, limit any potential accident related releases, anj provide radiation shielding.
The bulk (99.99%) of the approximately 2 million curies of activity in the RVP is in the form of activated metal, which cannot be released to the environment in particulate or gaseous form. Intemal contamination is approximately 155 curies, which is less than the contamination contained in the Trojan Steam Generators which were successfully licensed and shipped as greater than Type A, low specific activity (LSA) packages.
The fissile material content of the RVP will consist of 3.56g of Plutonium, and is contained within the internal contamination.10 CFR 71.53(a) provides that a package containing not more than 15g of fissile material is exempt from fissile material classification and from the fissile material standards of 10 CFR 71.55 and 10 CFR 71.59.
D.
Penetrations will be sealed with welded closures that have been designed to meet regulatory requirements for a!! conditions of transport.
E.
Steel shielding will be installed on the exterior surface of the reactor vessel, as necessary,
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to comply with the dose limit requirements of 10 CFR 71.47 and 10 CFR 71.51.
Radiation surveys will be conducted to verify the requirements are met.
F.
Th: RVP will be removed from containment, lowered to ground level, and secured onto a sp ecially designed transporter using an engineered tiedown system.
G.
I apact limiters will be installed to minimize reactor vessel stresses due to the analyzed l
- VP drops.
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As described in Chapter 8 of the SAR, acceptance tests and inspections will be performed on the RVP, before it is transported, to ensure compliance with the requirements of Subpart G of 10 CFR 71.
After preparation as a shipping package as discussed in Chapter 2 of the RVP SAR, the RVP will be loaded onto a transporter at the Trojan site and transported as an exclusive use shipment. The RVP will be secured to the transporter by an engineered tiedown system. This tiedown system is designed to meet the requirements of ANSI N14.2," Proposed American National Standard Tiedowns for Truck Transport of Radioactive Materials." Once loaded onto the transporter, the RVP will not be removed until it is off-loaded into the disposal trench at the US Ecology disposal facility.
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C The shipment will comply with the specifications of ANSI N14.24-1985,"American National Standard for Highway Route Controlled Quantities of Radioactive Materials -Domestic Barge Transport," and with the applicable requirements of 10 CFR 71 -Packaging and Transportation of Radioactive Material (as exempted),33 CFR - Navigation and Navigable Waters,46 CFR -
Shipping, and 49 CFR -Transportation (as exempted).
The RVP-loaded transporter will be moved and secured onto a specially designed barge at the Trojan barge slip. The RVP will be shipped up the Columbia River (approximately 270 miles) to I
the Port of Benton in Washington. After the barge off-load, the RVP-loaded transporter will be l
moved to the US Ecology low level radioactive waste facility for disposal.
l 2.2 IHENEED FOR THE PROPOSED ACTION i
The Trojan Nuclear Plant was shutdown in November 1992, and on January 27,1993, Portland General Electric Company notified the NRC ofits decision to permanently cease power operation and subsequently defueled the reactor, storing the spent fuel in the Trojan spent fuel l
pool. Currently, PGE has a possession-only license under 10 CFR Part 50 and applied to terminate its license on January 25,1995, by submitting a decommissioning plan. PGE proposed to decommission the facility using a dismantlement or DECON approach as defined in the " Final
/~N Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities,"
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NUREG-0586, dated August 1988.
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i in accordance with the NRC-approved decommissioning plan, PGE's plans for decommissioning the Trojan Nncl:ar Plant include decontamination and dismantlement of contaminated structures, systems, and components. The removal of the Trojan reactor vessel and the internals is an l
evolution that is discussed in the decommissioning plan, and is necessary for completion of decommissioning and release of the site for unrestricted use.
2.3 DESCRIPTION
OF THE ENVIRONMENT AFFECTED BY THE PROPOSED ACTION The Trojan Nuclear Plant is located in Columbia County, Oregon, approximately 42 miles north of Portland, Oregon, on the Columbia River at Mile 72.5 from the mouth. The site consists of approximately 634 acres incorporating a recreational area / park, various office buildings, and an industrial area enclosed by a security fence. The Trojan barge slip is located just south of the industrial area on the Trojan site. The river at this location is the boundary between the States of Oregon and Washington.
The Port of Benton in Washington is located approximately 270 miles up the Columbia River from the Trojan Nuclear Plant. The licensed US Ecology low level radioactive waste facility is A
located on the Hanford Nuclear Reservation near Richland, Washington, less than 30 miles V
overland from the Port of Benton.
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2.4 ENVIRONMENTAL IMPACTS OF THE PROPOSED ACTION The RVP will be assembled and shipped approximately 300 miles as a one-time shipment from the Trojan Nuclear Plant to the US Ecology disposal facility located on the Hanford Nuclear Reservation near Richland, Washington. The expected duration of the land transport will be less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This includes the portions at the Trojan site and at Hanford. The duration of the river transit is expected to be less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Thus the total expected time the RVP will be outside of the Trojan site and disposal facility boundaries will be less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The one-time, short duration shipment of the RVP will be made under extensive and proven procedural controis and along a well-denned, favorable transportation route to the US Ecology licensed radioactive waste disposal facility. Removal of the reactor vessel with its internals intact and transport of the RVP will facilitate completion of decommissioning and release of the site for unrestricted use, which is a positive impact on the local Trojan site environment. The RVP will be shipped to a facility that is licensed to accept and dispose oflow level radioactive waste.
The shipment of the RVP involves no irreversible or irretrievable commitments of resources and will have negligible impact on the environment. The proposed method of packaging and transport ensures the safety of the shipment and is consistent with the NRC's policy to maintain (a) radiation exposure to workers and the public as low as reasonably achievable.
2.4.1 EFFECT ON HUMAN ACTIVITIES Additional workers will be employed at Trojan during the project. The peak in number of workers is expected to occur during the time (approximately two months) that the reactor vessel is first lifted and penetration covers and shielding are welded on. Skilled craft, particularly welders, will be needed. Some of the skilled workers will come from local communities. The
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largest source of skilled craft is in the Portland, Oregon area.
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The Trojan site is in an area that has experienced construction of several large industrial facilities in addition to the construction, operation, and maintenance of Trojan. The maximum number of on-site workers during the RVP removal and disposal project is expected to be signi6cantly less than that for a normal refueling outage when the plant was operational. Most of the workers from Portland are expected to commute, due to the short term nature of the project. No signi6 cant adverse impacts are expected on temporary housing or schools as a result of the project.
The proposed method of packaging and transport ensures the safety of the shipment and the j
l public. The effect on river traffic will be minor since this activity adds only one barge shipment on a major river that routinely carries a large number of commercial barge shipments. Highway i
,,3Q traf6c near the transport route from the Port of Benton to the disposal facility will be controlled l
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p) tv while the RVP-loaded transporter transits to the disposal trench at the US Ecology disposal facility. The traffic control measures will have only a minimal, short duration impact on routine traffic flow.
2.4.2 EFFECTS ON TERRAIN, VEGETATION, AND WILDLIFE The RVP removal and package preparation will take place on previously developed areas of the Trojan site. The reactor vessel will be removed from an existing building and transported on an existing road to the barge slip. The barge slip area is in a rocky area along the Columbia River, and is adjacent to an archaeologically significant area where Indian artifacts have been found.
Any barge slip dredging will be done in accordance with permit requirements.
Since the project will utilize existing developed areas, no impact is expected to occur on the undeveloped areas. The proposed activities will not affect endangered or threatened species or critical habitat in the vicinity of the site. No changes are needed to the conclusions reached by PGE on the environmental effects of decommissioning activities in PGE-1063," Supplement to Applicant's Environmental Report"(Ref: Section 4.2), or to the conclusions reached by the NRC in the " Environmental Assessment by the U.S. Nuclear Regulatory Commission Related to the Request to Authorize Facility Decommissioning," December 1995 (Ref: Section 2.1.3).
AV Land transport of the RVP from the Port of Benton, Washington, to the US Ecology disposal facility will also take place on previously developed areas. No impact on terrain, vegetation, or wildlife is expected from this portion ofland transport.
2.4.3 EFFECTS ON ADJACENT WATERS AND AQUATIC LIFE The RVP will be transported by barge up the Columbia River to the Port of Benton. Appropriate permits from the US Army Corps of Engineers will be obtained for barge slip dredging as necessary. Required permits will also be obtained for any barge slip modification that may be required. Regarding the potential for radioactive contamination of the water, radioactive shipment regulations require that the package be free of any loose surface contamination.
Reactor vessel external surfaces will be decontaminated, as necessary, to ensure compliance with 10 CFR 71.87(i) and will be coated to fix any residual contamination. The RVP will be tied down to the transporter, and the transporter tied down to the barge. Tiedown designs will be reviewed by the appropriate authorities. The reactor vessel nozzles and other penetrations will I
have covers welded over them, thus minimizing the potential for contamination of adjacent l
waters and aquatic life. Therefore, there will be no impact on adjacent waters or aquatic life.
2.4.4 EFFECTS OF RELEASED RADIOACTIVE MATERIALS l
Radioactive gas may be removed from the reactor vessel via venting connection (s) during LDCC (Jg) filling operations. Radioactive particulate matter will be generated during certain operations of I
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Troian Reactor Vessel Package - Safety Anah sis Report - Environmental Report p
V the project such as cutting and grinding. These operations will take place inside the Containment Building. High efficiency particulate air (HEPA) filters (local and/or Containment Building purge exhaust) will be utilized as necessary. The opening in the Containment Building will be l
closed when there is a likelihood of airborne contamination. This will minimize the potential for j
an unmonitored release of gaseous radioactive material.
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l Regarding the potential for radioactive liquid effluents, the reactor vessel will be drained prior to filling with LDCC. Any radioactive liquid will be processed as required prior to disposal.
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Water is used on the diamond wire saw during concrete cutting operations. Although not expected to be contaminated, the effluent will be monitored prior to release.
The proposed method of packaging and transport ensures the safety of the shipment and precludes the release of radioactive materials during transport. Therefore, there will be no impact of released radioactive materials during transport.
2.4.5 EFFECTS OF RELEASED CHEMICAL AND SANITARY WASTES A small amount of boron may be in water drained from the reactor vessel. In addition, a A
chemical foaming agent may be used in the LDCC. Any chemical discharges resulting from the
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project will be made in accordance with the limitations and conditions of the NPDES Waste Discharge Permit.
Regarding sanitary wastes, the Trojan sewage waste treatment plant was placed in senice in 1989 and was based on operational staffing levels. The maximum number of workers on-site during the RVP removal and disposal project will be less than for a typical refueling-maintenance outage when the plant was operational. Thus, there should be no adverse impact on sanitary waste treatment and effluent discharge.
No uncontained chemical or sanitary wastes are expected to be generated during land and water transpon of the RVP.
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V 2.4.6 EFFECTS ON RADI ATION EXPOSURE TO THE PUBL1C By the time the vessel leaves the Containment Building, it will be filled with LDCC and have penetration covers and shielding installed. By the time the vessel leaves the site, it will meet the applicable radiation exposure requirements of 10 CFR 71.47 and 71.51; and 49 CFR Parts 171 and 172 (categorize hazardous materials), Part 173 (prescribe requirements for package preparation), and Parts 176 and 177 (prescribe general requirements for water and land transport, respectively).
The reactor vessel will be transported by barge to the Port of Benton. As such, the number of people in close proximity to the package will be significantly less compared to overland shipments. Detailed information on predicted exposures is provided in Section 2.5 and Table E2-1 of this environmental report. Total dose to the public is predicted to be only approximately 0.019 person-rem. Comparing this total dose to all members of the public to the 10 CFR 20.1301 limit of 0.1 rem per year to an individual member of the public from a facility such as an operating nuclear power plant, shows that the radiation exposure to the public from this project is well within acceptable standards for radiation exposure to the public.
2.4.7 CONSEQUENCES OF A NON-CREDIBLE REACTOR VESSEL CONTAINMENT
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BREACH V]
PGE evaluated the radiological consequences to the public from two non-credible accidents which result in a non-credible breach of the RVP. The following conditions were evaluated:
A.
During overland shipment, the reactor vessel package falls off the transporter, and is breached.
B.
During river shipment, the reactor vessel package falls off the barge near the intake to a water treatment plant that draws drinking water from the river, and is breached.
The evaluation, described in Section 1.1.1.4 of the SAR, concluded that calculated doses for individuals due to either non-credible breach accident are well below the doses used to establish the Type A transportation package limits (5,000 mrem TEDE,50,000 mrem TODE, and 15,000 l
mrem eye dose equivalent).
Type A package limits are also used for several other purposes in the regulations, such as specifying Type B activity leakage limits, LSA, and excepted package content limits. In establishing the Type A limits, the regulations assume that a person is unlikely to remain at a distance of I meter from the damaged package for more than 30 minutes.
As required by the SAR, PGE Radiation Protection personnel will accompany the RVP O
id shipment, and therefore, will be available to establish boundaries and perform emergency E-7 August 8,1998
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response functions. In addition, traffic escorts will control / restrict road traffic in the vicinity of the transporter during the overland transport. As a result, the evaluation for the overland shipment accident assumed exposure conditions for an individual standing 100 meters from the scene of the accident for 30 minutes. The evaluation determined the external exposure (DDE) to an individual is approximately 25 mrem and the intemal (CEDE) is approximately 12 mrem.
The evaluation for the river shipment accident determined that the external exposure (DDE) to an individual is 0 mrem and the internal exposure (CEDE) is approximately 1.25 mrem.
Therefore, it is concluded that the above non-credible accidents will not result in a significant radiological consequence to the public, and do not significantly affect the public health and safety.
2.5 ALTERNATIVE TO THE PROPOSED ACTION The proposed action and three altematives were considered for the disposal of the reactor vessel and intemals from the Trojan Nuclear Plant:
A.
Reactor Vessel and Internals Removal (Proposed Action) p)
t One niece disnosal of the reactor vessel with its internals intact. The RVP will be transported via barge and land transporter to the US Ecology disposal facility near Richland, Washington. This scenario is the preferred method based on radiation exposures to the general public and workers, and based on schedule and cost.
B.
No Action Storage of the reactor vessel on site. On-site storage of the reactor vessel with its internals intact is not considered to be a viable alternative since federal regulations (10 CFR 50.82(b)(1)(i)) require decommissioning within 60 years. Storing the vessel on-site for 50 years prior to removal is similar to the SAFSTOR decommissioning alternative, which was addressed in NUREG-0586," Final Generic Emironmental Impact Statement on Decommissioning of Nuclear Facilities." On-site storage for 50 years is not consistent with the DECON decommissioning alternative that was selected by PGE and approved by the NRC. The DECON decommissioning alternative has also been accepted and approved by the State of Oregon for the decommissioning of the Trojan Nuclear Plant.
i On-site storage of the reactor vessel would result in retaining the 10 CFR 50 license and l
necessary staff to maintain radiological controls and other 10 JFR 50 required programs.
Other results include, but are not limited to, performance of required periodic surveys, increased exposure to workers, and increased cost. It should be noted that low level radioactive waste disposal costs tend to increase at a rate greater than that ofinflation.
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Although radioactive decay would reduce shielding requirements, the reactor vessel I
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I would still have to be disposed using one of the alternatives described below. Since insignificant gain would be realized, this scenario was not further evaluated.
I C.
Modified Reactor Vessel and Internals Removal (Modified RVAIR) l Disposal of the reactor vessel in one niece with only the non-creater than Class C (non-GTCC)intemals left inside. The GTCC internals will have to be segmented underwater, placed into containers, and stored in the spent fuel pool or the Independent Spent Fuct Storage Installation (ISFSI) at the Trojan site. The vessel and non-GTCC internals will be shipped via barge in a single package, similar to the RVAIR alternative. The GTCC internals will be shipped at an unknown date in the future when a high-level waste repository becomes available to accept the waste.
D.
Separate Disposal Separate disposal of the reactor vessel and intemals. The reactor vessel internals will be segmented under water. The non-GTCC internals will be placed in shielded casks and shipped to the US Ecology disposal facility via truck. The GTCC internals will be stored in the spent fuel pool or the ISFSI at the Trojan site. The reactor vessel will be disposed n
of separately from the internals and either shipped whole via barge, or segmented and
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shipped via truck to the disposal facility. The GTCC internals will be shipped at an unknown date in the future when a high-level waste repository becomes available to accept the waste.
Radiation exposures, number of radioactive waste shipments, cost, and schedule were analyzed.
These categories are described below and summarized in Table E2-1 in a comparative form.
2.5.1 RADIATION EXPOSURE (ALARA)
I Radiation exposure for the proposed action and alternatives was analyzed for the categories listed i
below. Dose estimates do not include doses resulting from on-site storage and future shipment l
of GTCC waste to a high-level waste repository (date and site unknown).
I Occupational - exposure to workers completing the various work activities at the a.
Trojan site, j
f b.
Transportation Occupational! - exposure to the drivers, inspectors, barge j
personnel, etc., related to the transportation of the radioactive waste shipments.
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General Public - exposure to the general public based on the distance to the site, I
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population dose factors, and the number of shipments.
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d.
On-looker - exposure to members of the general public when the package is not in transport. For truck shipments, this is when the truck driver stops for food, fuel, j
or inspections. For barge shipments, this is when the barge is in the locks.
Disposal Facility Occupational - exposure to workers who dispose the packages at e.
the disposal facility.
2.5.2 NUMBER OF RADIOACTIVE WASTE SHIPMENTS I
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The number of radioactive waste shipments was based on the amount and configuration of the l
waste produced.
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1 Radioactive waste shipments include two future shipments for GTCC waste for the Modified RVAIR and the Separate Disposal alternatives. Not included are shipments of Dry Active Waste j
(DAW), or cavity cleanup waste (e.g., filters). For the RVAIR proposal,1 DAW shipment is l
estimated. For the Modified RVAIR alternative,2 DAW shipments and 1 filter shipment are
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estimated. For the Separate Disposal alternative,5 DAW shipments and 2 filter shipments are J
estimated.
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2.5.3 SCHEDULE The estimated schedules for the proposed action and alternatives are based on a final determination of the selected project by approximately the fourth quarter of 1998. In addition, the schedules are based on a limited period for water transport due to Columbia River level constraints on barge facilities.
The RVAIR proposal is currently scheduled for completion in the third quarter of 1999.
The Modified RVAIR alternative would complete in the third quaner of 2000 based on the scope of work necessary to segment portions of the internals, package and remove the reactor vessel and the remaining internals, and ship the package for disposal.
4 The Separate Disposal alternative would complete in the third quarter of 2001 based on the scope of work necessary to segment all of the internals, package and remove the internals, and ship the reactor vessel.
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Troian Reactor l'essel Package - Safety Analysis Report - Environmental Report p,g 2.5.4 TOTAL COST--
The RVAIR proposal is estimated to cost $23.8 Million in 1996 dollars. This cost includes the packaging, transport, and disposal of the reactor vessel and internals.
The Modified RVAIR alternative is estimated to cost $3 t7 million in 1996 dollars. This cost includes removal of the required portion of the intemals, on-site storage of the required material and eventual disposal, and the cost related to packaging, transport, and disposal of the reactor vessel and remaining portions of the internals.
The Separate Disposal attemative is estimated to cost $38.4 million in 1996 dollars. This cost includes segmentation of all of the intemals, on-site storage of the required material and eventual disposal, the cost related to packaging, transport, and disposal of the remaining portions of the i
internals, and the separate packaging and disposal costs for the reactor vessel.
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Table E2-1 Summary of Proposal and Alternatives Option RVAIR MODIFIED SEPARATE 0
Description RVAIR )
DISPOSAL 0 ). (2)
Shipment Method Barge -
Barge Truck + Barge Occupational 67.1 87.8 133.2 Exposure
- Transportation Occ.
0.092 0.092 1.060 Exposure
- General Public 0.005 0.005 0.245 Exposure
- On-looker 0.014 0.014 0.234 Exposure
- Disposal Facility 0.2 0.2 4.2 to O
Occ. Exposure
- 5.2 LJ Total Exposure
- 67.4 88.1 138.9 to 139.9 No. of Radioactive 1
3(3) 47(3)
H Waste Shipments )
Estimated Total 23.8 Million 34.7 Million 38.4 Million Cost (1996 Dollars)
Schedule Third Quarter 1999 Third Quarter 2000 Third Quarter 2001
- person-rem (1)
Dose estimates do not include doses resulting from on-site storage and future shipment of GTCC waste to a high-level waste repository (date and site unknown).
(2)
The reactor vessel is shipped whole by barge and the non-GTCC reactor vessel internals are segmented and shipped by truck.
(3)
Radioactive waste shipments include two future shipments for GTCC waste.
(4)
Not included are shipments of dry active waste (DAW), or cavity cleanup waste (e.g., filters). For the RVAIR proposal,1 DAW shipment is estimated. For the Modified RVAIR alternative,2 DAW shipments and 1 filter shipment are estimated. For the Separate Disposal alternative,5 DAW shipments and 2 filter shipments are estimated.
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2.6 ALTERNATIVE USE OF RESOURCES Thi, removal of the Trojan reactor vessel and the internals is necessary for completion of decommissioning and release of the site for unrestricted use. If the reactor vessel and the internals are not removed, it effectively results in storing radioactive waste at the Trojan site and precludes the release of the site for unrestricted use.
2.7
SUMMARY
AND JUSTIFICATION OF EXEMPTIONS Full compliance with the regulations of 10 CFR 71 and 49 CFR 173 is imprac ical for the proposed shipment of the Trojan RVP. Full compliance with drop-height test requirements would significantly increase the size and cost ofimpact limiters attached to the reactor vessel.
Larger impact limiters would raise the center of gravity of the RVP in its transport configuration resulting in a larger actual drop height that could occur during the shipment. Larger impact limiters could also make the shipment by barge physically impossible since a slightly taller package would not fit under the minimum overhead clearance point for the shipment route.
Furthermore, installation oflarger impact limiters would result in an increase in occupational dose to the workers performing the installation, which is not in keeping with the As Low As Reasonably Achievable (ALARA) concept. The RVP design meets the intent of the regulations N
to ensure that a drop of the package during shipment will not result in unacceptable consequences to workers, the public, or the environment. In summary, the RVP design provides an equivalent, if not improved, level of safety by a simpler and more cost-effective and dose-effective means.
2.7.1 NRC EXEMPTIONS The exemptions requested of the NRC are from two requirements specified in 10 CFR 71:
A.
Normal Conditions of Transport (NCT): 10 CFR 71.71(c)(7) requires a drop of the i
specimen through a distance of 1 foot onto a flat, 3sentially unyielding, horizontal surface, striking the surface in a position for which maximum damage is expected.
B.
Hypothetical Accident Conditions (HAC): 10 CFR 71.73(c)(1) requires a drop of the i
specimen through a distance of 30 feet onto a flat, essentially unyielding, honzontal surface, striking the surface in a position for which maximum damage is expected.
The exemption from 10 CFR 71.71(c)(7) is fully described and justified in Sections 1.1.1.1 and 2.6.7 of the SAR. Based on the conditions and the special handling and operational controls to be exercised, the one foot drop should not be considered a normal condition of transport.
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l However, PGE has desige.d and analyzed the RVP with impact limiters to withstand the effects of a one foot horizontal drop and one foot oblique pivot drops.
The exemption from 10 CFR 71.73(c)(1) is fully described and justified in Sections 1.1.1.2 and 2.7.1 of the SAR. Based on the transportation evaluation and the operational controls and specific considerations, the hypothetical accident condition of a 30-foot drop should nei Se considered a condition of transport of the RVP. However, based on the specific transportation route and controls established, a maximum non-mechanistic drop configuration has been determined. The maximum postulated distance that the RVP could drop, based on the transportation system and route, during a hypothetical transport accidc at is 11 feet. This drop height and horizontal orientation was used as a design basis for the RVP.
Based on the justification provided, it is concluded in accordance with 10 CFR 71.8 that the proposed packaging and shipment will not endanger life or property, not the common defense and security. Furthermore, as stated in Section 2.4 of this report, this shipment will have negligible impact on the environment, and the proposed method of packaging and transport ensures the safety of the shipment and is consistent with the NRC's policy to maintain radiation exposure to workers and the public ALARA.
C's 2.7.2 DOT RELATED EXEMPTIONS V
The RVP is classified as a highway route controlled quantity of normal form Class 7 radioactive material, n.o.s. (not otherwise specified), to be shipped under exclusive use provisions. The total quantity of radioactivity in the RVP is approximately 2 million curies, primarily of activated metal, which exceeds the A value of 49 CFR 173.433 for the mixture of radionuclides. For the 2
RVP classification and quantity of radioactivity, the following Title 49 regulations lead in series to the conclusion that the appropriate shipping package for the RVP is a Type B package that meets the applicable requirements of 10 CFR 71 and that has been approved by the NRC:
i A.
49 CFR 173.24(c)(1) states in part," Authorized packagings. A packaging is authorized i
for a hazardous material only if--The packaging is prescribed or permitted for the hazardous material in a packaging section specified for that material in Column 8 of the (172.101 [ Hazardous Materials] Table.. "
B.
49 CFR 172.101 Hazardous Materials Table Column 8 specifies {l73.416 as the applicable section for packaging of" Radioactive material, n.o.s."
C.
49 CFR 173.416(a) states,"Each of the following packages is authorized for shipment of quantities exceeding A or A, as appropriate: Any Type B.. packaging that meets the i
2
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Troian Reactor Vessel Package - Saferv Analysis Report - Environmental Report i
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applicable requirements of 10 CFR Part 71 and that has been approved by the U.S.
Nuclear Regulatory Commission may be shipped.. "
In addition to 49 CFR 173.416(a), there are two other applicable Title 49 regulations that rely on the radioactive material transportation package being certified by the NRC as a standard Type B package. 49 CFR 173.403 states," Type B package' means a Type B packaging that, together with its radioactive contents, is designed to retain the integrity of containment and shielding required by this part when subjected to the normal conditions of transport and hypothetical accident test conditions set forth in 10 CFR Part 71." 49 CFR 173.467 states,"Each Type B packaging... must meet the test requirements prescribed in 10 CFR Part 71 for ability to withstand accident conditions in transportation."
Since the NRC has indicated that their approval of PGE's tequest for the one-time shipment of the RVP per 10 CFR 71 will not include issuance of a C of C for the RVP as a Type B radioactive material transportation package PGE seeks relief specifically from Regulations 49 CFR 173.416(a),173.403, and 173.467. The non specification package is otherwise being assembled and controlled as a Type B package (as exempted by the NRC), except that it will not be marked " TYPE B," since that is specifically prohibited by 49 CFR 172.310 for a package that does not conform to Type B requirements.
n
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The information provided in the RVP SAR meets the requirements forjustification of the exemption proposal, as set forth in 49 CFR 107.105. It demonstrates that the exemption achieves a level of safety at least equal to that required by regulation and is consistent with the public interest.
Information describing relevant shipping and incident experience that relates to this application is provided in Sections 1.1.1.1 and 1.1.1.2 and Appendices 1-1,1-2, and 1-3 of the RVP SAR.
Also provided in those references is substantiation by industry experts that the favorable, relatively short transportation route and the extensive transportation controls that are being placed on this one-time shipment demonstrate an equivalent, if not improved, level of safety for the proposed land and river transport scenarios. The transportation controls are discussed in Chapter 7 of the SAR. Furthermore,it is shown in the exemption requests from 10 CFR 71 discussed above that it is impractical to meet th: requirements from which exemption is requested due to considerations of the package, the transportation route, t a the transportation controls.
2.8 REGULATORY GUIDE 7.12 ALTERNATIVE The RVP brittle fracture evaluation methodology is fully described and justified in Sections 1.1.1.3 and 2.1.2.3, and Appendix 2-12 of the RVP SAR. This information provides the basis n()
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v from which the NRC can conclude that the alternative method of evaluating fracture toughness of the RVP is acceptable.
2.9 STATUS OF COMPLI ANCE Federal permits and approvals that must be obtained in connection with transporting the RVP for disposal at US Ecology's low level waste disposal facility and their status are as follows:
A.
Approval from the NRC in accordance with 10 CFR 71 for the one time shipment of the RVP as a radioactive material transportation package, including approval of an exemption from drop test requirements of 10 CFR 71.71(c)(7) and 71.73(c)(1).
STATUS: Application was made by PGE on March 31,1997. The NRC issued a first Request for Additional Infonnation (RAI) on May 19,1997. A response to the first RAI was made by PGE on June 18,1997. The NRC issued a second RAI on July 9,1998. A response to the second RAI is being made by PGE, including this Environmental Report.
Approval from the NRC is currently anticipated to occur in the fall of 1998.
B.
Approval from the DOT of an exemption from 49 CFR 173.403,173.416(a) and 173.467, (3
with respect to those regulations relying on the RVP being certified by the NRC as a
(,/
standard Type B package.
STATUS: Application by PGE for the exemption is expected to occur in August 1998, to allow the DOT to complete their review and noticing in parallel with gaining approval by l
the NRC. Approval from the DOT is anticipated to occur within approximately one week of them being provided evidence of the NRC's approval.
C.
Hazardous Material Certificate of Registration from the DOT.
STATUS: Current 1
D.
Load Line Certificate for the barge from the American Bureau of Shipping, acting as an agent of the U.S. Coast Guard.
STATUS: Will be issued upon request.
E.
Certificate ofInspection for the barge from the U.S. Coast Guard.
STATUS: Complete.
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E-16 August 8,1998 5
i Trojan Reactor l'essel Package - Safety Analysis Report - Environmental Report O(h l
F.
Certificate of Documentation for the barge from the U.S. Coast Guard.
STATUS: Complete.
l G.
Approval of stability for the barge from the U.S. Coast Guard.
STATUS: Complete.
l H.
Certificate of Loading for the barge from the National Cargo Bureau, Inc. (NCB),
functioning as an agent of the U.S. Coast Guard.
STATUS: NCB completed a review of the Barge Tiedown Structural and Barge Stability Analyses, Revision 1, dated June 25,1998. They have identified to PGE the remaining inspections that will be required before the Certificate of Loading is issued. Since some of these inspections are to be performed after the RVP is secured to the barge and the barge is afloat, issuance of the Certificate of Loading by the NCB is anticipated to occur between the first of July and the end of October 1999.
The only identified applicable environmental quality requirements associated with transporting the RVP for disposal at US Ecology's low level waste disposal facility, other than those with which tug boats and prime movers routinely deal, are land use regulations associated with disposal of the RVP. It is required that the State of Washington Department of Health (WDOH) determine that the RVP is suitable for disposal under the State's regulations. In that regard, US Ecology provided to WDOH a Radiological Dose Pathways Analysis for disposal of the RVP.
WDOH is completing a review of the analysis. It is expected that WDOH will inform US Ecology that the RVP is suitable for disposal at US Ecology's facility before the NRC approves the one time shipment of the RVP for disposal.
l 3.0 RECOVERY PLAN FOR THE TROJAN RVP OVERBOARD AND LAND TRANSPORT DROP SCENARIOS The probability of a significant accident during water and land transport has been evaluated and is included in the RVP SAR as Appendices 1-1 and 1-2. The results of the evaluation determined the probability of an accident that would require some sort of recovery operation is extremely minimal. The discrete probabilities of the significant accidents evaluated on both the Columbia River and overland are:
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Troian Reactor Vessel Package - Saferv Analysis Report - Environmental Report pV Table E3-1 Probabilities of Significant Transport Accidents Event Discrete Probability i
Impact of the RVP on the Barge 3.2E-07 Separation of the RVP/ Barge 1.0E-06 Severe Fire / Explosion 6.0E-10
(:uring barging)
Land Transport Accident 1.3E-07 As noted in the RVP river transit study (Appendix l-1 of the RVP SAR), because of the unique nature of the RVP shipment and the importance of safety in all aspects ofits planning, the -
accident rates determined from historical records (and utilized in the study) will tend to overstate l
the accident probabilities for the RVP river shipment.
p Nevertheless, in the unlikely event that such an accident were to occur, a contingency plan has been developed to recover the RVP and is included as Appendix E-1 to this environmental report. Possible scenarios include foundering (sinking) of the barge, capsize, or failure of sea fastenings (tiedowns) during a collision. The contingency plan identifies technically feasible salvage methods, available equipment, and potential methodologies for recovering the submerged RVP.
The initial activity will be to complete an assessment of the barge and/or package based on the accident. This assessment will include a determination of the amount of damage to the components and determination of the best alternatives for recovery and repair.
3.1 WATER TRANSPORT l
l 3.1.1 DEEP WATER RECOVERY
)
i Deep water immersion of the entire RVP, cradle, and barge is not considered to be a credible accident event. However, if this were to occur, the assembly would almost certainly be capsized, with the barge resting on top of the cradle and RVP, due to air trapped in the barge. In this unlikely event, the preferred recovery method would be to separate the components, salvaging first the barge, then the cradle, and then the RVP. There are a variety of salvage methods for the E-18 August 8,1998
i Troian Reactc.r Vessel Package - Saferv Analysis Report - Environmental Report L
V barge, because even in a damaged condition, air can be bubbled into compartments in the hull for flotation. The RVP and cradle do not contain enclosed permeable spaces and must be lifted. The most likely procedure would be to rig the package for a submerged lift, lift it nearly to the surface, and move it to the nearest suitable shallow water location for further preparation and repair.
The recovery of the RVP to shallow water can be accomplished by a variety of strategies. The most conventional method would be to mobilize several large derrick barges with sufficient combined lifting capacity. Several suitable west coast derrick barger and two salvage vessels have been identified by PGE's naval architect. If sufficient derrick capacity is not readily available, portable lifting gear can be rigged to a conventional barge, and the RVP lifted directly under the barge. Since the load is centered, this can be accomplished using a relatively small barge. The RVP can then be moved to the nearest suitable shallow water for recovery operations.
3.1.2 SHALLOW WATER RECOVERY Potential shallow water (less than 50 feet depth) immersion cases that are considered are: the barge capsized and stabilized at a suitable site with the cradle and RVP intact, and the RVP separated from the barge, with or without the cradle attached. In the case of a capsized barge
(")
with intact package, the assembly may be righted by lifting with one or more derricks using lifting wires wrapped around the barge. Parbuckli,g is another option, where horizontal forces are exerted to right the barge using two sets of wrapped wires. Another alternative is to ground the assembly, detach the barge and cradle, and lift separately. The method chosen will depend on the circumstances encountered, such as the degree of damage and the availability of equipment.
In the case of the RVP separated from the barge, with or without the cradle attached, the barge, cradle, and transporter would be salvaged, shipped to the appropriate shipyard. vendor, or owner for refurbishment or repair, as necessary, and returned to the incident site. The RVP would be lifted in air using cranes and lowered onto the cradle on the repaired barge. The vessel would be inspected, and further repairs would be made, if necessary. The RVP would then be secured to the transporter and barged to the Port of Benton for subsequent disposal at the US Ecology disposal facility.
3.1.3 PACKAGE OVERBOARD DAMAGE Remedial action would be required if closure plates or shielding were dislodged, or if there were l
a breach in the vessel wall. In the event of dislodged closure plates, the preferred method of repair would be to use mechanical / pneumatic plugs which would be installed by a team of divers.
pV E-19 August 8.1998 i
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l Trojan Reactor l'e.;sel Package - Safety Anahsis Report - Environmental Report
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V in areas of partial detachment, a sealing compound (either epoxy or metallic) would be applied to the open area, breach, or crack.
In the event that shielding is dislodged, reattachment could be accomplished by the installation of circumferentially placed slings, which would be tensioned to hold the shielding plates against the vessel or remaining shielding. If this method were not feasible, the shielding plates could be tack welded until permanent repairs could be effected on the surface.
{
In the event of a breach in the vessel wall, steel plates would be welded over the breach and additional steel plates would be added as necessary to reduce radiation levels to within acceptable limits for continued transport. In the extreme case of a breach in the vessel wall under the shielding, an indirect approach to sealing this breach would be used. The perimeter of the j
shielding cavering the area of the breach would be seal welded to the vessel to create a boundary around the breach.
After submerged repairs are made, the RVP would be lifted in air using cranes and lowered onto the cradle on the repaired barge. The vessel would be inspected and further repairs made, if necessary. The RVP would then be secured to the transporter, and barged to the Port of Benton for subsequent disposal at the US Ecology disposal facility.
,3
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3.2 LAND TRANSPORT 3.2.1 RECOVERY A land transport accident that would require a recovery operation is extremely minimal, and based on the design basis drop for the package, subsequent damage is not expected. However,in the event it did occur, the initial activity will be to complete an assessment of the transporter and/or package based on the accident. This assessment will include a determination of the amount of damage to the components and determination of the best alternatives for recovery and repair. A bounding estimate for the potential radiation exposure was completed for the type of potential actions necessary. The extent of damage and methods of repair were assumed to be similar to the water recovery scenario. Mobile cranes of sufficient capacity will be assembled at the accident site. First, the transporter and cradle will be recovered and repaired. The vessel will then be repaired, lifted onto the cradle on the transporter, and secured to the transporter. Final repairs will be effected, as necessary, and the package will be transported to the US Ecology disposal facility.
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Troian Reactor Vessel Package - Saferv Analysis Report - Environmental Report AU 3.2.2 PACKAGE DAMAGE l
A similar number G man-hours estimated for water repairs are assumed to effect land repairs. In the event of a breach in the vessel wall, steel plates would be welded over the breach and l
I additional steel plates would be added as necessary to reduce radiation levels to within acceptable limits for continued transport. In the extreme case of a breach in the vessel wall under the shielding, an indirect approach to sealing this breach would be used. The perimeter of the shielding covering the area of the breach would be seal welded to the vessel to create a boundary around the breach.
i i
After repairs are made, the RVP would be lifted in air using cranes and lowered onto the cradle on the repaired transporter. The vessel would be inspected and further repairs made, if necessary.
The RVP would then be secured to the transponer and transported to the US Ecology disposal facility.
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l Appendix E-1 l
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PORTLAND i
GENERAL ELECTRIC COMPANY Jon No. RVA1Q-h/At_/JoA-240 Leger No. Q d Ai d2
- AMa-GR L.
CONTINGENCY PLAN
~~= =c="a-1XFnal Sutettal.
7 d Work may progned. Sutml findi document s a a
.~-~. ~ ~
FOR PACKAGE RECOVERY suo,eci 4 0 Pevtse and resutmt Work rney not proceed 5 o Kevow not required. Work rney proceed.
6 o Other Permission to proceed does not consutute acceptance or approval of design details, calculations, analysee, test methods, or meteriale developed or selected by the supplier and does not relieve eu,$ler from full compliance with contractual obligations.
oINFORMA90N ONLY,
'"ad *W* #^
Portland General Electric Company 7I'#I n Rainier, Oregon o*
concurretTy D ib
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P
'692 (Jul 80)
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/ONAL N I
EXP!RES _3/25A2P j
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~ hn A. Springer lil, P.E.
'J. Thomas Bringloe, P.E.
Jo Principal-in-Charge Project Manager j
File No. 9656 14 August 1997 Rev. A,18 May 1998 O
f>$
Consulting Engineers Serving The Marine Community 600 Mutual Life Building a 605 First Avenue
'A seattle Washington 98104 2224 The Glosten Associates, incorporated Phone: (206) 624 7850
- Fax (206) 682-9117 IL________.________________
TABLE OF CONTENTS
\\
Contingency Plan for Package Recovery
- 1. OBJECTIVE.
...1
- 2. SCOPE
. 1
- 3. LIrrING REQUIREMENTS 2
1
- 4. DEEP WATER SALVAGE CASES.
.~
2
- 5. SHALLOW WATER SALVAGE CASES
. 5 l
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- 6. NAVIGATION CLEARANCES
.. 7
- 7. MARINE SALVAGE EQUIPMENT AND CONTRACTORS.
. 7
- 8. EXAMPLE RESPONSE.
.... 9 i
f RE FERENCE
....-............. 12 t
APPENDIX A-NAVIGATIONAL CLEARANCES ON THE COLUMBIA RIVER l
APPENDIX B -SOME HEAVY LIFT AM) SALVAGE ASSETS AVAILABLE l
ON THE U.S. WEST COAST s
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liv PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan i
File No. 9656,18 May 1998 Rev.A J.\\WP\\9666\\ REPORTS \\SALVGLDOC
CONTINGENCY PLAN FOR PACKAGE RECOVERY 1.
Objective The Trojan Nuclear Power Plant reactor vessel package (RVP) is to be transported by barge from the plant location near Rainier, Oregon, to the Port of Benton, Washington. The objectives of this report are to present technical strategies for recovering the RVP in the event of accidental immersion, and to identify commercial resources and equipment for recovery.
A previous probabilistic safety study (Ref.1) determined the probability of various accidents during RVP transportation by barge on the Columbia River, resulting in package immersion. The results are summarized in Table 1.
Table 1 Probability for Accident in RVP Tran6 port by Barge on the Columbia River Probability of Type of Accident Submergence Collision, Ramming or Foundering Effectively Zero Capsize Effectively Zero 4
RVP Seafastenings Failin Collision 1.0 x 10 4
TOTAL 1.0 x 10 l
4 A probability level of 1.0 x 10 is considered to be below the defined threshold of a credible accident. Nevertheless, this report will address the technical aspects of recovery in the event of any of the three accident scenarios above: foundering, capsize and failed sea fastenings.
i j
2.
Scope l
The scope of this investigation is to identify technically feasible salvage methods and j
available equipment for recovering the submerged RVP.
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i PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan 1
File No. 9656,18 May 1998 Rev.A 4
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3.
Lifting Requirements OV Table 2 gives weights, in air and in water, of the principal components; this is for guidance in judging equipment requirements. There are a variety of salvage methods for the barge because, even in a damaged condition, air can be bubbled into compartments in the hull for floatation. The RVP and cradle, on the other hand, do not contain enclosed permeable spaces, and must be lifted.
i M
Weights, in Air & Water, of RVP and its Components l
Component Weight in Air, s. tons Weight in Water, s. tons i
i j
RVP 1020 642 i
Shipping cradle &
270 235 support platform Trailer 269 234 f
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Subtotal 1559 1111 i
Barge w/ Bolsters 831 723 O
TOTAL 2390 1834 4.
Deep Water Salvage Cases The deepest point in the Columbia River between the Trojan Nuclear Power Plant site and the Port of Benton is approximately 191 feet (at normal pool elevation) at mile 219.5, located in Lake Umatilla above the John Day Dam (Ref.1).
For purposes of this discussion, we will consider deep water to be in excess of 50 feet.
This is an approximate threshold beyond which the productivity of diver activity diminishes and the cost increases. Also, another PGE contractor has demonstrated the integrity of the RVP when submerged to a depth of 50 feet in accordance with the provisions of 10 CFR 71.73(c)(5). The analysis of a hypothetical capsize using a hydrostatic computer program (GHS) has shown that when the RVP is constrained to remain with the floating capsized barge, in accordance with ANSI N14.24, the depth of RVP submergence is less than 50 feet.
The river route from the Trojan Plant to the Port of Benton contains water exceeding 50 depth in the deepest part of the main channel over 56% of the route. However, these deeper areas are mainly in the lightly traveled pools above the upper river dams. There are only a few isolated deep water areas between the Trojan Plant and Bonneville Dam.
O PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan 2
File No. 9656,18 May 1998 Rev.A J.\\%~/\\9656\\REPO5JI$\\$ALVGX. DOC
{
The most likely procedure for dealing with a deep water immersion incident would be o
to rig the package for the submerged lift weight of 642 tons, lift it nearly to the h
surface, and move it to the nearest suitable shallow water location for further preparations. Considerations for the suitability of this intermediate site would include:
Bottom conditions (slope and soil type)
Avoiding interference to navigation Avoiding strong currents and high wave conditions e
Logistics and access to site e
i Controlling security and public access to site i
e Potential work sites are identified in Table 3, together with a general summary of regional water depths. Portion of the route with little or no areas of water depth exceeding 50 feet are noted. Casualties in these areas are not considered to be deep water events. In water depth ofless than about 40 feet, the cargo would ground upon capsizing, and the casualty would have to be dealt with at the incident site.
Table 3 Summary of Water Depths and Potential Work Sites River Mlle Location Condition 72 to 105 Trojan to Vancouver Nav depth 40', depth generally
<50' except:
O mi. 72 to 79'(Cable area) mi. 74 to 65' mi. 78 to 66' mi. 80 to 69" mi. 84 to 59' mi. 87 to 73' mi. 93 to 59' mi.101 to 68' 101 Willamette River, Port of Various potential work areas, Portland shipyards 105 to 145 Vancouver to Bonneville Project depth 15', depth generally <50" except:
mi.140 to 83' 116 Fisher Quarry Dock Moorage, shoreside access i
120 off Lady Is. Range 50'+ work area 120 Sundial Marine Shipyard w/drydock 130.5 off Cape Horn Channel 50'+ work area j
O PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
File No. 9656,18 May 1998 Recovery Contingency Plan 3
Rev.A J:\\WP\\9666\\ REPORTS \\SALVGX. DOC i
River Mile Location Condition l
145 to 175 Bonneville to Hood River Generally 50' to 120' depth l
147 Upper Bonneville fleeting Potential work area l
dolphins 149 Cascade Locks Old lock, shoreside access 170 to 192 Hood River to The Dalles Generally <50' water depth except:
mi.171 to 120' mi.177 to 57' mi.181 to 101' mi.179 to 102' mi.181 to 101' mi.184 to 101' mi.187 to 178' mi.188 to 143' 170 Hood River Nichols shipyard 170.5 Bingen lumber yard, shoreside access 174 Eighteenmile Is.
Possible protected work area 189 Dallesport wharf Possible work area 189.5 Aluminum plant wharf Possible work area 192 to 217 The Dalles to John Day.
Generally >50' depth, with (Lake Celilo) weather exposure and limited i
access.
193 Klickitat Port Dock Possible work area 199 Avery Possible work area
~
21i~to 293 John Day to McNary.
Generally >50' depth to mi. 284 (Lake Umatilla) 243 Arlington Grain Elevator Possible protected work site 245 Roosevelt Grain Elevator Possible protected work site 269 Port of Boardman Possible work site subject to weather exposure.
279 Grain elevator Possible work site O
PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
File No. 9656,18 May 1998 Recovery Contingency Plan 4
4 Rev.A J:\\WP\\9666\\ REPORTS \\SALVGX. DOC
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l River Mlle Location Condition 280 Dock Old dock (Irrigon), possible work site I
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293 Umatilla Port Dock Crane, Dock j
293 to 329 McNary Dam to Pasco Generally >50' depth (Lake Wallula)
]
l 299 Hat Rock State Park Possible work site 312 Port Kelly Possible work site 328 Port of Pasco Port Docks, Lampson facilities.
)
329 to 343 Pasco to Port of Benton Generally <50' depth Deep water immersion of the entire RVP, cradle and barge is not considered to be a credible accident event (Ref.1). But if this were to happen, the assembly would l
almost certainly be capsized, with the barge resting on top of the cradle and RVP, due to air trapped in the barge. In this unlikely event, the preferred procedure would be
~N(d to separate the components, salvaging first the barge, then the cradle and then the RVP.
Recovery of the RVP to shallow water can be accomplished by a variety of strategies.
The most conventional method would be to mobilize several large derrick barges with sufficient combined lifting capacity. If derrick capacity is not readily available, portable lifting gear can be rigged to a conventional barge, and the RVP lifted directly under the barge.
Since the load is centered, this can be accomplished with a relatively small barge. Examples of portable lifting equipment which may be used include hydraulic strand jacks, hydraulic linear winches (wire pullers) and winches with multiple part blocks.
Hydraulic devices have the advantage of allowing equalization ofloads, and measurement ofloads, on multiple lift lines.
Once_thet RVP is relocated to shallow water, the recovery can proceed as described in the following section.
5.
Shallow Water Salvage Cases Potential shallow water (less than 50 feet depth) immersion c65es include:
Barge capsized and stabilized at suitable site with cradle and RVP intact.
RVP separated from barge, with or without cradle attached, in less than 50 feet water depth.
OV l
PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan 5
File No. 9656,18 May 1998 Rev.A J:\\WP\\9866\\ REPORTS \\SALVGX. doc
In the case of the capsized barge with intact packsge, the assembly may be righted by
,q lifting with one or more derricks, or by parbuckling. Alternatively, the assembly may V
be grounded and the barge and the cradle detached and lifted separately. The method chosen will depend on circumstances, such as the degree of damage to the barge and fastenings, and availability of equipment.
When righting by lifting with derricks, lifting wires are wrapped a full turn around the barge and package in such a way as to maximize moment arm throughout the operation. The amount oflifting force required can by controlled to some extent by ballasting. In this case, the lift force required is approximately 1265 tons, although this may vary depending on the condition of the barge. This operation is illustrated in Figure 1.
Crane Lift Force h
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j Figure 1 - Righting by Lifting with Derricks O
PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
l Recovery Contingency Plan 6
File No. 9656,18 May 1998 Rev.A J:\\WP\\9656\\ REPORTS \\SALVGX. DOC
The parbuckling operation is similar, except that horizontal forces are exerted by two sets of wrapped wires. The required parbuckling force in this case is approximately m
540 tons, although this may vary depending on the condition of the barge. This operation is illustrated in Figure 2. Salvage vessels, designed to pull stranded ships off beache's 'can be used to perform this task.
Parbuckling Force /
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Figure 2 - Righting by Parbuckling 6.
Navigation Clearances It may be necessary to use a combination of equipment such as multiple derrick barges, not only because of availability, but because of limited navigational clearances on the Columbia River. A summary of navigational clearances is given in Appendix A. The largest derrick barges available in the area, with capacities in the range of 400 to 500 tons, are too wide to pass through the locks, and cannot be used above Bonneville.
7.
Marine Salvage Equipment and Contractors The following marine salvage and heavy lift contractors were contacted regarding j
this investigation:
Crowley Marine Salvage, Seattle Salvage vessel American Salvor, diving, rigging Attn: Capt. Richard Roth Seattle, WA 206-340-2904 PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
l Recoven Contingency Plan 7
File No. 9656,18 May 1998 Rev.A JAWP\\9656\\ REPORTS \\SALVGX. DOC
Fred Divine Diving and Salvage, Portland Salvage vessel Salvage Chief, diving, rigging (m")
Attn: Capt. Mickey Lites e
503-283-5825 General Construction Company, Seattle Derrick barges, diving, rigging Attn: Tom Anderson 206-368-6300 Niel F. Lampson, Inc., Kennewick Large cranes available for mounting on barges, rigging Attn: Bruce Tolley 509-586-0411 Manson Construction and Engineering Company, Seattle Derrick barges, diving, rigging Attn: Glen Edwards 206 762-0850 The marine transport contractor, Foss Maritime, has local knowledge and familiarity l
with regional resources, and could marshal equipment and personnel under their contract, at least during the initial days of the response. Appendix B contains brochure material describing some of the significant marine heavy lift and salvage assets available on the U.S. West Coast.
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An experienced marine salvage expert should be retained to lead the recovery effort under the direction of PGE and the USCG assigned On-Scene Commander. Two j
candidates with extensive experience and knowledge of West Coast assets are:
Capt. Mickey Lites 1
Fred Divine Diving and Salvage Portland, OR 503-283-5825 Capt. Lites has a wealth of salvage experience, most notably as Salvage Master on the Exxon Valdez incident.
. Gary Root Techh'ical Salvage Advisors,'Inc.
San Francisco, CA 415-362-8502 Emergency phone 1-800-365-5982 Formerly with Crowley Marine Services, Gary Root is a naval architect with extensive salvage and special project experience. His company specializes in developing salvage preplanning for fleet owners, and on-scene response with state-of-the-art communication resources.
O PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
File No. 9656,18 May 1998 Recovery Contingency Plan 8
Rev.A J \\WP\\9656\\ REPORTS \\SALVGX. DOC
I l
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8.
Example Response l
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Using the package characteristics given in Section 3 and the equipment capabilities presented. in Appendix B, the following outline describes a feasible response to a package immersion accident.
Mobilize a salvage vessel (Salvage Chief or American Salvor) to the incident scene to provide logistical support, diving support, hyperbaric chamber and initial rigging support.
Mobilize four floating cranes with sufficient combined lifting capacity.
For e
example, Manson cranes Wotan (o00 tons), Haakon (400 tons), Manson 24 (300 tons) and Valkyrie (230 tons) have a combined capacity of 1530 ton versus package l
weight in air of 1020 tons. Note that Wotan is not capable of passage through the Columbia. River locks, and Manson 24 may have to be stripped of tires and i
fenders. Above The Dalles Bridge, river mile 191, disassembly of one or more crane gantries will be required to clear under vertical obstructions.
l 1
Fabricate or modify existing spreader bars to distribute package weight according e
to crane capability, and deliver to site.
Salvage barge if necessary and send to shipyard for repairs. Redeliver to incident site.
Salvage shipping cradle separately and ship by chartered deck barge to a l
e fabricator for repairs. Redeliver to site on repaired transport barge, Salvage transport trailer and ship to owner for refurbishment.
Redeliver e
refurbished or replacement trailer to discharge port, Port of Benton or Trojan i
Plant.
l Rig RVP for lift. Position and moor floating cranes and rig spreader bars. Lift package clear of water. Position repaired transport barge with cradle under package and moor securely with winch wires from floating cranes. Lower package l
- onto cradle and secure as original. In the deep water case, this would proceed in l
two phases, one submerged lift and one in air lift, and the mobilization of crane assets could be staged accordingly.
ITelfver RVP to Port of Benton or Trojan Plant for unloading.
Demobilize.
l A sample schedule for such an operation is shown in Figure 3. It is assumed that l
fast-track contracting authority is available, allowing fixed daily rate or time and l
l materials contracts to be placed within one to two days. It is also assumed that, in j
j the initial few days after an incident, existing contractors (e.g. Foss, Lampson, i
I Glosten) could be directed to undertake initial response efforts such as reconnaissance and preliminary planning, until more specialized personnel and I
equipment are under contract.
\\
i PGE Tmjan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan 9
File No. 9656,18 May 1998 Rev.A JAWP\\9656\\ REPORTS \\SALVGEDOC
l l
l l
A cost estimate is attached as Table 4. This is based on the sample scenario given above. While some of the assumed equipment is not applicable to response above j
Bonneville, it still provides a rational basis for estimating.
l It should be noted that the current market in heavy marine construction is quite favorable, and equipment is heavily committed. This situation has been addressed in the cost estimate as an allowance for liquidated damages that might be incurred on existing projects and would have to be compensated. In reality, this money might be spent to assemble alternative lift equipment.
In conclusion, there are adequate resources available on the West Coast to accomplish the recovery of the RVP in the event of an accidental immersion.
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PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan 10 File No. 9656,18 May 1998 Rev.A J:\\WP\\9666\\ REPORTS \\SALVGLDOC l
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Table 4 RVP Recovery - ROM Cost Estimate Salvage Master 3-33 31 days x $2000
$62,000 Engineering 1-11 12 days x $4000
$48,000 Engineering 1-28 29 days 7. $800
$23,000 Salvage vessel 3-27 25 days x $25,000
$625,000 250 ton cranes (2) 4-34 31 days x 2 x $16,000
$992,000 Special equipment, allowance
$100,000 rigging 400 ton cranes (2) 13-34 22 days x 2 x $20,000
$880,000 Recon diving 2-10 9 days x $8000
$72,000 Salvage diving 12-26 15 days x 12,000
$180,000 Deck crew 1 11-27 17 days x $16,000
$272,000 Subtotal
$3,254,000 Emergency premium, rep. as liquidated dam.
30 days x $40,000
$1,200,000 25% contingency 814,000 TOTAL
$5,268,000 1 Deck crew: three 8-hr shifts x 5 men @$55/hr = $6,600 5 men @$75/hr = $9.000
~'
$15,600/dey Reference l'
1.
Probabilistic Safety Study for the Transportation of the Reactor Vessel Package (RVP) by Barge on the Columbia River from the Trojan Site to the Port of l
Benton. The Glosten Associates,Inc., 27 February 1997, File No. 9656.
O PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan 12 File No. 9656,18 May 1998 Rev.A
.f.\\WP\\9666\\ REPORTS \\SA1,VGX. DOC j
APPENDIX A O
Nevisetie i cieer ee ee ine ceiemuie niver Mile
[ Obstruction Vertical Horizontal Depth Comm.ent "
Clearance Clearance 0
40 Project depth -
entrance to mile 106 14 Astoria fixed bridge 193 feet (205 at center) 66 Longview fixed 185 feet bridge 105.5 Burlington Northern RR bridge (swing bridge) 106 27 Project depth -
mile 106 to 145 106.3 Vancouver Interstate 178 feet Bridge (lift bridge)
/7 112.5 Fixed highway bridge 136 feet h.
(144 for center 300 feet) 145 20 Project depth -
mile 145 to 191.5 145.3 Bonneville Lock &
86 feet wide Depths and overhead Dam 675 feet clearances are at long normal pool from Bonneville to The Dalles Dam 148 Bridge of the Gods 135 feet
- Ifixed bridge)
(for middle 284 feet) 170 Hood River Bridge 148 feet l
(lift bridge) 191 The Dalles fixed 100 feet (at 81 feet at main span bridge lock approach) l
(%
PGE Trojan Nuclear Plant, RVAIR Project The Glosten Associates,Inc.
Recovery Contingency Plan Appendix A, page 1 File No. 9656,18 May 1998 Rev.A J.\\WP\\9654\\ REPORTS \\SALVoX. Doc
Mile l Obstruction iVertleal Horizontal
- Depth Comment 4
(
Clearance ' Clearance 191.5 14 Project depth -
mile 191.5 to 343 191.5 The Dalles Lock &
86 feet wide Depths and overhead i
Dam 675 feet clearances are at long normal pool.
201 Railroad bridge (lift 79 feet 3
bridge) j 209 Biggs Bridge (fixed 88 feet bridge) 216 Overhead cables 93 feet Other overhead cables between here
& mouth of river are over 100 feet and not noted in this table.
216 John Day Lock &
86 feet wide Dam 675 feet I
long 291 Highway bridges 85 feet &
(fixed parallel 71 feet bridges)
. N 292.5 McNary Lock & Dam 86 feet wide (with bascule bridge) 675 feet long j
323.5 Union Pacific rail-72 feet Marked channel I
road bridge (lift (shoal spots of bridge) 14 feet) 325.5 Overhead cables 85 feet 328 Railroad bridge (lift 70 feet bridge) 328.5 Kennewick area 56 feet highway bridges (west)
(parallel fixed 49 feet bridges)
(east) 328.5 Overhead cable 54 feet 330 Highway bridge 61 feet (fixed bridge) 336 Interstate 182 fixed 73 feet parallel bridges 343 Port of Benton 1
0 PGE Trojan Nuclear Plant, RVA!R Project The Glosten Associates,Inc.
Recovery Contingency Plan Appendix A, page 2 File No. 9656,18 May 1998 Rev.A J:\\WPi9666\\ REPORTS \\SALVGX DOC
O
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APPENDIX B i
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l SOME HEAVY LIFT AND SALVAGE ASSETS AVAILABLE ON THE U.S. WEST COAST l
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{
Recovery Contingency Plan Appendix B, page 1 File No. 9656,18 May 1998
{
Rev.A J
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lc______________-____
SPECIAL PURPOSE VESSELS l
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Based in Seattle, the kehe Salvor is the
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vessel in the U.S.A.
lt is equipped to respond to any marine
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removal, raising sunken vessels, underwater repairs, and refloating grounded ships.
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RIG ENGINEER Crowley's 5,000-h.p. supply vessel Rig Engineer features a bow thruster and is l
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Flag United States Other Helicopter pad Port of Registry San Francisco, CA 35-ton crane Official Number 527 280 21-ft. workboat Call Sign WY 9778 16-ft. skiff Builder Equitable Equipment Decompression chamber Year Bullt 1970 2 Diving compressors Converted to Salvage Tacoma Boatbuilding 4 Welding machines Vessel 1980 2 Firefighting monitors Overall Dimensions 213' x 53' x 14' 6*
Salvage Crew Accommodations Registered Tonnage 949 gross; 645 net construction Steel Light Draft 10' RlG ENGINf.ER Loaded Draft 11' 11*
Flag United States Fuel Capacity 81.380 gations Port of Registry San Francisco, CA
,o Potable Water 50,000 gallons Official Number 507 468 (d
i Lube 900 gallons Call Sign WJ 8439 Main Engines 2 Caterpillar D 399 Bullder Mangone Shipyard Auxillary Engines 2 Caterpillar 3406 Year Built 1967 Propellers Twin Screw,4 blade Overall Dimensions 165' x 36' x 15' Horsepower 2,300 Registered Tonnage 190 gross; 128 net i
Reduction Gear Western Gear, Construction Steel I
ratio 4.54:1 Light Draft 10' l
Winches 4 Skagit DTW 150 SXS Loaded Draft 12 '.
i Double drum Fuel Capacity 110,000 gations Line Pull 4 @ 300,000 lbs.
Potable Water 146,000 gallons (1,200,000 lbs. total)
Lube 1,500 gations Dow Anchor Wires (4) 3900' of 2* wire Main Engines 2 EMD 12 645 E5 Stern Anchortmd (2) 3900' tsf 2* wire Auxiliary Engines 2 Caterpillar D 343 Tow Wires (1) 5100' of 1%
- wire Propellers Twin Screw,5-blade (1) 6900' of 1%* wire Horsepower 5,000 Emergency TowJ.ine, 800' of 8' rope hawser Reduction Gear Falk, ratio 4.480:1 Bow Thruster 200-h.p.
Bow Thruster 150-h p.
Anchors (2) 2390-Ib.
Anchors (2) 1000 lb.
(4) 12,000-Ib. bow Navigation /Cornmunication Radar: 2 Furuno Navigation / Communication Radar: 2 Furuno Equipment 3 VHF, SSB, phone Equipment 2 VHF, SSB, Loran: Northstar 6000 Loran: Northstar 6000 Satellite Navigator Crawley Maritime Corporation's tug and tsarge fleet of some 450 vessels includes ocean tugs to 9,000 horsepower, harbor /ri.er tugs, ocean-going deck barges tJ 730 feet in length with three decks (the world's largest RO/RO barges), harbor / river deck barges, covered barges, and oil l
bar *- to 16,200 dwt (long ton) capacity. In addition, the company operates a fleet of more than two dozen ship, serving 'n the Caribbean, Central a, South A'nericar., European, and Far Eastern trades.
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