ML20205D910
| ML20205D910 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/20/1988 |
| From: | Ellen Brown PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Carr K, Curtiss J, Roberts T, Rogers K, Zech L NRC COMMISSION (OCM) |
| References | |
| CON-#488-7326 CLI-88-07, CLI-88-7, NYN-88142, OL-1, NUDOCS 8810270248 | |
| Download: ML20205D910 (164) | |
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NYN- 88142 Pubuc SeMee of New Hampette ,88 OCT 21 A10:06 October 20, 1988 New Harnpshire Yankee Division
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United States Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Attention: Lando W. Zech, Jr. , Chairman Thomas M. Roberts, Commissioner Kenneth H. Carr, Commissioner Kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner
Reference:
(a) Facility Operating License NPF-56, Docket No. 50-443 (b) NRC Order CLI-88-07, dated September 22, 1988
Subject:
Response to CL1-88-07 Gentlemen: On September 22, 1988, the Commission issued CLI-88-07 in which it deter-mined that: the unique and unusual circumstances of this case require that before low power may be authorized, Applicants provide reasonable assurance that adequate funds will be available so that safe decomm!ssioning will be reasonably assured in the event that low power operation has occurred and a full power license is not granted for Seabrook Unit 1. The Commission thus requested that within 30 days of the date of CLI-88-07, Applicants submit: adequate documentation of their plan and appropriate commitrents under that plan to provide reasonable assurance that adequate funding for decocusissioning will bu available in the event that a full power license is not granted for Seabrook Unit 1. CLI-88-07, eages 2-3. The purpose of this letter is to respond to the Commission's request in CL1-88-07 by presenting a plan describing the steps necessary to return Seabrook Unit 1 to unrestricted use and terminate the license after the facility has operated at up to 5% of rated power (hereinaf ter referred to as the Plan), estimating the costs of implementing that Plan, and providing assurances that adequate funding to cover those costs will be available in the event that authorization to proceed beyond 5% power is not granted for Seabrook Unit 1. 0010270240 001020 PDR O ADOCK ODOOO443 PUR O) P.O. Box 300. Seabrook. NH 03874 . Telephone (603) 474 9574
O United States Nuclear Regulatory Commission October 20, 1988 Attention: Lando W. Zech, Jr. Chairma" Page 2 Thomas M. Roberts, Commission Kenneth M. Carr, Commissioner Kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner A. Options for the Site At the outset, it should be noted that, in the event that the facility were operated for low power testing purposes but not granted authorization to proceed beyond 5% power, the Seabrook Joint owners could consider a number of options for the Seabrook site, all of which would include the Plan as a first step. Among the options which could be considered is utilization of the site by using aaother type of fuel for alectric power generation. In this option, the Plan would be implemented, thus releasing the site for unrestricted use. The nuclear portion of the plant would be abandoned (the nuclear side of the plant could not be used for any alternative generating purposes whether low power testing is accomplished or not) and certain portions of the non-nuclear buildings and systems could be used to build a fossil fuel generating plant. Alternatives could include a coal-fired facility, an oil-fired f acility or a combined-cycle gas-fired f acility. New cash requirements for building a fossil fuel fired facility would range from a minimum of $1 billion to more than $2 billion, and 8 to 10 years would be required, depending on the type and size of the plant. In any event, compliance with NRC's decommissioning and license tercination requirements would be an important initial step in any option for use of the site that might be selected. B. Decommissioning Guidance and Criteria New Hampshire Yankee (NHY) has looked to, and applied the NRC's decom-missioning rules, 53 Federal Register 24018 (June 27, 1988), toe definitions. criteria and assumptions to be used in formulating this response. In ' , particular, in preparing the Plan and attendant cost estimate, NHY has concluded that " ' Decommission' means to remove (as a facility) safely from service and reduce residual radioactivity to a level that permits release of : the property for unrestricted use and termination of license." 10 CFR 50.2. The rules also provide that "[djecommissioning activities [are not to) include the removal and disposal of spent fuel which is considered to be an operational activity or the removal and disposal of nonradioactive structures and saaterials beyond that necessary to terminate the NRC license." 53 Federal Register 24018. This guidance has also been incorporated in this response. C. Low Power Operation The type of operation that Seabrook Unit I would experience in the scenario posited by the Commission in CLI-88-07 differs substantially from the life-time of full power operation contemplated in the NRC's new decommissioning regulations. The low power test program for Seabrook Unit I calls for heatup and initial criticality followed by 10 days of intermittent testing at a power level of between 0.01 percent (1/100th of 1 percent) and 0.1 percent 1
United States Nuclear Regulatory Commission October 20, 1988 Attention: Lando W. Zech, Jr. Chairman Page 3 Thomas M. Roberts, Commission Kenneth M. Carr, Commissioner Kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner (1/10th of 1 percent) of full power and 12 hours of intermittent testing in the range of 2 to 3 percent of full power. This testing programs results in the operation of the reactor for the equivalent of approximately 45 minutes or 3/4 of one effective full power hour.1 Because of the limited time associated with low power operation of a pressurized water reactor, the radiological impact will be minimal and isolated to very specific areas and components within the plant. The only long-term radiological concern outside of the fuel would be from direct Cobalt-59 neutron activation of certain sections of the reactor vessel and associated internals that are immediately adjacent to the core. As confirmed by recent startups at other nuclear plants, gaseous fission products that enter the primary coolant and any coolant activation products are short-lived in nature with half-lives less than 24 hours. Since opera-tion at criticality is limited, the buildup of corrosion products is not expected to occur. It is expected that plant radtoactivity levels will be undetectable shortly after low power testing is concluded, but if they were detectable, they would consist of short-lived isotopes that decay within a few weeks of shut-down. After that period, the onle steas in the plant expected to contain radioactive material would be certain sections of the reactor vessel and associated core internals, reactor fuel and, potentially, in process system filters and demineralizers. D. The Plan To respond to the Commission's request in CLI-88-07, NHY has formulated the Plan which describes the steps necessary to return Seabrook Unit 1 to unrestricted use af ter the facility has operated for low power testing purposes in the manner described above. The implementation of this Plan, described in more detail below, would cost approximately $21 million. All major work would be accomplished in about 20 months with a greatly reduced site workforce. The shipment of the fuel would then commence and continue through the end of month 49. Decontamination of the fuel storage pool would 1 A previous estimate of one and one half effective full power hours was based on a conservative calculation that assumed that the plant was taken to dif f erent power levels during low power testing. Refined and more accurate e s t ima t e s show the effective full power hours from low power testing to be somewhat less than that previous estimate. t
United States Nuclear Regulatory Commission October 20, 1988 Attention: Lando W. Zech, Jr. Chairman Page 4 Thomas M. Roberts , Commission Kenneth M. Carr, Commissioner . Kenneth C. Rogers, Commissioner l James R. Curtiss, Commissioner finally be completed by the end of month 52. The Plan (set forth in the Attachment to this letter) entails removing all the fuel from the reactor for eventual shipment offsite, verifying that there is no fixed or removable radioactive material, and decontaminating (if necessary) equipment, components and systems, and dismantling the reactor vessel and associated internals for shipment to a licensed low-level waste disposal site. The Plan thus provides for the removal of the nuclear facility safely from s6 vice and the reduction of residual radioactivity to a level that permits release of the property for unrestricted use and termination of the NRC licenses. In the hypothetical event that authorization to proceed above 5% power is not granted for Seabrook Unit 1 after low power testing has been performed, the following steps would be taken:
- 1) The Plan and an application for termination of the operating license in accordance with the provisions of 10 CFR 50.82 would be filed with ,
the NRC.
- 2) NHY would immediately begin the process of unloading fuel from the reactor and storing the fuel in the Fuel Storage Building. This activity would be completed by the end of month 2 of the Plan process.
- 3) Flushing and, as necessary, decontamination of plant systems used during low power testing would be initiated in month 2 and would be sufficiently complete by the end of month 7 to allow the initiation of work to remove and dispose of the reactor vessel and internals.
- 4) At the end of month 7, dismantling of the reactor internals and the reactor vassel would commence. For purposes of this Plan, NHY has made the conservative assumption that the reactor internals and the entire reactor vessel would need to be dismantled, cut-up, put into licensed containers and shipped to a licensed disposal site as low level waste.
In fact, it is much more likely that activation of the vessel will be such that only portions of the vessel will need to be dismantled and cut out. In either case, dismantlement will proceed from month 7 through month 20, with shipment in month 21, at which time the Plan process would be essentially complete.
- 5) Fuel would be stored onsite with required security and operational safe- I guards. By month 20, shipments to an overseas reprocessing facility would commence. Fuel shipment of fsite vould be completed in month 49.
Final radiological surveys and decontamtnation (if necessary) of the fuel storage pool and related equipment would be completed in month $2.
United States Nuclear Regulatory Commission October 20, 1988 Attention: Lando W. Zech, Jr. Chairman Page 5 Thomas M. Roberts, Commission Kenneth M. Carr, Commissioner Kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner
- 7. Cost Study On the basis of the Plan described above, the costs of returning the facility to unrestricted use and terminating all NRC licenses were estimated.
In estimating such costs, it was assumed that necessary approvals of the Plan would be given so that major dismantling activities can begin seven months after the Plan is submitted to the NRC. The cost estimate includes:
- costs of maintaining the fuel onsite until all fuel is shipped offsite and decontaminating the fuel storage pool and related components after fuel is removed;
- costs for radiological survey and decontamination, as required, of l systems used in the low power test program and the subsequent off loading of fuel as well as surveys required to allow unrestricted use;
- costs for segmenting, packaging, shipping and disposing of the reactor vessel, reactor internals and core instrumentation;
- costs of direct labor (craft) and indirect labor (plant operatore, health physics technicians, instrumentation and controls technicians, cicotri-cians, engineering, quality assurance, supervision, security, licensing personnel and administration) and materials (low level waste shipping i containers, specialty tools);
costs for preparation of an Environmental Report Supplement;
- costs of insurance; and
- costs of electricity and other utilities.
Based on the foregoing assumptions, NHY has conservatively estimated the costs to implement the Plan to be about $21 million spread over a period of about 52 months. These costs consist of: Staff, Operating and Decontamination Expense $ 9.99 Million Dismantlement, Packaging, Shipment and Disposal $ 4.79 Million of Reactor Vessel and Internals NRC Fees and Insurance $ 4.96 Million contingency $ 1.36 Million TOTAL $21.10 Million ! I b (
United States Nuclear Regulatory Commission October 20, 1988 Attention: Lando W. Zech, J r. Chairman Page 6 Thomas M. Roberts, Commission Kenneth M. Cirr, Commissioner Kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner As discussed above, the Plan cost estimate includes those costs necessary to reduce residual radioactivity to a level that permits release of the property for unrestricted use and termination of the license. There are costs, not included, that would be incurred by the Joint Owners in any event if the pro;ect was terminated before low power testing such as: contract termina-tion costs, project accounting, claims settlements, severance pay, property tax settlements, disposal of fuel, non-nuclear-related insurance, or the costs of demolition and removal of nonredioactive structures or materials or preparations for total abandonment of the site. (Indeed, if total termina-tion cf the project were to occur today prior to any low power testing, the total easts, including those listed herein, are es:imated to be in the range of $120 millfon to $390 million in 1988 dollars.2) Thfs estimate of the costs to comply with the NRC's decommissioning rules a l t es t low power testing differ from, and are more appropriate than, the ', gerrric minimum decommissioning costs set out in 10 CFR 50.75 for utiliza-L tim. facilities that are assumed to have operated at or near full power for tne full term of the license. This Plan and the $21 million costs to i 2It is important to emphasize the distinction between the costs inherent in the Plan and other estimates of so-called "decommissioning costs" which have been discussed in other forums relating to Seabrook: i Public Service Company of New Hampshire ("PSNH") and its various creditor ! cc mmittees have been examining in the context of PSNH's on going bankruptcy ; proceeding t'se estimated costs of several hypothetical scenarios involving the potential permanent shut down of the Seabrook project. Those estimates reflect i all the legal exposures to which PSNH, as one of the joint owners of the project, i tould be subject in the event of the hypothesized suspension, many of these legal exposures being beyond the technical decommissioning actions required by the Commission's regulations. Thus, those estimates reflect demolition of all structures on the site (other than those with potential commercial applications), r.o t just the decontamination and removal of radioactive materials and structures; contract termination and settlement charges owed to the numerous contractors involved in the project; severance pay and pension obligations for terminated staff; property taxes: and administrative support staff and expenses necessary to support the foregoing activities over the period of time projected for i completing these tasks. I s
United States Nuclear Regulatory Commission October 20, 1988 Attention: Lando W. Zech, Jr. Chairman Page 7 Thomas M. Roberts, Commission Kenneth M. Carr, Commissioner Kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner implement it should not be confused with, and cannot be compared to, such "end-of-operating-life" decommissioning plans and costs.3 F. Reasonable Assurance The Joint Owners have consistently acknowledged their responsibility for decommissioning the Seabrook project whenever its usefulness comes to an end. This responsibility takes several forms: As licensees of a commercial utilization facility under the Atomic Energy Act of 1954, as amended, and the Commission's regulations thereunder, the Joint Owners are obligsted to decommission that facility at the end of its useful life with minimal impact on public and occupational health and safety and the environment. As parties to the Seabrook Joint Ownership Agreement they have expressly provided for their several liability for the costs of decommissioning. (See Paragraphs 11.1 and 13A of the Joint Ownership Agreement). Furthermore, the State of New Hampshire has legislatively restated that obligation and made it enforceable by the New Haapshire 3During 1987 snd early 1988, NHY presented testimony supporting a decommissioning study before the New Hampshire Nuclear Decommissioning Financing Committee (the "NH committee") pursuant to New Hampshire RSA Chapter 162-F. Under that statute, the NH Committee is assigned the responsibility for deter-mining the funding requirements for permanently removing a nuclear electric-generating facility from service at the end of its energy producing life, such amount to be collected in monthly installments during the life of the facility, beginning with the first full month of service, and to be held under the administrativo control of the Treasurer of the State of New Hampshire. The NHY's decommissioning study estimated that decommissioning Seabrook Unit 1 after 40 years of operation would cost apptoximately $242 million in 1987 dollars, assuming the use of the DECON decommissioning alternative. The cost differential reflects primarily the significant diffsrence in residual radioactivity af ter 40 years of full power operation as opposed to the equivalent of approximately 3/4 of an effective full power hour of operation involved in low power testing and the fact that the 40 year life decommissioning cost is based on complete demolition of Unit 1 and includes site rehabilitation. It does not, however, include other owner cancellation costs such as contract termination costs, project accounting, claims, settlement and severance pay. A decision from the NH Committee is anticipated in the near future which will establish the initial level of decommissioning funding to be collected pursuant to this statute, which level is subject to periodic adjustment during the er.ergy-producing life of the facility. See NHRSA 164-F:22.
United States Nuclear Regulatory Commission October 20, 1988 Attention: Lando W. Zech, Jr. Chairman Page 8 Thomas M. Roberts, Commission Kenneth M. Carr, Commissioner kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner Attorney General. See NHRSA Chapter 162-F. /s responsible e12ctric utilities and licensies, the Joint Owners are cooperating with the NH Committee and the Treasurer of the State of New Hampshire to formulate funding arrangements through which they intend to fulfill this obligation during the anticipated life of the facility under the applicable require-ments of both the Commission and the State (f New Hampshire. Despite these longer term plana, the Commission has asked for further explanar. ion of hou such obligation would be met in the unusual circumstance that aut horization to proceed beyond 5% power is never granted after low " power testing is performed. As indicated above, the cost to implement the Plan under scch circumstances is estimated La be about $21 million which would be expended over 17 calendar quarters. The normal procedure under the Joint ownership Agreement would involve each Joint Owner being billed for its proportionate share of those expenditures as they are incurred. It is anticipated that expenses would be $11.98, $5.63, $1.39 and $1.!9 million, respectively, for each of the first four years and $.68 million in the final four months. These amounts, in the normal course, would be payable by the Joint Owners from their gross operating revenues for those periods. Therefore, those annual amounts should be compared with the gross operating revenues of the Joint Owners. In 1987 those gross revenues aggre3ated approximately $5.066 billion and the Joint Owners aggregate operating revenues, net of purchased power costs and fuel expense, in 1587 aggregated approximately $3.265 billion. In short, the total $21 millior cost of implementing the Plan equates to 0.42% of the Joint Owners grcas revenues in 1987 and the 0.64% of the Joint Owners net operating revenues for the single year 1987 and would be proportionately less as the Plan impleaentation cost is spread over 17 quarters. In this connection it must be pointed out that there are three Joint Owners as to which special considerat ions apply. As to PSNH, it is important to ' note that, as a result of the suspension of certain interest expenses due to the pending bankruptcy proceeding, available net revenues have increased 4 and that the obligation of PSNH to pay its share of the costs included in the Plan could not be avoided by reason of the pending bankruptcy proceeding. See Midlantic National Bank v. New Jersey Deoartment of Environmental , Resource, 474 U.S. 494 (1986). Massachusetts Municipal Wholesale Electric Company ("KFWEC") with its 11.5934% share which is currently seeking a l 4 See Response to NRC Question No. 6 in Enclosure to NYN-88115. PSNH Letter I dated August 31, 1988, Re: "Request for Additional Information," in Docket No. i 50-443.
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United States Nuclear Regulatory Commission October 20, 1988
; Attention: Lando W. Zech, J r. Chairman Page 9 Thomas M. Roberts, Commission Kenneth M. Cars, Commissioner Kenneth C. Rogers, Commissioner James R. Curtiss, Commissioner "financially responsible" termination of its participation in the Seabrook project, nevertheless has "funds necessary to cover a potential $10 million decommissioning exposure in the bank", an amount more than sufficient to cover its exposure under the circumstances posited by the Commission's order 5. Finally, EUA Power Corporation ("EUA Power") with its 12.1324%
share is not currently generating operating revenues; however, in anticipa-tion of that fact when it acquired its interest in Seabrook in 1986 it established a Decommissioning Costs Security Agreemant with State Street Rank and Trust Company, into which $10 million of securities have been deposited, again an amount more than sufficient tn cover its exposure under the circumstances posited by the Commission's crear. NHY submits that the foregoing demonstrates that ;'sts of the hypothesized pre-full power-authorization decommissioning of Seabrook would be de minimis in comparison to tho aggregate revenues and available funds from which they would be payat'.e and therefore reasonable assurance exists chat these costs would be funded. NHY is aware that the Commission's regulations, 10 CFR 50.75, establish the "recuirements for indicating to the NRC how reasonable assurance will be provided that funds will be available for decommissioning" which by their terms are applicable to consideration of decommissioning in the context of , anticipated routine full power operations. In accordance with tnese regula-tions applicable to full power, full term operation, NHY will file a decommissioning report, as required by 10 CFR 50.33 (ki, which contains the final decision of the NH Committee with respect to funding requirements, the schedule of payments with respect thereto which are to be paid into an external sinking fund during the life of the facility, a copy of thc trust instrument creating that external sinking fund, and evidence with respect to the Request for Ruling Amounts applicable thereto filed with the Internal Revenue Service. In tne interim, as a demonstration of their bona fides, the Joint Owners have taken the followtng steps to provide comparable "reasonable assurance" of their ability to fund the $21 million required to implement the Plan: On October 19, 1988, the Joint Owners voted to establish a separate and segregated "Pre-operation Decommissioning Account in the control of the Disbursing Agent for the sole purpose of defraying expenditures incurred in implementing the Plan. They also voted to fund that account, promptly after S See Attachment 2 to NYN-88124, PSNH Letter to Staff dated September 13, 1988, in Docket No. 50-443.
I
- United States Nuclear Regulatory Commission Octobar 20, 1088 Attention: Lando W. Zech, Jr. Chairm:n Page 10 Thomas M. Roberts, Commission Kenneth M. Carr, Commissioner Kenneth C. Reners, Commissioner James R. Cur.iss , Commissioner issuance of a Commission order requiring such funding, in the amount of
$21,069,500, those funds to be held by the Disbursing Agent until expended in accordance with the Plan or until Seabrook Unit I receives authorization to proceed above 5% power, whichever first occurs. The votes authorize approximately half of such amount to be transferred from the Project account presently controlled by the Disbursing Agent and the other half would be new monies paid in by the Joint Owners. The first half is reasonably assured because che balance presently available in the Project account in respect of each Joint Owner substantially exceeds its share of the required amount, except in the case of MMWEC, an 11.59340% owner, and Vermont Electric Transmission and Generation Cooperative, Inc., a 0.41259% owner ("Vt.
Coop"). The latter half is reasonably assured because it is de minimis in relation to the Joint Owners operat . revenues. As to MMWEC and the Vt. Coop, MMWEC has publicly anaounced at it has funds available to meet up to
$10 million of its decommissioning obligations and the $85,000 attributable to the Vt. Coop's share would be paid on its behalf from the same sources which have been funding its on going share of costs. Finally, the votes also directed that the EUA Power share (12.13240%) of such amount be paid out from the fund created under the existing Decommissioning Costs Security Agreement in which $10 million is currently deposited.
In conclusion, NHY submits, or. b= half of the Joint Owners, that the foregoing provides reasonable assutance that the funds necessary to implement the Plan, if that should become necessary, will be available. Very truly yours, T -- .0 Edward A. Brown President and Chief Executive Officer Enclosures cc: Atomic Safety and Licensing Board Service List Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 Division of Reactor Projects United States Nuclear Regulatory Commission Washingtsa, DC 20555 Mr. David G. Ruscitto Senior Resident Inspector P. O. Box 1149 Seabrook, NH 03874
STATE OF NEW HAMPSHIRE October 20, 1988 Rockingham, ss. Then personally appeared before me, the above named Edward A. Brown who, being duly sworn, did state that he is President and Unief Executive Officer of New Hampshire Yankee Division of Public Service Company of New Hampshire, that he is duly authorized to execute and file the foregoing information in the name and on the behalf of Public Service compan-/ of New Hampshire, and that the statements therein are true to the best of his knowledge and belief.
@ w OL b b Okuyoz Beverly E. Silloway, Notary Pehlic My Commission Expires: March 6, 1990
CERTIFICATE OF SERVICE 00C klif ? L Nr0 3 copies of the foregoing letter and its attachment are being sent by Federal Express to the following individuals: '8B 007 21 N0 07 OD n! - . Alan S. Rosenthal, Chairman RobertCarri[kh"dhlyma,n t iF F Atomic Safety and Licensing Appeal Panel Board of Selectmen U.S. Nuclear Regulatory Commission Town Office East West Towers Building Atlantic Avenue 4350 East West Highway North Hampton, NH 03862 Bethesda HD 20814 Diane Curran Esquire Thomas S. Hoore Andrea C. Forster, Esquire Atomic Safety and Licensing Appeal Panel Harmon & Weiss U.S. Nuclear Regulatory Commlasion Suite 430 East West Towers Building 2001 S Street, NW 4350 East West Highway Washington, DC 20009 Bethesda, MD 20814 Stephen E. Herrill, Esquire Administrative Judge Sheldon J. Wolfe, Attorney General Esquire, Chairman George Dana Bisbee, Esquire Atomic Safety and Licensing Board Panel Assistant Attorney General U.S. Nuclear Regulatory Commission Office of the Attorney General East West Towers Building 25 Capitol Street 4350 East West Highway Concord, NH 03301-6397 Bethesda HD 20814 Adjudicatory File Administrative Judge Emmeth A. Luebke Atomic Safety and Licensing 4515 Willard Avenue Board Panel Docket (2 Copies) chevy Chase HD 20815 U.S. Nuclear Regulatory Commission East West Towers Building Dr. Jerry Harbour 4350 East West Highway Atomic Safety and Licensing Board Panel Bethesda, MD 20814 U.S. Nuclear Regulatory Commission East West Towers Building
- Atomic Safety and Licensing 4350 East West Highway Appeals Board Panel Bethesda, HD 20814 U.S. Nuclear Regulatory Commission Washington, DC 20555 lioward A. Wilber Atomic Safety and Li'ensing Appeal Panel Philip Ahrens. Esquire U.S. Nuclear Regulatory Commission Assistant Attorney General East West Towers Building Department of the Attorney General 4350 East West Highway Augusta. HE 04333 Bethesda HD 20814 Paul McEachern, Esquire Hr. Richard R. Donovan Hatthew T. Brock Esquire Federal Emergency Management Agency Shaines & McEachern Federal Regional Center 25 Haplewood Avenue 130 228th Street, S.W. P.O. Box 360 Bothell, WA 98021-9796 Portsmouth, NH 03801
b CERTIFICATE OF SERVICE (Continued) Mrs. Sandra Gavutis, Chairman R. Scott Hill-Whilton Board of Selectmen Lagoulis, Clark Hill-Whilton & McGuire RFD 1. Box 1154 79 State Street Kensington, NH 03827 Newburyport. HA 01950
- Senator Gordon J. Humphrey Mr. Peter S. Matthews United States Senate Mayor Washington, DC 20510 City Hall Attention: Tom Burack Newburyport. HA 01950
- Senator Gordon J. Humphrey Mr. William S. Lord One Eagle Square, Suite 507 Board of Selectmen Concord, NH 03301 Town Hall - Friend Street Attention: Mary Jane Colton Amesbury HA 01913 Mr. George Olson H. Joseph Flynn, Esquire Town Manager Office of General Counsel Town of Exeter Federal Emergency Management Agency 10 Front Street 500 C Street, SW Exeter, NH 03833 Washington, DC 20472 Sherwin E. Turk, Esquire Gary W. Holmes Esquire Office of General Counsel Holmes & Ells i U.S. Nuclear Regulatory Commission 47 Winnacunnet Road One White Flint North, 15th Floor Hampton, NH 03842 11555 Rockville Pike Rockville, HD 20852 Judith H. Hizner, Esquire ;
79 State Street Robert A. Backus, Esquire Second Floor Backus, Heyer & Solomon Newburyport, MA 01950 116 Lowell Street P.O. Box 516 Lando W. Zech, Jr. Chairman Manchester, NH 03105 U.S. Nuclear Regulatory Commission One White Flint North Mr. J. P. Nadeau 11555 Rockville Pike Selectmen's Office Rockville, MD 20852 10 Central Road Rye, NH 03870 Kenneth H. Carr, Commissicner U.S. Nuclear Regulatory Commission Carol S. Sneider, Esquiro One White Flint North Assistant Attorney General 11555 Rockville Pike Department of the Attorney Gsneral Rockville, MD 20852 One Ashburton Place, 19th Floor Boston, MA 02108 Kenneth Rogers Commissioner U.S. Nuclear Regulatory Commission Calvin A. Canney One White Flint North , City Manager 11555 Rockville Pike City Hall Rockville, MD 20852 126 Daniel Street ; Portsmouth, NH 03801 b
,- - - - - - , , , _ . - . _ - - , - _ , _ _ _ , , - - ~ ,_ . , _ , - - - -
CERTIFICATE OF SERVICE
-(Continued)
Marjorie Nordlingler Esquire Deputy General Counsel Office of the General Counsel One White Flint North 11555 Rockville Pike Rockville, MD 20852 Charles P. Graham, Esquirs Murphy and Graham 33 Low Street Newburyport. MA 01950 Richard A. Hampe. Esquire Hampe and McNicholas 35 Pleasant Street Concord, NH 03301 Thomas M. Roberts Commissioner U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 , James R. Curtiss, Commissioner U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 William C. Parler, Esquire General Counsel Office of the General Counsel One White Flint North 11555 Rockville Pike Rockville, MD 20852
- U.S. First Cle.;. Mail
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f 1 I l Sea]roo< Unit 1
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in Res30nse to :
- N 30 Orcer CLI-88-:7 :
t Octo]er 1988
l THE PLAN l lN RESPONSE TO NRC ORDER CLI-88-07 1 i Prepared By: NEW II AMPSillRE YANKEE i
- l i
1 l OCTOBER,1988 l l I t
t 1 TABLE OF CONTENTS
- 1. Summary 4
- 2. General Overall Assumptions
- 3. General Oierview
> 1. Licensing Requirements i
- 5. Preliminary Activilles i
- 6. Fuel Unloading
- 7. Decontamination Operations
)
- 3. Reactor Yessel & Associated l Components Removal & Disposal i
- 9. Storage & Fuel Remova!
i l i 10. Decontamination of Fuel Storage Building r
- 11. Supporting Operations l
l l
, r . - - __ ._,,, - -- ._ _-- -.-.m__ . _ ,.r. - - . _ . _ . . , , , _ _ . _
SUMMARY
SUNf 5f A RY On September 22,1988, the Commission issued CLI 88 07 which requested that within 30 days of that date the applicants submit:
"adequate doc'imentation of their plan and appropriate commitments under that plan to provide reasonable assurance that adequate funding for decommissioning will be available in the event a full power license is not granted for Seabrook Unit 1."
As a resuit of that order, New Hampshire Yankee (NilY) undertook a study to determine the actions that would be required to decommission . Seabrook Unit I in the event that this became necessary after low power l testing. In accordance with 10 CFR 50.2, decommissioning is defined for purpose of this study as the safe removal from service and reduction of residual radioactivity to a level that permits release of the property for unrestricted use and termination of the license. The results of that study are detailed in the sections of this document, hereinafter referred to as The Plan. The basic objective of The Plan is to outline the actions required to permit unrestricted use of the property, in the case of Seabrook Unit I, this has been decmed to mean the reduction of all residual radioactivity to precriticality levels, as determined by comprehensive radiation surveys during l the decontamination, removal and disposal process, and finally after all low ' l level waste and fue! have been shipped offsite. ; The actual process of returnirs the Seabrook Unit I site to unrestricted i use after low power testing would be relatively straightforward and could be ! accomplished using existing technology. A wide range of alternatives and options was considered in formulating The Plan. The option self ited was l decontamination with water flushing of associated piping system, and cleaning ! of air handling systems along with cutting the reactor vessel and assoe ;sted j components into manageable pieces that could be shipped in Department of : Transportation (DOT) approved containers to a low level waste depository. l This option was conservatively selected even though New Hampshire Yankee has concluded that low power testing at Seabrook Station will result in negilgible radiological impact (see Attachment 1 in Section 7.5). Based on experience provided by other nuclear power slants, reactor coolant radioactivity and contamination produced during low power testing consists of short l'ved isotopes that decay within one to two weeks. After this decay period no significant levels of radioacti'.c material would be found within . major portions of the reactor system. The only areas in the plant expected to contain radioactive material within a few weeks following low power testing would be certain sections of the reactor vessel and associated core internals, reactor fuel, and potentially process system filters and demineralizers in the l ' primary auxiliary building. Therefore, there is no long term contamination of the plant from low power testing. Page 1-I L _ _ _ _ - . _ - - . - .
SUMMARY
However, notwithstanding the foregoing conclusion, New Hampshire Yankee took a conservative approach to all Plan activities. In this approach, systems which might remotely be contaminated during low power testing were included in the decontamination phase. The entire reactor vessel and associated components are assumed to be cut up and disposed of as low level , waste even though a majority of the vessel will not be contaminated and can i be disposed of as non radioactive scrap metal. l An overall summary schedule for this process is shown in Figure 1. The assumptions governing this process are defined in Section 2 (General Overall Assumptions). a brief summary of each of the major steps to be taken is provided in Section 3 (General Overview), and these steps are detailed in Sections 4 through 10. The major steps involved in this process include: o Filing a detailed plan with the h'uclear Regulatory Commission (NRC) and an application for terminatior of the operating license in , accordance with 10 CFR 50.82.
. Immediate actions to transfer fuel from the reactor to the fuel storage ,
building. o Decontamination of plant systems used during low power testing. , o Upon receipt of NRC approval of the detailed plan, removal and
- disposal of th
- reactor vessel and internals. l
. Shipment of the reactor vessel and internals and other low level waste to a licensed low level waste repository.
. Storage of fuel until preparations are msde for shipment offsite. !
. Decontamination of the fuel storage building and associated systems after fuel is shipped offsite. !
Activities which could have any potential impact on public health and safety l would be rerformed and governed by the New Hampshire Yankee Quality - Assurance Program. In addition, all Technical Specifications appropriate to the mode of operation would be adhered to. These incirde provision for radiological and environmental monitoring and surveillances. Occupational i 1 exposures would be maintained as low as reasonably achievable in acccrdance . with previous commitments (see FSAR Section 12.1.1). Costs associated with ' these safeguards as well as provisions for physical security of the site until ! termination of the license have been included in The Plan and overall cost estimates. . i f Page 1-2
SUMMARY
The environmental effects of implementation of The Plan would be much smaller than the generic impacts presented in the Generic Environmental Impact Study (NUREG 0586). NUREG 0586, therefore, would envelope the impact of decommissioning Seabrook Unit 1. A supplement to the environmental report, however, would be submitted to the NRC as part of the application for operating license termination. The majority of activities will take twenty months to complete. Final project completion is estimated to be at the end of month 52, which is after the completion of decontamination activities associated with the fuel storage building. The length of the operation conservatively estimated to be 52 months, is driven by the selected method of fuel disposal, reprocessing, which is dependent on the number and turnaround time of shipping casks. Using the conservative assumptions on which The Plan is based, the cost associated directly with returning Seabrook Unit I to unrestricted use is
$ 21,069,500. For comparison and information only it has been determined that under the most likely scenario in which minimal or no residual radiation and contamination exists the costs would be $15,295,900 in 1988 dollars. Table I shows cost summaries for both possibilities.
, The team assembled to prep 7re this study has a diversified backstound covering construction, operations, reactor engineering, health physics, system engineering, backfit and outage rinnagement including large component removal and decontamination experience. .; in conclusien, returning Seabrook Unit I to unrestricted use after low power testing can be accomplished in 52 months and for a cost of $21,069,500, using highly conservative assumptions. J )
, Page 13 t
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LOST SLlenaARY T M PLAM T M PLAM suteh C _ : Ase W m The Plos 8f C. _ :_- Asseepstems Ae, Paes 7 y
. Peelemassey Attevesses Prepareseos of f ace sesee m s Goandaag S 31.300 $ 8 f met necesse me.ad.es reeseos armere S 44.200 $ MD Reme.e enestessee 1 mW I *"
S )$4J00 5 330M
. Teet (Jeteedens S 95.400 $ *t.400
. Decessamensasse Ortesesses S 3.302w S 300.700
. Reme.si med Despenal Reacter tresses and Assoc 4esed Compeeemos S 4.798.300 $ 8.188.000
. $ssense and Preparessee (as Reme.sa
*f Fmel S 1H.700 5 109.700
. De<smesmeeses Feel Seesser Oe 4deas S 330.400 $ 4SA00
. Seppeetens Operasseen Neemeneel and Secuesey 5 7,499J00 5 6.384.300 Acceeesses and Payee 64 5 377.000 $ 377A00 NRC t ees S 906.400 5 906.400 loosenece 1 134 00m 1 1 94? 300
$ _j'Rm 1 11171 ?as Set Tsees S 39.70s.700 S 84JS2.300
. Ceasessency S 3.300.000 $ 941.000 Teses 5 28A09300 $ , t S.295.900 D NOTE: AB esters ese he 8908 det*. ass TASE2 1 Pese t-6
- _ - - - -_ - , _ _ _ _ _ - . - - , . . _ . . - - - --- , ..._,m --
GENERAL OVERALL ASSUMPTIONS GENER AL OVER ALL ASSUMPTIONS
- 1. All required Technical Specifications appropriate to the mode of operation, radiological control and environmental programs are maintained and met until fuel is offsite and final decontamination of the fuel storagi, building.
- 2. License chante from operating license with low power restriction to possession only license received within 3 months.
- 3. Conservative assumptions were used for all aspects of The Plan in that numbers of systems involved, radiation levels expected, amounts of contamination anticipated and duration of fuel removal from the site were estimated conservatively high.
- 4. Activities that could have any potentialimpact on public health and safety would be performed under and governed by the New flampshire Yankee Quality Assurance Program.
- 5. Release for unrestricted use by }{calth Physics would be based on pre-critical Radiation Control Area surveys.
- 6. NRC and the Department of Transportation (DOT) license approval of TN 12 shipping cask shortens fuel removal time by 8 months.
- 7. All work is conducted under As Low As Reasonably Achievable (ALAR A) conditions.
- 8. Cost of fuel shipping, reprocessing and disposal of any associated high level waste is not included in The Plan in accordance with the provisions of 10 CFR 50.2.
Page 2-1
GENERAL OVERVIEW i I GENEM AL OVERVIEW The purpose of this study was to outline the necessary actions and t determine the schedule (Figure 2) and estimated costs (Table 2) associated with returning Seabrook Unit I to unrestricted use and termination of the . NRC license as defined by 10 CFR 50.2 in the hypothetical case that low power testing has been completed and a full power license is not issued for Seabrook Unit 1. ; This study was treated as a Project with seven (7) separate but interrelated major operation , reference figure 2. Sections 4 through 11 of this study provide a detailed description of the ' operations and steps associated with each major operation, They include: i
- Section 4 - Licentine Reaulrements
- This section covers activities necessary for filing a plan with the NRC to return Seabrook Unit I to j unrestricted use and changing the license from a low power operating ;
lleense to a possession only license, and finally terminating all licenses. Receiving a possession only licent.e climinates many Technical Specification requirements and allows t'urther reduction of on site ; manpower. [ For the purposes of the study, NRC approval of The Plan and receipt of a possession only license was assumed to occur within 3 months of the ; request.
- (
l Section 5 - Preliminarv Actitlties: This section covers those activities [ necessary to prepare systems and equipment for actual jecontamination j and dismantling in order to save overall manrem exposure, schedule time i and cost. Activities include the foilowing: !
- l. Removing unnecessary fuel storage pool racks which eliminates the necessity to decontaminate the racks once all fuelis i shipped offsite, j 2, Filling the fuel storage pool with approximately 466.000 l gallons of borated water. This would not normally be donc p until just prior to the first refueling outage.
{
- 3. Installir.g at the entrance of the fuel storage building, local I control and alarm panels fo- fire protection / detection, pool .
level alarms, pool temperature alarms and radiation monitoring ! alarms. This allows long term local monitoring of fuel storage i building parameters without control room interf ace. I t
- 4. Tagging out and draining systems not required for defueling and storage of fuel.
i j 5. Removing insulation for Health Physics surveys of piping systems. i i Page 3 1 I i
GENERAL OVERVIEW . 4 Section 6 - Fuel Uniondine: This part of the operation is a typical l reactor core off loading of fuel into the fuel storage buildia.g. , A total of 193 fuel elements must be moved once the reactor head and associated support equipment are removed. i Section 7 - Decontamination Onerationat The decontamination operations i involve surveying equipment, systems, rooms and buildings that are l' directly and indirectly involved in low power testing, decontamination if necessary, and returning each to unrestricted use. For this section of the operetion a conservative assumption was made i that s) stems or components, directly or indirectly involved with low I power testing would require flushing or cleaning, when in fact very little i if any contamination is expected with the power levels and durations during low power testing. The following activities are included: e Flushing or cleaning piping systems involved, f
- i e Flushing the reactor vessel, i i
e Surveying external surfaces of piping systems involved. e Remove valve internals and survey the inside of piping systems.
. Additional flushing if required. ;
e Additional hand cleaning if requiref.
. Cutting out and disposing as low level waste, any contaminated i areas that cannot be reached for hand cleaning. l r
i e Surveying and release for unrestricted use rooms, systems and
- . buildin in the present radiation control area, with the -
exception of containment and fuel storage pool. (These arcis ! are released r.s work in each is completed.)
- Section - Reactor Vessel & Associated Commenents Removal & Disconal
Several options for disposing of the reactor vessel and associated l components were evaluated. The selected option entails cutting up the l reactor vessel and components into manageable pieces and disposing of the pieces as low level waste, r l Again a conservative assumption was made of high radiation levels i associated with this work. 500 mR/hr was assumed as an average radiation level of all pieces, when in fact, the study team concluded that only the middle portion of the vessel may have any residual radittion after flushing. - I Page 3 2 l l
GENERAL OVERVIEW Section 9 - Storare & Fuel Removal: Once fuel has been off loaded and stored in the fuel storage pool, the study assumed 18 months of storage onsite, before beginning shipment offsite, while reprocessing contracts, shipping contracts and permits are obtained. Once contracts and permits are obtained, shipping of fuel is dependent on the number of shipping casks available and turnaround time involved to a reprocessing facility. The last fuel assemblics are assumed to leave the site in month 49 of the overall schedule. Section 10 - Decontamination of Fuel Storare Buildina: After the last fuel assemblies are shipped offsite, the fuel pool is drained and decontamination, if necessary, of the fuel pool, storage racks and ' associated systems are completed and the facility is released in total for unrestricted use at the end of month 52 of the overall schedule. Section 11 - Suncortina Operations: In addition to the direct work activities listed above, the study team identified and estimated supporting operations and activities necessary to complete the overall project. Supporting operations include: executive management, project management, engineering support, licensing support, quality assurance, health physics and miscellancous operations support. Also included are expenses for power, fees, insurance and overhead. j 1 Page 3 3
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. . TABLE 2 Page 3 - 9
, Licensing Requirements IRC LICENSING ACTIONS ERA DECOMMISSIONING SE ABROOK UNIT 1 AFTER LQW POWER OPER ATION NRC lleensing and approval actions on decommissioning Seaba:'rt Unit I will involve:
- 1) An application for approval of a decommissioning plan and license termination pursuant to 10 CFR 50.82. This application is filed with the NRC staff which will publish a notice (in accordance with section 50.82 (c)) of the proposed action and provide an opportunity for intervention and hearing. Ultimately, approval of the decommissioning plan and license termination will be on such terms and conditions as the Commission determines to be necessary in the circumstances.
- 2) An application for an operating license amendment to remove authorization to operate (convert to possession only license) and delete certain inappropriate technical specification surveillance and maintenance requirements so that unnecessary operational requirements in the license will be eliminated while the licensee completes decommissioninC and decontamination work.
- 3) Subinittal of a supplement to '.he environmental report. The environmerital impact of implementing The Plan, however, will
- be enveloped by the Generic Environmental Impact Statement j'
because of the limited time associated with low power testing and the consequent small radiological impact as compared to a plant that had operated for forty years; because of the relatively small volume of radioactive material that must be i . disposed of as compared to a plant that had operated for forty years; and because of NHY's intention and ability to bring radiological levels down to precriticality levels.
- 4) Conslisnee with 10 CFR Part 71 and 10 CFR 73.67 requirements I
on the transportation of licensed material (e.g. Irradiated fuel, contaminated / activated structures and equipment) to licensed offsite storage or disposal facilities. Applicable requirements generally involve NRC packaging, Quality Assurance (QA), , record keeping, and security provisions in 10 CFR Parts 71 and 4 73, and Department of Transportation shipping requirements referred to in 10 CFR Part 71. Agreements with licensed waste receiving and disposal entities will also be obtained, i Page 4 - 1
Licensing Requirements
- 5) A motion under 10 CFR 2.107 to withdraw the operating license application for Seabrook Unit 1. This motion would be filed with the existing operating license ASLB which would determine the terms and conditions under which withdrawal might be permitted in accordance with section 2.107.
The application for amendment to convert to a possession only license, the radioactive material shipping matters, and the motion for withdrawal of the operating license application need not be acted upon and/or resolved before decommissioning work can begin. The action that is critical to commencement of major decommissioning work is, instead NRC approval of the decommissioning plan. For such approval, the NRC staff must first prepare and issue a technical / safety evaluation of the decommissionirig plan and an Environmental Assessm%:'t A. . the potential environmental impacts of The Plan. 10 CFR 51.95 CA /. view of the fact that the level of radioactive contamination and a;u<ation from the planned low power operation of Seabrook will be enremely low and the attendant decommissioning plan and activities will be Mmple, straightforwar1 and relatively limited, it is anticipated that the staff will be able to complete its safety evaluation and EA and 1 provide its approval of the occommissioning plan within a few months of the date on which the applicati on for plan approval is formally filed. Thus, it is i expected that NRC Plan epproval will not be on the critical path for
! dismantling and decommissioning work. "Although the Commission must approve the decommissioning alternative and major structural changes to 3 radioactive components of the facility or other major changes, the licensee may proceed with some activities such as decoatamination, minor component i
disassembly, and shipment and storage of spent fuel if these activities are i permitted by the operating license and/or (10 CFR] 50.59.'8 Such permitted ] work can and will commence sery soon after the decommissioning plan iJ submitted to the NRC. 1
- i 1
1 a l I heemean sf Ledermin ceami R*=r meau tu Pmmmaan ! h f m1mes. sa Fed Reg. stols (June sr.1964). i Page 4 2
PRELIMINARY ACTIVITIES TABLE OF CONTENTS SECTlQli DESCRIPTION PAGEo i 5.1.1 f.rimaration Of The Furi Storane 5 1 Emildinn For Off Londlan Fuel 5.1.2 Schedule Logic 5 3 I 5.1.3 Cost Estitute / D 2 55 5.1.4 Estimate Back up 5. I 5.2.1 Fuel Storane Buildinn 5 12 Control Center 5.2.2 Schedule Logic 5 14 5.2.3 Cost Estimate / D 3 5 16 l 5.2.4 Estimate Back up 5 19 1 1 5.3.1 Preliminarv Activiiles / Imanlatlan 5 21 EssalAl 5.3.2 Schedule Losic 5 22
- 5.3.3 Cost Estimate / D 7 5 23 5.3.4 Estimate Back up 5 26 i
Preliminary Activities / 5.1.1 PREPAR ATION OF Tile FUEL STOR AGE BUILDING FOR OFF LO iFUEL PU R POSE: Minimize potential future radioactive waste and decon-taminatior, efforts by removing un.1ecessary equipment and components from the teactor cavity and fuel storage pool. ASSUMPTIONS:
- 1. Work in the fuel storage building will not be 'one under radiological situation in tha: no fuel is currently in fuel building.
- 2. Single shift operation five days per week.
- 3. Temporary crane is required to remove unnecessary fuel storage racks.
DESCRIPlON OF ACTIVITIES Some equipment and components located in the reactor cavity and fuel storage building would serse no purpose during a core off load following low power testing. In the reactor cavity, the control rod change fixture and miscellaneous handling tools with their associated support brackets would not be needed. in the fuel storage building, some of the fuel racks and the new fuel elevator would not be necessary. Since these components have the potential to become contaminated during the core off load process . they will be removed prior to removing fuel from the vessel. In the reactor cavity the items to be removed are the control rod change fixture and miscellaneous handling tools. The control rod change fixture is used during a refueling outage to tcke a control rod from one fuel assembly and place it in another fuel assembly. Since the core will be off loaded with all core components left in their respective fuel assemblics, there is no need for the control rod change fixture. The handling tools located in the mvity that would be removed include the irradiation specimen handling tool nd the thimble plug handling tool along with their associated support brackets. Page 5 - I
Preliminary Activities / 5.1.1 The fuel storage pool has 660 fuel storage locations installed. This is approximately one half of the design number of locations. The 660 storage locations are broken up into 6 modular units of 110 storage locations each. Four of these modular units will be removed, using a temporary crane, from the fuel storage pool prior to off loading the core. The 2 remaining modular units contain 220 storage locations which is sufficient to receive the 193 fuel assemblies. The fuel elevator, which is used to transfer new fuel in the fuel storage building, would also be removea 'R l Page 5 - 2
Preliminary Activities / 5.1.2 SCIIEDULE LOGIC Page 5-3
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Preliminary Activities / 5.1. 3 1 COST ESTIMATE 4 L r I l \ l l l l l l l I i l f i l l Page 5 5
CLIEmi : muf DESCRIPTIOu OF WORK: PREPARATI0u 70d Of f LOADluG FUEL (POST LOU POWER TEST!uG) ESTIMATE u0.: 0-2 fuel STORAGE SUILD!uG
..........UmiT RATES------- SUB DESCRIPitou Qi'T Um MAi*L S lM-utslM-uRS MATERIAL LA80R CouTRACT TOTAL MANNOURS FLEL STORAGE BLDG:
LOCATE CLEAu AND LOAD SEVEu.ET) 1 LS 168 $22.87 SO S3,842 13,842 168 TEMPORARY SUPPORT BEAMS MOVE TEMPORARY SUPPORT SEAMS TO 1 LS 112 $22.87 50 $2,561 12,561 112 OuttDim; AND SET CLEAu 35 TOu FICKER 1 t5 to 522.87 S0 1566 1366 16 RIC. SET & SE8:URE 35 Tom PICKER 1 LS 96 522.87 50 $2.196 52,196 % ROUTE PICKER ExunUST DISCuARGE 1 LS 8 122.87 50 S183 $183 8 REMOVE mou-ESSEmilAL FUEL RACKS 1 LS 144 S22.87 50 13.293 53,293 144 REMOVE 35 TON PICKER FROM BtDG 1 LS 64 522.87 50 51,464 64
- S1.464 REMovi PICKER EXuAUST DISCNARGE 1 LS 4 122.87 50 591 591 4 REMOVE TEMP. BEAMS FROM SLDC 1 LS 112 122.87 50 $2,561 $2,561 112 REMOVE uG4-ESOENTI AL TOOLS AMD 1 LS 16 122.87 SO S366 S366 16 EQU!PMCui ISOLATE FUEL STORAGE POOL 1 LS 16 522.87 50 1366 S~66 s 16 C00LluG FOR RECIRC MODE y ISOLATE mou-ESSEJTIAL AREAS OF 1 LS 43 S22.87 10 11,098 S1,098 48
- a. TuE SUILDluG Q PREVE2TATIVE MAluTEuAuCE FUEL 1 LS 120 S22.87 SO $2,744 12,744 120 MANDLtuG EQUIPMEuT tm
- CLEAu IUEL STORAW SUILDIuG 1 LS 200 522.87 SO S4,5 74 54,574 200 CLEAu fuel STORACE POOL 1 LS 96 122.67 50 $2,196 52,196 %
os T MISC. DIRECT MAI*L $1,395 11,395 fD E5% OF DIRECT LA80s) T-SUS-TOTAL DIRECTS $1,395 127,901 S29,296 3 10 1,220 -* f SMALL TOOLS & CouSUM. m 10 50 -v S< 3> luDIRECT LA80R: n c' E15% OF DIRECT LAa0R) SO S4,185 50 $4,185 183 2' uGNMANUAL N' SO SO SO SO O 5* sn u(ALT 4 PuTSICS TECuu!CIAus SO S0 SO SO O N Eu IhEEtthG: LJT UEEC 0 Mu 10 SO . Nuf 0 Mu SO SO p YAEC 0 Mu SO SO CouSULTAuf 0 Mu g g 50 50 LJ
CLIENT : NNY DESCRIPi':38 Of Want: PREPARATIra FOR OFF LOADING FUEL (POST LOW POWER TESTING) ESTIMATE NO.: 0-2 ruEL STORAGE BulLOING
.........-UNIT RATES------- SUS DESCRIPTION Cf'Y UN MAT *L 1 lM-NRSlM-NRS MATERIAL LABOR CONTRACT TOTAL MANNOURS 1
Sus-TOTAL St,395 132,087 SO S33,482 1,403 NONMANUAL TEE & ON SO 10 (NONMAN S + 30%)+15% E NGt hE Ea NG FEE & On 50 10 (tKEC ENGIN 1 30%).30% TQiAL Esi! MATE (MAE10URS ARE CRAff ONLY) l S1,395 132,087 SO S33,482 1
................................................ .......................................................................... 403 .......
DESCR!Pil0N
.......... UNIT CDST-------> j QUANill UN M41't S lM-NRSlM-NRS MA TE RI AL LABOR S08 0412 TOTAL MANNOURS 7
............................................. ...........................................................[......................
as SIDetARY OF COST: - 10TAL DIRECT COST S t.395 127,901 10 129,296 *j20ll , w e y TOTAL INDIRECT COST SO S4,155 10 54,,65 183 g
"4 tt TOTAL NONMANUAL SO SO SO SO T.
(INCLLCES FEE & ON) . 3_.
"3 TOTAL ENGINEERING SO 10 SO SO a,s (INCttOES GEE & OM) M TOTAL ESTIMAir St.395 S32,C87 SO S33,482 1403 3>
........................... ........ ............................. ......................................................... n, uSE l l l l l ll Si,4m l S32,im 10 133,5m 1403 7,,-
..............................-.................................................................l.........l.............l.l.......... ,
- fD ITEMS NOT REQUIRED IF PLAN AS$lMPTIONS DO PROVE 10 BE CONSERVATIVE in N
L21 e
i i Preliminary Activities / 5.1.4 PRELISilNARY ACTIVITIES ESTIN1 ATE B ACK-UP
- 1. LOCATE CLEAN AND LOAD 7 TENfPOR ARY CR ANE SUPPORT BEAN 1S Crew 5 hicchanics handling rigging and clean.,g beams I hicchanic operating 35 ton picker I hicchanie diiving truck Duration 3 days 7 men x 8 hrs / day / man x 3 days = 168 hrs
- 2. Af0VE TEStPOR ARY CR ANL' SUPPORT BE ASIS TO BUILDING AND SET Crew Same as item i Duration 2 days 7 me: x 8 hrs / day / man x 2 day t = 112 hrs
- 3. CLE AN 35 TON PICKER Crew 2 hicchanics Duration I day
. 2 men x 8 hrs / day / man x 1 day = 16 hr 8, RIG SET AND SECURE 35 TON PICKIR Crew 7 hicchanics handlitig and rigging picker I hiechanic . operating overhead crane Duration 1.5 days 8 men x 8 hrs / day / man x 1,5 days - 96 hrs Page 5 8
Preliminary Activities / 5.1. 4
- 5. ROUTE PICKER ENIIAUST DISCIIARGE Crew 2 Mechanics Duration 0.5 day 2 men x 8 hrs / day / man x 0.5 = 8 hrs
- 6. RI510VE NON ESSENTIAI. FUEL R ACKS Crew
, 5 hicchanics rigging and handling racks i Mechani: - operating picker 1 Mechani: - driving truck 1 Mechanic operating overhead crane 1 Mechanie - operating yard picker Duration 2 d.tys 9 men x 8 hrs / day! man x 2 days = 14/ hrs
- 7. RE510VE 35 TON PICKER FRO 5111UII. DING Crew Same as in item 4 Duration 1.0 day 8 men x 8 hrs / day / man x 1.0 days = 64 hrs
- 8. RE510VE ENII AUST DISCil ARGE Crew Same as in item 5 Duraton 0.25 day 2 men x 8 hrs / day / man x 0.25 day = 4 hrs Pue 5 9
Preliminary Activities / 5.1. 4 9. RE510VE TE51POR ARY CR ANE SUPPORT BF A515 FRO 51 BUILDING Crew Same as in Item i Duration 2 days 7 men x 8 hrs / day / man x 2 days = 112 hrs
- 10. RIS10VE NON ESSENTI AL TOOLS AND EOUIP51ENT Cre v 2 hicchanics - to remove non essential fuel handling tools and equipment in order to minimize contamination risk Duration 3 days 2 men x 8 hrs / day / man x l day = 16 hrs
- 11. 11QlATE FUEL STOR AGE POOL COOI.ING FOR Rl: CIRC 510DE Crew 2 hicchanics - to locate and perform necessary valve line ups and lock valves in required positions.
Datation i dc y 2 men x 8 hrs / day / man x ! day n 16 hrs
- 12. ISOLATE NON ESSENTIAL AREAS OF BUILDING Crew l
l 3 hiechanics - to locate and seal openings, doors and penetrations into non essential areas of the fuel building to prevent contamination. Duration 2 days l 3 men x 8 hrs / day / man x 2 days = 48 hrs l l t l l Page 5 - 10
Preliminary Activities / 5.1. 4
- 13. ERJYENTIVE $1AINTENANCE FUEL IIANDLING EOUIPNIENT Crew 5 hiechanics - to perform maintenance on fuel bridge, upender, etc.
Duration 3 days 5 inen x 8 hrs / day / man x 3 days = 120 hrs
- 14. CLE AN FUEL i1UILDING Crew 5 hicchanics - to scrub floor at elevation 23 and wipe walls DJrPtion 5 days 5 men x 8 trs/ day / man x 5 days = 200 hrs
- 15. CLEAN FUEL STOR AGE POOL Crew 3 hiechanics handling hoses I hiechanic operating hydrolaser Duration 3 days - including set up time and removal of washing equipment and inspections.
4 men x 8 hrs / day / man x 3 days = 96 hrs i l [ Page 5 11
Preliminary Activities / 5. 2.1 FUEL, STOR AGE BUILDING CONTROL CENTER PURPOSE: To establish a control center local to the fuel storage building for the purpose of housing the guard force and monitoring the fuel building functions in order to shut down the main control building and guard house. ASSUSIPTIONS:
- 1. Sufficient electrical capacity exists with Exeter & flampton Electric Company Feed.
- 2. Radiatiori Monitor Ciicuits Fire Detection Circuits, and Security can be routed to the local control center.
- 3. Fire water pump functions can be routed to the control center.
- 4. licating Ventilation, and Air Conditioning (liVAC) equipment function routed to *he control center.
- 5. Work performed single shift 8 hours per day.
- 6. Activation of local control panel does not occur until after issuance of possession only license.
DESCRIPTION OF ACTIVITIES Erect a trailer to house the necessary security personnel required to insure the protection of the fuel building as well as to house monitoring consoles to monitor system and building functions. Electrical circuits would be ' pulled through conduits and terminated at the status boards for the following: Radiation Monitors. IIVAC Fan and Filter Functions. Fuel Storage Pool Water Level and Temperature. Fuel Storage Pool Recire Pumps. f..e Detection. Fire Protection. Door Alarms. Page $ 12
Preliminary Activities / 5. 2.1 Power would be provided to the building by use of a temporary feed from the Exeter llampton Electric Company Feeder, located e.ast of the circulating water pump house, to the motor control center located at elevation 21 f t. 6 in, in the fuel storage buildi: g. Fire protection would be provided by use of the existing yard fire protection system located immediately south of the fuel building. Page 5 13
Preliminary Activities / 5. 2. 2 1 SCIIEDULE LOGIC , l' age 5 14
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-_________________J
_ - _ _ _ _ _ . . _ _ . _ _ m _ _ _. . m 4 Citimi : met DESCRIPTION Cf WOSC: FUEL STORAGE BUILCinG CCMTROL CENTER (POST LOW PCtJER TESTimG) ESTIMATE m0.3 D-3
............................_.............................................................................................s...
4 m ..... DESCRIPTION QT'T UN
. . .. . . . . . .Uu s i R A T E S - - - - - - -
MAI'L 1 lM-MRSlM-NRS MATERIAL LABOR SC3 CouTRACT TOTA l' MAmMOUR5 1
................. ........................ ......................................................................L..... .........
FUEL SLDG CouTROL CENTER SET UP 12E60 FT TRAttER 1 LS T20 S'2.87 10 12,744 52,744 120 Mou!TORinG ConsotES (ALLOW) 1 LS 12,500 24 122.87 S2,500 S'49 S3,049 24 lusTALL ELECT RACIWAT FROM FtEL 1 LS 560 $22.87 10 s12,807 112,807 560 STORACE 5tDC TO TRAltER, 7 560 LF OF 2* "OmDUIT KILL & TERM MONITOR!aG CASLES 1 LS 340 $22.87 50 57,776 57,776 340 i TEST SYSTEM 1 L5 72 S22.87 50 $1,647 S1,647 72 Im5TAtt POWER FEED RAPEWAY 1 LS 300 S22.87 SO 56,861 56,861 300 EECAVATE & BACKFILL TRENCu 750 LF CF 4" CONouti PULL & TERMIuATE POWER CA3tf 1 LS 64 522.87 SO $1,464 S1,464 satAg PERMAmEuf TIES OF POWER 64 1 LS 40 S?2.87 SO 5915 5915 40 Amo IEC 5 MISC. DIRECT MAT'L S1,738 51,738 es F3 (51 OF DIRECT LABOR) i SUS-TOTAL DIRECTS S4,238 534,762 S39,001 i 1 9e SO 1,520 SMatt TOOLS & Constm. 50 10
-a I
,T
; tacIRECT LAa0R. m (15% OF DIRECT LA808) S5,214 1
SO SO S5,214 228 g m0mmAmUAL 10 SO 50 SO O 3 1 as MEALYN PuYSICS TECau!CIAm5 SO SO SO e SO O *< 3> EmGimEERimG: ] UEEC 0 Mu SO SO h . unY 0 mm SO g So ; -. 7AEC 0 j ConsutTAsT 0 mm SO SO ' C MN 10 SO m s SUS-TOTAL S4,238 139,977 50 544,215 1, 748 g monMAmuAL FEE & 04 10 So (Maasene S + 30%F151 m ENG!bEERImG FEE & On l SO SG M l (LEEC INGlu S +30%)*30% g - l t
CLif ti : not DESCRIPilou CF WORat: FUEL STORAGE SUILOla? COu!BOL CEh!ER (POST LOW POWER TESTING) ESTIMTE mO.: 0-3 m .......uugg RaggS_...... SUB l DESCRIPI!ON IQi .... UN
......'T .
mal'L S lM-NRSlM-h4S MAIERIAL LABOR CONTRACT l TOTAL
. ........................................ .......................... m ..........
MAuMoues TOTAL ESigmATE (manuGURS ARE CRAf f OutT) 54,238 139,971 10 S44,215 1, 748
..................................- ..........................................................................................i ......
m . .....Unli CUST-------> DESCRIPTION QUAmilT UN Met *L S lM-ht$lP'-MRS MATERIAL LABOR StS CNIRC TOTAL MANNGJRS
............. - .................... m ......m......... m m ...... m .......... m ........ m .... m .. m .. m ... m ....... m ..
Supue4RT OF COST: (j l TGTAL DIRECT COST S4,238 S14,762 50 539,001 1,520 TOTAL InCIRECT COST So $5,284 SO 15.214 223 j -c tciti ioumAquAL SO $3 S0 10
- (ImCLUDES FEE & Ou) g
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, (ImCLts0E! FEE & Ou) 1 =
j q TotAt ESiinATE i u,25a 559,977 SO
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Preliminary Activities / 5. 2. 4 FUEL STOR AGE BUILDING CONTROL CENTER ESTISTATE B ACE-UP
- 1. SET UP 12 X 60 FT. TR AILFR Crew 5 Mechanics to block and lev:1 trailer. Install skirting and stairs Duration 3 days 5 men x 8 hrs / day / man x 3 days - 120 hrs
- 2. INSTALL SiONITORING CONSOLES Crew 3 Mechanics to install and anchor consoles 3 men x 8 hrs / day / man x ! day - 24 hrs l
- 3. INSTALL R ACEWAY FROS1 FUEL STOR AGE TO TR AILER AND CONSOLE Crew 6 Niechanics to install cable tray 8 2 in conduits at 1.00 mhs/ft x 70 ft/ea = 560 hrs Duration 12 days
- 4. PULL AND TERS1510NITORING CABLES Crew 6 Mechanics Pull Allow 20 circuits @ 100 if/cire x 0.09 mhs/f t = 180 hrs Term Allow 8 conductors for circuit x 0.50 mhs/cm = 160 hrs 340 hrs Duration 7 days
- 5. TEST SYSTES_I Crew 3 Instruinent & Control Techniciar.s to check circuits, terms and calibrate instrumeritation Duration 3 days 3 men x 8 hrs / man / day x 3 days = 72 hrs Page 5 19
Preliminary Activities / 5. 2. 4
- 6. INSTAL,I. POWER FEED CONDUIT Excavation 750 if 3 f t. deep x .10 mhs/cy = 25 hrs Conduit 750 if 4 in. RGS x .3 mhs/f t = 225 hrs Backfill 6750 cf/27 = 250 cy x .20 mhs/cy = 50 hrs Total 300 hrs Crew 3 hicchanics install conduit I hicchanic operate back hoc
- 1. hfechanic grade and compact 5 hien Duration 8 days
- 7. ML POWER FEED 3/C 500 mem cable Crew 5 hiechanics pull cable 3 hicchanics term Duration 8 hrs Pull Duration 8 hrs Terms 5 men x b hrs / day / man x I day - 40 hrs 3 men x 8 hrs / day / man x 1 day = 21 hrs 64 hrs
- 8. BRAKE PERh1ANENT TIES OF POWER. INSTRUNtENTATION AND CONTROL Crew 5 hicchanics Duration I day 5 men x 8 hrs / day / man x 1 day = 40 hrs i
Pace 5 20
Preliminary Activities / 5. 3.1 PRELIMINARY ACTIVITIES INSUL ATION R EMOV AL PURPOSE: Removal of insulation from the building to allow external radiation surveys of piping systems. ASSUMPTIONS:
- 1. Insulation and lagging are not contaminated
- 2. Insulation removal can take place during other activities.
- 3. Insulation can be removed from systems and equipment at approximately 25% of the manhours required for installation.
DESCRIPTION OF ACTIVITIEE ' To provide Health Physics personnel the ability to survey external piping and equipment surfaces while performing surveys of the containment, primary auxiliary building, equipment vault and waste process building, thermal insulation and tagging must be removed. This activity will require that it be done in a logical manner in order to lessen the impact to the overall scheme. The containment will be done first followed by the Primary Auxiliary Building (PAD), equipment vault and finally the waste process building. As insulation is removed, it will be ! surveyed and released for unrestricted use. It will be removed from the buildings in order to prevent accidental contamination from decontamination activities, t Page 5 21
Preliminary Activities 5. 3. 2 SCIIEDULE LOGIC See Decontamination Project / 7.2 l l l l i l i l l t I i l Page 5 22
Preliminary Activities / 5. 3. 3 J COST ESTIMATE i I ! I I l i, i i t I r t i 6 i h Page 5 - 23
CLIEuf : mwY DESCRIPTION Of WDRE: luSIAAi!OM 2Emov4L (POST L0lJ POWER TESilmC2 ESTI MTE No.: D-7
<<<....... UNIT RAIES------- l SUB CESCRIPi!04 IQT'T Um MT't S lm-pts lm-h25 MATERIAL l LABOR CoutRACT TOTAL MANMCURS ConfAlmutui inSULATIou 1 LS 3,227 522.87 50 573,801 573.801 3227 pas & VAULT INSULATIou 1 LS 3,323 522.87 50 175,997 175,997 3323 WASTE PROCESS INSULATION 1 LS 4.623 522.87 SO S105,728 1105,723 4623 i
MISC. DIaECT mAf*L $12,776 512.776 (51 0F DIRECT LA80R) SUS-f0TAL DIRTCT* S12.776 1255,527 SO S268,303 11,173 SMALL TOOLS & ConSun. 50 10 mE InottfCT LA80R: Q (1510F DIRECT LA80R) SO S38,329 SO S38,329 1,676 'Je nommeauAL SO SO SO SO O N ufALTN PMYSICS TECNulCIANS 50 SO SO 10 0
*U E NGIDE E RING- ~*
UEst 0 mn S0 SO muY 0 MN 50 S7 , TAEC 0 mm 50 SO 3 ConSULTAmT 0 mm SO SO SI s St4-Tot AL 112,776 5293,855 SO S306,632 12,849 waamaast*L FEE & On 50 50 O (mommas S . 30%)*15% .". EhGibEERING FEE & ou 50 50 * (UESC Enclu S .3C1)*30% E en TOTAL Esilm4TE (memnouRS ARE CRAff Outv) S12,776 $293,855 SO S306,632 12,849 N
CLIENT : NNY DESCRIPf80N OF WORC: INSULAllON Rest. vat (POST LOW POWER TESTING) ES!!nATE No. 0-7 SUS u<-------UNITRATES-------l l l DESCRIPTION QT UN MAT *L S lM-MR$lMWRSl MATERIAL LABOR CONTRACT l TOTAL MANNOURS l
............................ ......'T........................................... ................................................. j SupunARY OF COST:
)
i total DIRECT COST S12,776 1255,527 SO S26s,303 11,173 l l TOTAL Inc1 RECT COST SO 118.329 SO 'd,329 1,676 TOTAL nan a mat SO SO SO SO (INCLtOES FEE & ON) TOTAL ENGINEERING SO SO SO SO (INCLtJDES FEE & CW) total ESTIMATE S12,776 $293,E55 10 S306,632 12849 uSE 12s49 g
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Preliminary Activities 5. 3. 4 , PRELIS11NART 3CTIVITIES / INSULATION RE510 VAL ESTIhf ATE B ACK-UP
- 1. CONTAINNIENT Piping Systems = 1312 hrs Equipment = 1915 hrs 3227 hrs Crew 10 hicchani;s 6 Utility Technicians Duration 25 days
- 2. PAB AND V AULT Piping Systems = 2894 hrs Equipment = 429 hrs 3323 hrs Crew 8 htechanics 4 Utility Technicist s Duration 35 days
- 3. WASTE ERQfyS BUILDING Piping Systems = 3$05 hrs Equipment = 1118 hrs 4623 hrs Crew 8 hicchanics 4 Utility Technicians Duration 50 days Page 5 - 26
_ FUEL UNLOADING _ TABLE OF CONTENTS SECTION DESCRIPTION PAGE= 6.1 Fuel Unloadine 6-1 6.2 Schedule Logic 6-3 6.3 Co s t .".- este / D 4 6-5 6.4 Estimate Back up 6-8
Fuel Unloading / 6.1 MIN LO A DING P U R POSE: Remove fuel from reactor vessel and store in fuel storage building. A SSif M PTIONS:
- 1. The reactor is initially shut down in mode 5.
- 2. All fuel assemblies and their associated core components, control rods, burnable poison assemblics, source ,
assemblics and thimble plugs will be off loaded directly to the fuel storage pool. i
- 3. Fuel unloading is performed three shifts five days per week.
DESCRIPTION OF ACTI\*ITIES Fuel unloading will be conducted in a manner similar to that of a typical refueling in a pressurized water reactor. The major activities associated with fuel off load are reactor vessel disassembly, reactor cavity fill, fuel storage pool fill and removal of fuel from the reactor vessel. Reactor vessel disasse.nbly is the most complex of the evolutions necessary to off load the coie. The first step in the process is to perform preventive maiatenance on the polar crane, which is used to remove the reactor vessel head and ot' , wt equipment.
, The next sc% . .
< cps involves disconnecting or removal of support equipment ussocia -4 with the reactor vessel such that the reactor head may be removed. These 9ctivities include:
Removal of control rod drive mechanism cooling fins and associated ductwork. Disconnecting power and control cable associated with the control rod drive mechanisms and control rod position indication system. Removal of reactor vessel head insulation. Retracting incore instrumentation assemblics and installation of low pressure seals. Page 6 1
o Fuel Unloading / 6,1
- Detensioning anri rernoval of the reactor vessel studs.
Installation of the reactor cavity refueling sest ring and stud l hole plugs. ( Once the above setivities are completed the reactor vessel head is removed ' from the reactor and placed on its storage stand. As the reactor vessel head is lifted, the reactor cavity is slowly filled from the refucting water storage tank. T he last two major steps in vessel disassembly involve disconnecting t' e control rod drive shafts and removal of the upper internals packtge. Once the upper internals are removed and preventive maintenance on the refueling machine and upender is complete the resstor vessel is ready for fuel removal. Before any fuel is moved, the fuel storage pool must be filled. The fuel storage pool requires tM.000 gallons of 2000 ppm borated water. The fuel I storage pool must rer.,t it, dry until removal of the fuel storage racks and new fuel elevator is complete. Since the activities in the fuel storage ' building are expected to take longer than vessel disassembly the refueling
, water storage tank will be refilled with the water required to fill the fuel storare pool after the initial contents of the refueling water storage tank j have been used to fill the reactor cavity. The boric acid batching process at Scabrook is the limiting factor with respect to filling the fuel storage l pool. It is estimated it will take about 15 days to manufacture enough l borated watet.
Once the reactor. vessel acd fuel storage paol are ready, fuel unloading may begin. The unloading process in.alves the removal of a fuel asse nbly and its associated compocents from the reactor vessel using the refueling , machine. Once removed from the reactor vessel, the fuel assembly is placed in the upender and is then transferred to the fuel storage building. In the fuel storage building, the fuel storage bridge crane transfers the fuel assembly from the upender to its storage locatien in the fuel storage racks. r
! This process is repeated until all 193 fuel memblics are removed from the a
res.ctor vessel. During the core off loading process all applicable count ' rate monitoring and special nuclear material inventory requirements will be me t. Once the off load is complete the contents of the fuel storage pool will be inventoried to verify the location and identity of each fuel assembly and its associated core component. At this point in the process, fuel unloadir:g is complete and reactor ve*sel
>nd systcm decontamination would begin.
i i Page 6 - 2 e -. ._____.,,__-__.__,c , __ __-- -
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Fuel Unloading / 6. 2 SCIIEDULE LOGIC 1 J i . 4 4 Page 0 - 3
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_= _ - - . - - I Ctstut : maf DESCaIPTION OF Wuen DEMOVE FUEL FDOM REACTOR (POST LW PNEE if SiiuG) ESTIstatt uO.s 0-4
........................................................a.......................................................
s e.-~- ---tas t i R A T E S----- -- sus OESCRIPTION IGT'T Um st4T'L S lM-utslm-usS MATERIAL LA808 "X)mTRACT T0 fat l
...................................................................................................3.Maunouns l
CONTAIMMEmi SLDG: Remove mou-ESSENTIAL TOOLS Amo 1 LS S0.00 140 122.87 SO 13,202 S3,202 140 SUPP0 aft ist FUEL #ANDLluG EQUIPeIEuf AND 1 L5 S0.00 120 $22.87 SO S2,744 52,744 120 POLAR CRAeG DIStonutCT ComiROL ROD drive 1 gLS S0.00 72 S22.87 10 S1,647 S1,647 72 CASLES REmovt Comis0L 300 Delve 1 L5 S0.00 576 S22.87 50 S13,173 S13,173 5 76 00CfWORE mEmovE n!S$3tt SulELO 1 L5 S0.00 64 122.87 SO S1,464 $1,464 64
#EMOVE ufutacu SulELDS 1 LS S0.00 64 S22.87 $0 St 444 51,464 64 eEmovE FLANGE Insut4TIou 1 LS S0.00 64 S22.87 SO S1,464 51,464 64 lustALL SEAL RING 1 L5 S0.00 120 S22.87 SC S2.744 S2,744 120 DETEusION AND #EmovE Sites 1 L5 S0.00 768 S22.87 SO S17,.*64 S17,564 T68 -
mEMOVE NEAD AuD PLACE Ou stamp, 1 L5 S0.00 288 $22.87 SO 56,587 S6,587 288 FILL POOL 5 DI5ComuECT a0DS,etmovE UPPER 1 L5 S0.00l 288 S22.87 SO 56,53T 56,587 238 as ImiERNALS Q aEMOVE FUEL ASSEMSLIES 1 LS S0.00 720 $22.87 SO I S16,466 516,466 720 InvEmioar EuEL 1 ts 90.00 48 522.87 So S1,C98 S1,098 48 m o > . 4C. DIRECT staf't S3,810 S3,810 (5S OF DIRECT LASOE) SUS-TOTAL DIRECis S3,410 ST6,203 SO $80,013 3,332 smALL TOOL 5 & CDustse. SO SO "Tl luGIRECT LAeos: (151 0F DIRECT LAeos) #D 50 S11.430 SJ S11,430 500 - esammAmuAL SO SO SO SO O C 3 alEAttu PuYSICS TEcumICIAus SO SO SO SO O o. EssGluEER!aG: O UESC 0 sus SO SO E sur 0 esu SO SO g TAEC 0 seu SO 90 Cou5ULTAuf 0 asu SO S0 CD Sus total S3,810 l SST,633 l SO 991,443 3.832
Ctitui : huf DESCatPitom OF W)et: #EMOWE FUEL F90M #EACTOR (505T LOW POWS TEST 8mG) ESTIMATE 20.3 D-4
........ .....u.............. ........
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..........uult eATES------- SUS DESCRIPfl0N Of'i um MAf*L $ l m-surS m-he S MATEtlAL LASOR ComithCT
.................. ..........................................l.......... ......................................OIAL T senmuGUR$
40mmAmust FEE & On SO SO (moumae S
- 3033*151 EmClutERlhG FEE & ON 10 50
, (tE&C Encis S .301)*30%
TOTAL EsilmATE (mammoues A#E Ca4f f onLY) S3,810 587 50 S91,443 3,832
..... ................ .. . ..................................................... 633................s........................
g ...,....u.. eft M GUAuftilum.........UNITCOST-------> 9taf'L S l m-mes l m-me $ MATERIAL LASO4 $US-CultC TOTAL 9enmuGUR5 so supMAst *. C05ft en a TOTAL cI2ECT Cost $3,810 576,203 S0 $80,013 3,Y32 e
~s TOTAL tuDIRECT COST SO S11,430 S0 Sil.430 500 TOTAL mrmanaamaan SO SO SO SO (It.CLUDES FEE & OW) 10tAL Eucluf EtimG SO SO SO SO is (ImCLts)is FEE & 05) c
.it 10iat Esfin4TE $3,810 S87 SO 591,.43
.... ................... ......... ........ .. ......................... ...........,633
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Fuel Unloading / 6. 4 ESTIMATE B ACEUf.
- 1. REMOVE NONESSENTI AL TOOLS AND S11PPOR.T.
Crew 3 Mechanics to rig cut and handling tools and supports 1 Mechsnic to operate polar crane Durations - Install staging I d.ty Remove fixtures and supports 2.0 (sys Remove staging I/2 day 4 men x 8 hrs / day / man x 3.5 days = 112 hrs Radiation Access Control Impact 25% = 21 hrs 140 hrs
- 2. PM FUEL II ANDLING EOUIPMENT & POLAR CR ANE Crew 5 Mechanics Duration 3 days 5 men x 8 hrs / day / man x 3 days = 120 hrs
- 3. DISCONNECT CONTROL ROD DRIVE CABLES Crew I 3 Mechanics
!. Duration I day = 3 shifts i
3 men x 3 hrs / shift / man x 3 shifts = 72 hrs
- 4. REMOVE CONTROL ROD DRIVE DUCTWORK Crew 7 Mechanics disconnect ductwork rigging, storing 1 Mechanic operating polar crane Duration 3 days x 3 shifts = 9 shifts 8 men x 8 hrs / shift / man x 9 shifts = 576 hrs s
Page 6 8
Fuel Utiloading / 6,4
- 5. RENIOVE StISSILE SillELD Crew 7 Mechanics - rigging [
l Mechanic - operator ! Duration I shift 8 men x 8 hrs / shift / man x ! shift = 64 hrs
~
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- 6. RES10VE NElfTRON SIIIELDS Crew 7 Mechanics - rigging 1 Mechanic - operator Duration I shift 8 men x 8 hrs /shif t/ man x i shift = 64 hrs
- 7. WE510VE FL ANGE INStf L ATION Crew 7 Mechanics rigging 1 Mechanic - opera tor
! Duration I shift 8 men x 8 hrs / shift / man .v. I shift = 64 hrs J e
- 3. INSEALL SEAL RING l Crew 4 Mechanics install gaskets., clean and rig, remove storage stand 1 Mechanic - operate polar crane Duration 3 shifts j 5 men x 8 hrs / shift / man x 3 shifts = 120 hrs i
l l Page 6 9
i Fuel Unloading / 6. 4 ! l
- 9. DETENTION AND RDf0VE STUDS Crew 7 hiechanics operating tensioners. hoist. handling studs I hicchanic operating polar crane -
Duration 4 <*' s s 3 shif ts = 12 shif ts " 8 men x ,, hrs / man / shift x 12 shifts = 768 hrs ,
- 10. RD10VE IIEAD PLACE ON STAND AND FILL POOL Crew 5 hicchanics rigging and standing by I hicchanic operating polar crane Duration 2 days x 3 shifts / day = 6 shifts r 6 men x 8 hrs / shift /raan x 6 shifts = 288 hrs r
- 11. DISCONNECT RODS REhf0VE UPPER INTERN ALS Crew 5 hiechanics / Operators - rigging and disconnecting rods I hiechanic operating polar crane Duration 2 days x 3 shifts / day = 6 shifts 6 men x 8 hrs / shift / man x 6 shifts = 288 hrs i 12. RD10VE FUEL ASSEhfBLIES I .
- Crew I
5 Operators operat', fuel bandling equipment i Technician Duration 5 days 3 shifts / day = 15 shifts 6 men x 8 hrs / man / shift x 15 shifts s, 720 hrs Page 6 - 10
i 4 Fuel Unloading / 6. 4
- 13. INVENTORY FUEL !
Crew . 2 Men Duration i day x 3 shifts / day = 3 shifts r 2 men x 8 hrs / shift /msn x 3 shifts - 48 hrs l l
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I Page 6 11
i DECONTAMINATION OPERATIONS 1 TABLE OF CONTENTS SECTION DESCRIPTION PAGEa ! I l 7.1 Decontamination Operationg 7 I 7.2 Schedule Logic 7- 5 l 7.3 Cost Estimate / D 6 7 7 7.4 Estimate Back up 7 11 7.5 Attachment I 7 21 I i I I i l l t r .
t. i Decontamination Operations / 7.1 i DECONTA\llNATION OPER ATIONS Pl* R POS D Decontamination, if necessary, of the plant piping and i ductwork systems potentially contaminated by the passage of l fluids during the low power testing program, i ASSU\fPTIONM ' t
- 1. Buildings and equipment cubicles are not contaminated .
during system decontamination. i t
- 2. Auxiliary boiler system will be operational in order to provide steam to the Boron Recovery System (BRS). *
! 3. Single shift operation five days per week.
4 Decontamination flushes equal three velocity flushes of a piping system at twice its volume cach time. '
- 5. liigh Energy Particulate Absorption (HEPA)
, filters pe, form as designed and no radioactive contarnination occurs downstream of the filter, a
- 6. Proof flush equals a selocity flush of a piping system at twice its volume.
All systems have been drained, excluding reactor coolant l system.
- 8. Boron Recovery System tanks are empty prior to decontamination, j
!' DESCRIPTION OF ACTIVITIFS l It is unlikely that significant amounts of long lived radioactivity will exist outside the reactor vessel, process systems, demir. ralizers and filters. This conclusion resulted from the evaluation of reactor cdant radioactivity and plant radiation and contamination surveys performed during and shortly ! after low power test at five recent vintage nuclear power plants. (See Attachment I section 7.5) Typical reactor coolant radioisotopes have less [ than 24 hour half lives and would easily decay to non detectable levels within a oric to two weeks after shutdown. However, for the purpose of 1 conservative decontaminatiori efforts, it is assumed that the reactor coolant i system and auxiliary process systems along with soine of the plant's Nir l handling systems will contain some activity whi:h will require
- decontamination prior to unrestricted release.
- Page 7 - 1
\ _
4 Decontamination Operations / 7.1 Upon review of Technical Specifiestion requirements and the low power testing program the following systems may require monitoring and decontamination,if necessary, based on our conservative assumptions: DRS - Doron recovery system Call- Containment mir handling CS - Chemical and volume control RC - Reactor coolant Ril - Residual hest removal SS - Sample system VG - Vent gas WG - Waste gas WL - Waste liquids WLD - Waste liquid drains in addition the following systems may require monitoring and decon-tamination, if necessary, as the result of the off loading of the fuel: Fall- Fuel building air handling Refuel cavity (containment) j Reactor building fuel handling equipment i FS - Fuel storage pool and racks i Fuel sturage handling equipment The following systems will require surveys to insure unrestricted release even though the potenti:1 for contamination is unlikely: I CAP - Containment air purge 4 CBS - Containment building spray i COP - Containment on line purge 1 EAll- Equipment vault air handling Pall- Primary auxiliary building air handling Rhl - Radiation hionitors SI - Safety injection l Wall - Waste process building air handling RCA - Radiologically Controlled Areas Decontamination will start with the processing of the water contained in the reactor cavity for t purpose of off loading the fuel from the reactor vessel. Decontamination of the water will occur by pumping the water down using the FS system pumps and discharging to the letdown system demineralizers for the removal of any contamination. The effluent from the letdown system will be transferred to the boron recovery system (BRS) tanks for processing through the BRS evaporators in order to remove boron, when, upon schieving satisfactory levels, it will be discharged in accordance with approved procedures and Environmen'al Protection Agency (EPA) requirements. Page 7 - 2
Decontamination Operations / 7,1 l l Upon draining, the refueling cavity will be rinsed using hydroters along
- with the upper and lower internals of the reactor as they are removed in i order to use the vessel itse;f as a sump for decontaminating flushes '
performed on the primary plant systems: CS, RH and RC. In order to perform these flushes, pump internals and relief and check valve internsis will be removed along with bypassing system filters and vessels. Components removed from these systems as well as filter housings and vessels will be cleaned utilizing conventional decontamination methods of hydroissing and/or hand wiping. The RHR pumps will be utilized as the vehicle for establishing the velocity necessary to schieve the three potable water flushes and one proof flush required to remove contamination. The refueling water storage tank will be the source. ' Decontamination,if necessary, of the primary side of the steam generators, reactor coolant loops and pumps will not be schievsble by the aforementioned flushes. Therefore, these components will be decontaminated by convendonal methods of water lansing the steam generator tubes and hydroissing and hand wiping the reactor coolant pump internals and reactor coolant loops. Again wash water will flow to the resctor vessel. All water flushed to the vessel will be transferred by temporary pumps and piping to the BRS tanks for storage and processing by portable mixed bed demineralizers to acceptable levels and discharged under approved procedures. With successful decontamination of the primary plant piping systems the VG and WG systems will be flushed from the containment back to the WLD system sumps or the BRS tanks 66 A & B utilizing temporary flushing pumps. With completion of VG decontamination, the WLD system will be flushed utilizing existing sump pamps and fire noses as water sources. This effort will be done building by building with flush water being contained in the waste liquid tanks then transferred by waste liquid pumps and filters to the port51e mixed bed demineralizers and processef to acceptable limits for discharge. Upon processing decontamination water from the BRS tanks and WLD tanks to low enough levels, the final piping runs will be ilushed to acceptable levels, the remaining flush water processed, and the pumps and tanke decontaminatiJn if necessary. Simultaneous with the flushing of the piping systems, the systems previously listed will be surveyed and released for unrestricted use along with each building in the radiation access control area of the plant witt. the exception of the containment and fuel storage building. These buildings will be surveyed and released for unrestricted use upon successful completion of the removal of the reactor vessel and fuel. 4 Page 7 - 3
Decontamination Operations / 7.1 Air handling systems will be surveyed and,if necessary, decontam!nsted after all other activities other than final building acceptanc. are completed , in order to maintain building environments. Ductwork. If required, will be decontaminated by hand wiping. IIEPA and charcoal filter media will be removed from filter housingt and, if necessary, placed in DOT approved low level weste shipping containers for shipment and divposal. Upon completion of media removal cach filter compartment will be hand wiped for l
! decontamination.
The removal of contaminated demineralizer resin beds, ilEPA and charcoal filters could generate the following volumes of low level waste to be dispesed of offsite at a licensed low level waste site. Mit\tES IN CUBIC FEET i 1 SYSTE\1 DEN 11Nf'R ALIZER I1EDS ff LTER SIEDI A Cil A R CO A L IIEPA L BRS -- 3.00 -- - I CS 60.0 5.05 -- - SF 75.0 1.43 -- - i WG -~~ 0.20 212.0 -
, wL .- 2,13 . .- -
Call l -- --- 22.0 24.0 , 2 Pall ~~ -- 756.0 240.0 ' TOTA LS 135.0 11.g3 990.0 264.0 } i l L l l l i r I t ! i i l i i Page 7 - 4
i l Decontamination Operations / 7. 2 i t J I SCIIEDUI.E LOGIC I l I i J 1 l t 1 l 9 I i l l Page 7 5
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CLIEmi s ma' ! DESCRIP180s of WODE: MCEnfansoA130s optaATION (POSI L*JW POda TESTtu;) ESi! MATE m0.s D-6
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Il DRAls futt STORAGE POOL 1 15 192 S22.87 SO A4.371 S4,391 192
- R3W%E FUEL STODA ;E POOL 1 LS 96 $22.87 SO S2,196 12,196 96 INSTALL TEseP0aAaf Ptser In 1 ts 32 122.87 10 5732 ST32 32
#EACTOR 4 55EL
- In5iatt TEMPEwAar PJPsy, TO 1 LS 5 76 S22.87 SO S13,173 S13,173 576 C5 DEmimEmat:2Ets CometETE PIPimG TO 8851 1 11 576 S22.87 SO S13,173 S13,171 5 76 DaAlu 8C5 At0 WESSEL 1 ts 32 S22.8T SO ST32 1732 32 PeOCf 55 4 4TER 4e0 Dealm susf 1 15 320 122.8T S0 ST,318 17.318 320 eEMOVE CmECK vetyt Amo RELIEF 1 ts 214 122.*,7 SO S4,8X S4,894 214 WALVE Imitemats PERFC9st WALVC List UPS TO 1 LS 448 522.87 SO S10,246 110,246 448 STPASS fil!Ets,WESSEts,PtsqPS lh5f Att DAa5 IW DOT & COLD LEG 5 1 15 512 S22.87 10 S11,709 511,709 512
- fluiu #C,pme,AND CS
) 1 LS 640 S22.87 SO S14,637 S14,637 640 DEcom WE55EL5 fittEa5 Amo PtsqPS 1 ts 3,200 S22.87 SO ST3,184 S T3,184 3200 RP',8C Aa0 C5
#E cWE Pe0C'.55 Insisumf uf ATI0m 1 LS 1,200 $22.87 SO S27,444 527,444 1200 F3 iROM SYSTEMS Em0VE WALWC INTER-ALS, CUT LOW 1 L5 5,785 S22.87 SO S132,303 5132,303 5785 Q -J PO!ui Of PIPE FOR SURWEYS it * #Em0VE Dans Is NOT & COLO LEGS 1 15 64 S22.87 SO S1,464 S1,464 64 O
- 0 DEComiARImATE STEAM GEnteAices 1 LS 1,280 122.8T SO $29,274 529,274 1280 etn0VE MACTOR PtseP InitenALS DECou MACTOR CE.2* A4T LOOP 1
1 ts ts 560 640 522.37
$22.87 SO
$9 S12,507 514,637 S12,807 S14,637 560 640 3
as PIPING Amo Ptr+ S0WL5 3 Deals WSSEL 1 LS to S22.87 SO S366 5366 to :f.
* #EMOVE Pump Ae TEMP 0esaf PIPE 1 ts 96 S22.8T SO S2,196 52,196 % 3 IN Couialmstui etm0WE Meta!a0ER Of TEMP PIPimG l LS 384 522.87 SC $8,182 S8,782 384 DECON WG SYSTEat PIPleG 1 LS 512 522.87 So S11,709 S11,709 512 DEcou WG STsiin W55ELS 1 ts 9'O $72.87 10 S21,955 $21,955 960 ' $
rem 0VE vatWE tu1EstAt5 As CUT 1 L5 1,684 122.87 SO S38,513 S38,513 1684 O LOW POINT PIPImG,WERIFF V CLEA4LINE55 88 DECou WLO Stamp Aac PtseP 1 L5 1,152 S22.87 50 S26,346 126,346 1152 as
), C, FLU 54 WLD PIPimG SunP TO faeK5 1 LS 1,152 122.87 SO S26,346 $2C,346 1152 atmoWE WAtWE5 Aa0 LOW P)!af 1 LS 4,307 S22.87 SO 598,501 $98,501 4307 O PIPING TO WEstff CLEAntimE55 3
- CLEAm WL TA=ms ped piser #
1 ts 320 S22.87 $0 57,318 ST,318 320 j fluss ses PIPE 1 ts 256 S22.8T SO 55,855 SS,855 256
- g CLEAe ses faerrs.fitites & PtsePS 1 LS 1,920 S22.87 SO S43,910 543,910 1978 I MMOVE WALWE Imitemals Aa0 CUT 1 L5 3,153 522.87 SO ST2,109 ST2,109 3th y LOW Poluf P8P3mG,WERIff CLEAmtImE55 N
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Decontamination Operations / 7 4 DECONTA%11 NATION OPER ATIONS ESTISIATE B ACK-UP
- 1. DR AIN REFUEL POOL +
Crew
- Mechanics to perform valve lineup and oversee draining Duration 12 days men x 8 hrs / day /msn x 10 days = 192 hrs
- 2. RINSE REFUEL POOL
! Crew 4 Mechanics to rinse refuel pool with hydrolaser Datstion 3 days 4 men x 8 hrs / day / man x 3 days = 96 hrs
- 3. INSTALL TESIPOR ARY PUhlP REACTOR VESSEL Crew 4 Mechanics to set pump, install controls and hook up power Duration I day 4 men x 8 hrs / day /msn x 1 days = 32 hrs
- 4. INSTALL TEhlPOR ARY PIPING TO CS DESilNER ALIZERS Crew 8 Mechanics Duration 9 drys 8 men x 8 hrs / day /msn x 9 day = 576 hrs lieme nei required it Plan assumps.ons de prove to be conservative Page 7 - 11
Decontamination Operations / 7. 4
- 5. CONIPLETE TEN 1POR ARY PIPING TO BRST Crew 8 hicchanics Duration 9 days 8 men x 8 hrs / day / man x 9 days = 576 hrs
- 6. DR AIN RCS AND VESSEL.
Crew 4 hicchanics to handle valve lineups,look for leaks, temporary riping, etc. Duration 4 days 4 men x 8 hrs / man / day x 1 day = 32 hrs
- 7. PROCESS WATER AND DR AIN BRST
) Crew 2 htechanics to valve lineups and stand by j Duration 20 days 2 men x 8 hrs / day / man x 20 day = 320 hrs I
- 8. REStOVE CllECK V ALVE AND RELIEF VALVE INTERN ALS CS RC RH TOTAL UNIT RATE IIRS
. 21/2 to 4' Valves 28 7 - 35 3.5 hrs 123 6 to.8' Valves 3 6 10 19 4.8 hrs 91 10 to 14' Valves -- - - - -
14 and Up . - - .- - - -- 214 hrs Crew 4 hicchanics Duration 7 days i e J Page 7 12
r Decontamination Operations / 7,4
- 9. PERFOR51 Y ALVE LINEUPS TO BYPASS FILTERS. VESSELS. PUSIPS Crew 8 hicchanics Duration 7 days 8 men x 8 hrs / day / man x 7 days = 448 hrs
- 10, INSTALL D A%1S llOT AND COLD LEGS Crew 8 hicchanics Duration 8 days 8 men x 8 hrs / day / man x 8 days = 512 hrs
- 11. FLUSil RC. RilR AND CS Crew 4 hicchanics Duration 20 days 4 men x 8 hrs / man / day x 20 days = 640 hrs
- 12. DECONTA511N ATE VESSEL FILTERS AND PU51PS RilR. RC AND CS Crew 20 htechanics remove resins, place in shipping containers, remove filter cartridges, disassembic pumps and decontaminate valve components, vessels and filters Duration 20 days 20 men x 8 hrs / day / man x 20 days = 3200 hr Page 7 13
Decontamination Operations / 7. 4 <
- 13. RESIOVE PROCESS INSTRUSIENTATION FROSI SYSTESIS i
Crew 6 Instrument & Control Technicians to tag out cables lif t from terms in boards, determ at instrument, isolate instrument, remove and return to - shop and decon ! Curation 25 days ' 6 men x & hrs / day / man x 25 days - 1200 hrs
- 14. RESIOVE V ALVE INTERN ALS CUT LOW POINT PIPE FO'A Sif RVEYS Assume 25% of pipe will be of configuration that requires cutting due to !
potential for contamination being trapped. Pipe will be cut in 6 foot lengths. CS RilR RC TOTAL CUTS UNIT RATE IIRS 21/2 TO 4' 13611f 20lf 2381r 16191f 162ea 7.28 1179 6 to 8' 2861r 2731f 431f 6021f 60ea 11.46 688 10 to 14' - 181f 154tf 1721f 17es 19.40 330 16* 1nd up .- .- -. . - -- - . -- .-- .- 2* and less 19831f 1591f $471f 36891f 2691f 4.80 1291 SUB TOTAL 3488 hrs , i CS Rito RC TOTAL UNI 7 RATE IIRS . l 21/2 TO 4' 154 2 19 175 3.25 569 t 6 TO 8' 15 19 --- 34 5.40 184 10 TO 14' .- - 4 4 10.30 41 16' and Up - -- -- - -- 14.70 -- - , SUB TOTAL 794 hrs ! Remove Remote Valve Operators 71 remote valve operators at 8 hrs ca = $68 hrs Remove motor and air operators 85 operators at 11 hrs ca = 935 hrs Total 5785 hrs Crew 12 Mechanics Duration 60 days Page 7 - 14
i Decontamination Operations / 7. 4
' 15. REN10VE DASIS IlOT AND COLD LEGS Crew 8 Mechanics Duration 1 day 8 men x 8 hrs / day / man x I days = 64 hrs
- 16. DECONT A\11N ATE STE A%1 GENER ATORS Crew 8 Men Duration 20 days 8 men x 8 hrs / day / man x 20 days = 1280 hrs
- 17. RES10VE RE ACTOR PUNIP INTERNALS i
Remove concrete plug Iday Remove pipe connections 2 days Remove electrical 2 days Rig and move motor 2 days
- Rig and move motor stand Iday
, Pull pump internals 2 days j Decontaminate internals 4 dsys Total Duration 14 days Crew I 4 Mechanics
! Mechanic operating crane Duration 14 days 5 men x s hrs / day / man x 14 days = 560 hrs
- 18. DECONTAS11N ATE REACTOR COOL ANT LOOP PIPING AND PUS 1P BOWLS Crew i 8 Men Duration 10 days 8 men x 8 hrs / day / man x 10 days = 640 hrs Page 7 - 15
Decontamination Operations / 7. 4 4
' 19. DR AIN VESSEL Crew l i
2 hien Duration I day 2 men x 8 hrs /dsy/ man x ! days = 16 hrs
' 2 0, RE5iOVE PUSIP AND TEStPOR ARY PIPE IN CONTAINAtENT Crew 4 hien Duration 3 days 4 men x 8 hrs /dsy/msn x 3 days = 96 hrs i
- 21. RE510VE RESTAINDER OF TESIPOR ARY PIPING Crew 8 hien Duration 6 days 8 men x 8 hrs / day /msn x 6 days = 384 hrs
- 2 2. DECONTA511N ATE VG AND WG SYSTEnt PIPING r l
Crew ! 8 hien - llandle flush hoses, perform valve lineups and monitor hose and I connectors during flushing activities Duration 5 days to set up flushes 1 days to perform flushes 8 men x 8 hrs / day /msn x 8 days = 512 hrs
- 2 3. DECONTA511N ATE WG SYSTE51 VESSELS Crew I 8 hien - Open tanks, erect scaffold if required and hand wipe tank Duration 15 days
] ; 8 men x 8 hrs / day /msn x 15 days = 960 hrs Page 7 - 16 ^
Decontamination Operations / 7,4
- 24. RES10VE V ALVE INTERNALS. CUT LOW POINT PIPING AND VERIFY CLEAN Assume 25% of piping will be of configuration that reauires c,otting due to potential for contamination being trapped. Pipe will be cut in 6 foot lengths.
Cut Pipe Remove VG WG Total Cuts Unit Rate lits
- 1/2" to 4" 3421f -- 342tf $7ea 7.28 415 6" to 8" 1211f - 1211f 20ea 11.46 229 10" to 14" 341f -
341r 6ca 19.40 116 16" and Up 13tf - 131f 2ca 34.20 68 2" 2991f 749 10481f 175ca 4.80 840 Sub Total 1668 hrs Remove Valse Internals 21/2" to 4" 5 @ 3.28 hrs ca = 16 hrs Total 1684 hrs Crew 8 hiechanics Duration 26 days
- 2 5. DECONTA%11N ATE WLD SU$tP AND PUP 1P Crew 2 Mechanics to clean pumps 4 Utility Technicians to clean sump Duration per sump Clean pump 2 days Clean sump 2 days 2 men x 8 hrs / day / man x 2 days x 12 pumps = 384 hrs 4 men x 8 hrs / day / man x 2 days x 12 sumps = 76g hrs ,
1852 hrs
- 26, FLUSH WLD PIPING SUh1P TO TANKS Crew 4 Mechanics to move fire hose from building sump to building sump work down stream towards the tanks Duration per sump 3 days 4 men x 8 hrs / day / man x 3 days x 12 sumps = 1132 hrs Page 7 17
Decontamination Operations / 7. 4
- 27. REMOVE VALVES AND LOV' POINT PIPING TO VERIFY CLEANLINESS Cut Pipe: Assume 25% of piping will have to be cut and t' moved in 6 foot pieces due to configuration WLD WL TOTAL CUTS UNIT RATE IIRS 21/2" to 4' l'671f 3481f 21151f 353 7.28 2570 6' to 8' ~~- 251f 251f 5 11.46 57 10' to 14' -- --- -- - - -- -- --
16' and Up ~~ 61f 61f 2cs 34.20 68 2' 979tf 7231f 17021f 285ea 4.80 1368 Sub Total 4053 hrs Remove valve internals WLD WL TOTAL UNIT RATE ilRS 21/2" TO 4' 38 37 75 3.25 244 ilRS Total 4307 hrs . Crew 8 Mechanics Du' cation 67 days
- 2 8. CLEAN WL TANKS AND PUMP Crew 4 Mechanics to open and hand wipe tanks, disassemble pumps and hand wipe Duration 15 days 4 men x 8 hrs / day / man x 10 days - 320 hrs
- 2 9. FLUSif BRS PIPE Crew 4 Mechanics to perforrn~ valve lineups, route flush h;ses, monitor flush and remove flush equipment at completion Duration 8 days 4 men x 8 hrs / day / man x 8 days = 256 hrs Page 7 - 18
Decontamination Operations / 7. 4
- 3 0. C,LE AN BRS
- ANK$. FILTERS. PUS 1PS Crew 8 hfechanics to wash tanks with hydrolaser, scaffold and hand wipe, disassemble pumps and decon Duration 30 days 8 men x 8 hrs / day / man x 30 days = 1920 hrs PIPE CUTS UNIT R ATE IIRS 21/2" to 4' 6421f 107 7.28 779 6" to 8" 1041f 18 11.46 206 10" to 14" 4if 2 19.40 38 14' and Up 12if 3 34.20 103 2' and Less 1420lf 237 4.50 1136 Sub Total 2262 hrs Remove valve internals 2 t/2" to 4' 94 es 2. 3.25 hrs /ca - 306 hrs 6" to 8' 4 ea x 5.40 hrs /ca = 22 hrs Sub Total 328 hrs Remove remote valve operators 36 operators x 8 hrs /ca = 288 hrs Remove motor and air operators 25 operators x 11 hrs /ea = 275 hrs Total 3153 hrs
. Crew 12 !. ten Duration 33 days
- 3 2. CLE AN Call DUCTWORK 62,700 sf @ 0.10 hrs /sf = 6270 hrs Crew 6 hicchanics 4 Utility Technicians Duration 78 days Page 7 - 19 A
i Decontamination Operations / 7. 4
- 33. SHIPMENT OF LOW I.EVEL WASTE 1400 cubic feet of waste from demineralizers, filters, etc. Allow 96 cubic feet per containers for miscellaneous waste such as protective clothing, hoses, visqueen, etc.
Total 14 containers @ $600.00 each purchased 1344 cf to be shipped and disposed at $90.00/cf
- 3 5. PORTABLE MINBED RESIN DEMINER ALIZERS WILL COST SM.000.00 s
Disposal of portable bed resin 80 cf I DOT container @ $600.00 Shipment and disposal @ 590.00 cf x 96 cf a 1 1 1 1 i i i j P. .. , . 2 0
Decontamination Operation / 7 . 5 1 R ADIOACTIVITY IN FACILITIES AND SYSTEMS Restrictine Access to Radiation Areas f Federal regulations (10 CFR 20, Standards for Protection Against Radiation), ! provide limits on radiation levels in unrestricted areas. These limits are ' applicable to facilities which hold licenses for the use of radioactive materials, such as hospitals, dentists, universities and nuclear power plants.
- The licensee is responsible for controlling access to any area where an individual could receive a radiation dose of two millirem in one hour, or >
100 millirem in seven consecutive days. The unit mrem is used to describe l exposures to radiation, similarly the unit lumen is used to describe exposure ! to light. As a result of exposure to natural background radiation, we receive a yearly radiation exposure of 360 mrem. One chest X ray results in an exposure of 20 30 mrem. ' Furthermore, to protect against transfer of radioactive material (contamination) as a result of system leakage or equipment maintenance, site procedures restrict access to any area where such contamination levels exceed 1,000 disintegrations per minute over a 100 square centimeter (approximately 4' x 4') area. This is a low value which represents a very low exposure to radiation. For example,if someone was exposed to this . contautination level which consisted of a radioactive species with a 21 hour , half life for the entire time the area was radioactive, they would receive a t radiation exposure of much less than I mrem. The two main criteria for controlling access for worker protection are. therefore, radiation levels of two millirem in one hour and contamination i levels of 1.000 disintegrations per minute over a 100 square centimeter area. ' I To determine the impact low power testing will have on workers' exposures, data from five power reactors was obtained and will be compared to the above limits in the following sections. . I I f Attachment 1 Page 7 - 21
Decontamination Operation / 7 , 5 FACILITIES AND TilEIR CONTENTS Protected Ares The NRC requires nuclear station owners to have legal control of the land around the station out to a distance called the exclusion boundary. At Seabrook, this is equal to a distance of 3,000 feet from the reactor and covers tn area of 719 acres. A "Protected Area' is established immediately around the permanent station structures and is there to provide security for all system: needed for safe operation and shutdown of the plant. The Protected Area contains all the systems needed to support electrical power generation. it covers an area of approximately 2.5% of the 719 acre site. The reactor system, auxiliary process and cooling systems and waste processing systems are all located within the Protected Area. The Protected Area, as a whole, is not controlled a cither a radiation or contamination area. Only 8% of the total facilities within this area potentially will be under radiological control. Containment Buildine The Containment Building houses the reactor system and will contain the majority of radioactivity resulting from plant operation. It is a cylindrical structure with a radius of 79 feet, occupying approximately 20,000 square feet, or 2.5% of the Protected Area and less than .1% of the entire site. Major components in the Containment Building are the reactor, coolant recirculation system and support systems. The vast majority of the radioactivity produced in the fission process will be contained in the reactor fuel located in the reactor core. The core is contained in the reactor vessel, a steel cylindrical vessel 15 feet in diameter and 42 feet high. A thick concrete shic!d surrounds the reactor vessel in the core region, reducing direct radiation from the core to non.
. detectable levels (less than one millirem per hour).
The reactor coolant system circulates cooling water through the reactor vessel and steam generators. After extended power operation (several months at Qtil cower), activation products plate out on the inside walls of the reactor coolant piping, creating radiction areas in the areas surrounding these pipes. This is typically caused by the activation products Cobalt 58 and Cobalt 60. Measurements taken during low power testing at other facilities demonstrates that these activation products are not available in any significant quantities during low power testing. Furthermore. radiation measurements tsken in the vicinity of the resetor coolant reelreulation system followine low nower testina confirm that rsdistion levels are less than two millirem eer hour. snd do not reouire classifiestion ss rsdistion areas. In fset. inspection of radiosetivity in resetor coolant samples (see Attachment i Page 7 - 22
Decontamination Operation / 7 . 5 Table li demonstrates that snv fission and scrivation eroducts svsilable in i snv sinnificant ausntity have very short half lives fless than one dav). and will therefore decsv to insinnificant levels within s week or so followine s h u td ow.',th Following extended full power operation, contamination levels resulting from system lesks and maintenance typically require control as ' contaminated areas'. Similar to eteeriences in radiation measurements described above. both in clant measurements (Table 2) and resetor coolant setivity (Table I) ' messurements demonstrstes that low oower testine does not esuse residusi lone lived rsdioloeical contsminstion in the Contsinment Buildine. Auxillsrv flulldine The Auxiliary Building houses the equipment used to purify, chemically adjust and recycle reactor coolant. It is a rectangular concrete structure, occupying approximately 8,700 square feet or 1.1% of the Protected Area and less than 1% of the entire site. Equipment used in actual processing of reactor coolant occupies a small portion (approximately 20%) of this facility. While no radioactivity is generated in this facility, the processing systems transport a small amount of reactor coolant from, and return it to, the Containment Building. The radioactivity and radiation levels in vicinity of this equipment, similar to that in the Containment Building, will be insignificant (see Table 2). While the filters and demineralizers used in the process systems may concentrate this radioactivity the radioactivity, as indicated in Table 1, is relatively short lived and will decay to insignificant levels within several weeks af ter shutdown. Waste Processine Buildina The Waste Processing Building houses the equipment used to recycle leakage associated with reactor coolant and process systems, and to handle any waste generated by the auxiliary process systems. It is a rectangular concrete structure, occupying approximately 26,000 square feet, or 3.4% of the Protected Area and less than .1% of the entire site. Equipment used in actual processing of radioactivity occupies approximately 16% of this facility. Similar to the Auxiliary Building, no radioactivity is generated in this facility and radiation and radioactivity will be equally insignificant, low power testing is not expected to generate waste from the purification and processing systems. Attachment 1 Page 7 - 23
Decontamination Operation / 7 . 5 CONCLUSION The low power test program at Seabrook Station will result in a negligible i radiological impact, if plant contamination levels were measurable they , i would consist of short lived isotopes that would decay within 12 weeks. i The only areas in the plant expected to contain radioactive material within a few weeks following low power testing would be the reactor vessel and associated core internals, reactor fuel and potentially in removabic process filters in the primary auxiliary building. i e e Attachment 1 Page 7 - 24
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5 TAett 23 saDIATIOu A m CostafelmATION LEvtLS EFFECTIVE FULL POWER RACIATION *CouT AseleATION plani mouts LOCATION (mittiree/ hour) (4 W 100 sq. cm.) A 5000 Generet Areas en seector Conteirament * .5
- 1000 Generet Arees in Beector Piping Area 20 = 1000 8 peector Cootent Pipe A'ee 1 e 1000 Appree 200 Ausitiary Process Systra meet Eschenger Area 1 w 1000 Ausillary Process System Pipe aree e1 e 1000 "U
es es O 4 C appree 10 Aunillery Process System Neet Eschenger Area 9000 men (short-lived, e n half-tives .5 to 20 hours) $ N Aunitlary Process Systes Pipe Aree
- e1 e 1000 **
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Decontamination Operation / 7 . 5 i TABLE 3: PLANTS INVOLVED IN SURVEY i l 1 Ejant Statles Name Time ! l A Millstone 3 Pressurized Water Rese:or i i B South Texas Project 1 Pressurized Water Reactor I i C Braidwood 1 Pressurized Water Reactor D Shoreham Boiling Water Reactor ( E Braidwood 2 Pressurized Water Reactor f I r i l i ( l l 7 l { l Attachment 1 i Page 7 - 27 I
Reactor Vessel & Associated Components Removal & Disposal P t' TABLE OF CONTENTS - 1 I SECTION DESCRIPTION PAGEo i l l !
- i
) 8.1 Reactor Vessel .id Attociated 8 1 i Com pon e n ts j 8.2 Selected Antion and Cost 8 5 Analstit 8.3 Schedule Logic 3 8 i ! 8.4 Estimate Assumptions 8 10 ; S.5 Cost Estimate / D.I 8 11 I S.6 Estimate Back up .' . 16 l l I i f i I I i
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i Reactor Vessel & Associated Components Removal & Disposal / 8.1 1 RE ACTOR VESSEL AND ASSOCI ATED COklPONENTS , PURPOSE: To determine the most efficient cost and schedule for removal i and disposal of the Seabrook tJnit i reactor vessel and associated components: 1.c., head. Internals, control rods. { incore instrumentation, etc. after low power testing has been l completed. i I ASSit\tPTIONS:
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- l. Ascrate, on contact radiation levels from fixed contamination l or cobalt activation is 500 mR/hr (conservative). !
l :. All components are disposed of as low level waste, This ! I provides a worst case scenario when in fact many I components or pieces of components will hase no radiation levels and can bJ disposed of as normal scrap. ! . l l 3. The following items are availtble for use j i during removal / disposal operations without ' any additional costs: A. Containment Integrity. B. Containment Gantry Crane, g C. Reactor Cavity Manipulator Crane. I i
- 4. All operations are conducted under ALARA practices, !
l REN10 VAL OPTIONS CONSIDERED: j t OPTION I. Fill with Concrete and Leave in Place: This option entails I fiUing the reactor sump, reactor itself, and the reactor : refueling cavity (partially or entirely) with concrete and ; leaving the reactor in place. { While this option, in terms of schedule and logic, is the casiest. It was climinated for the following reasons:
- 1. The site would hhve to be licensed as a low level waste disposal site.
O. Cost of environmental impact studies, legal fees, license fees, etc. would be very high. Page s . I
i Reactor Vessel & Associated Components Removal & Disposal / 8.1
- 3. This option would preclude use of the site for any other purpose.
l 4. The top of the retctor head is 3 feet above current site grade elevation. OPTION 11. Ship reactor whole with internals inside: This option entails a i cutting the reactor vessel loose intact, seal welding all openings and shipping the reactor with internals, control rods, ) and incore instrumentation all inside the vessel. J This option was eliminated for the following reasons: l
- 1. Present containment gantry crane cannot lift the amount of weight involved in this option, approx.
imately 630 tons. I :. The physical size and weight of this option required l shipment by barge, c 4
- 3. Major expense involved in shoring up or rebuilding bridge between the Seabrook site and the barge facility.
] 4. Heavy haul contractor required at shipping end as well as receiving end.
- 5. Major equipment hatch ramp modifications reavited to
{ accommodate heavy transport vehicle. I 6. Option would require DOT approval of reactor vessel j as an approv:d low level waste shipping container. I
- 7, Low Level waste receivers (disposal sites) are not
- geared for large component disposal.
i ) OPTION 111. $his ecmoonents intact but senaratelv: This option entails l shipping the major components separately but whole. While i some of the weight problems are solved with this option,it was eliminated for the following reasons: i
- l. Physical size and weight of reactor sesselitself l required shipment by barge, i
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Reactor Vessel & Asso::iated Components Removal & Disposal / 8.1
- 2. Stajor expense shoring bridge to barge facility.
- 3. Overall volume of low level waste is significantly increased, thut increasing disposal costs.
4 Ileavy haul contractor required at shipping end, as well as receiving end. (for vessel).
- 5. Stajor equipment ramp modifications required for bravy transfort vehicle.
- 6. DOT approsal of specialized shipping containers required.
7 Low Level waste receivers not scared for large component disposal. OPTION IV: Cut components up into manageable pieces: This option would entail cutting components into manageable pieces from a weight and volume itandpoint and placing the pieces in standard (DOT approved) low level waste shipping containers. This option was selected as the preferred method of disposal for the following reasons:
- 1. No special technology, such as heavy lift and transport, requ.' ed.
- 2. Pieces can be standardized to fit presently approsed 7 DOT containers.
- 3. Containers can be shipped by common flatbed truck carrier.
- 4. l.ow level waste receivers geared to receive approsed containers,
- 5. No modification required to present equipment ramp, containment crane, etc.
NOTE: Two additional variations of this option (Option IV) were also analyzed and climinated for the reasons discussed: Variation A. Cut components into large non standerd shapes and weights. This variation was climinated because of many of the problems already listed, associated with weight and non standard container sizes. Page 8-3
I l _ Reactor Vessei & Associated Components Removal & Disposal / 8.1 - Variation B. Remove the cladding from the inside of the reactor vessel and head by machining. This would have the potential of climinating the need to dispose of the reactor vessel and head as low level waste, This variation was eliminated because no guarantee can be provided thrit all residual activation of vessel material could be el;minated. e Page 8 - 4
I i Reactor Vessel & Associated Components Removal & Disposal / 8. 2 i SELECTED OPTION AND COST ANALYSIS GENER AL OVERVirW: i Option IV entails cutting up the reactor vessel and , associated components into manageable pieces. Each piece f would be less than 4 foot by 4 foot by 6 foot in volume (the size of the present DOT approved, low level waste shipping containers used at Seabrook Station) and also each piece plus shielding must weigh less than 6000 lbs. ; (weight limi' of present containers). : Containers would be shipped by common truck carrier,7 containers per truck minimum (7 containers at 3 tons each ( t would coual 21 tons; 2 tons is maximum load for a l flatbed truck). l t Components would be cut udng high pressure Plasma Arc cutting torches in order to cut the stainless steel components and stainless steel cladded reactor sessel and l head. i t j . All cuttine operations would be contained in tented I
- enclosures maintained at a slightly negative pressure with (
a all air filtered through IIEPA filters to contain airborne I contamination caused by cutting smoke and gases, l I
- All workers are assumed to require respirators and [
breathing line during cutting operations. [ Decontamination of th reactor cavity and area ur. der the [ reactor were assumed as the final closcout step. l i 6 j GENERAL ACTIVIT!ES 4 { i i 1. Preparation for Cutting: I J 1. Procurement of equipment and contracts. l ! (Note: Majority of equipment, protective clothing, L 1 lights, scaffolding, rigging equipment, etc. would bc already available onsite), l t A. Scrap magnit (to handle cut pieces of vessel). l l B. Shipping containers. i i C. Tenting material. l I D. Plasma Arc cutting equipment and gases. E. Shipping contract, f F. Protective clothing laundry contract. j Page 5 4 I
l l i i Reactor Vessel & Associated Components Removal & Dispcsal / 8. 2 L
- 2. Set up and Staging:
A. Set up tenting and air filtration equipment. B. Erect necessary scaffolding. C. Set up breathing air compressor and back up bottled air supply. D. Pre stage all shipping containers inside Containment. E. Set up and run test cuts with cutting equipment.
!!. Disassembly and Cutting:
- 1. Disassemble Reactor:
A. Remove head. B. Remove upper internals. C. Remove lower internals. D. Remove core barrel. E. Remove baffle plates. F. Remove Control Rod Drive htechanism (CRDht) from head.
- 2. Cut Internal Components into Transportable Pieces:
A. Cut picces to minimum number of shipping containers required. B. Shield pieces (if necessary). C. Place pieces in shipping containers. D. Store full shipping contair.crs behind Steam Generators to seduce exposure levels.
- 3. Cut Reactor Head:
(Satt.e general steps as No. 2).
- 4. Cut Reactor:
A. Lay out cut lines (vessel is hung from 4 cmbedded suppor ts). B. Block coolant loop pipes. C. Cut all hot and cold les piping. D. Cut and remove all incore instrumentation conduit. E. Cut Reactor into transportable pieces and place pieces into shipping containers.
!!!. Cicanup and Shipping:
- 1. Decontaminate refueling cavity and reactor sump.
Page 8 6
Reactor Vessel & Associated Components Removal & Disposal / 8. 2 2, Decontaminate all high potential investment recovery l equipment. l 1 i A. Scrap Magnet. B. Plazma Arc Torches. , I j 3. Dispose of majority of tools and materials as low level ! waste, i A. Ilose. i B. Lif ting slings. I C. Protectisc clothing. [ D Tenting material. i E. Air handling equipment, i
- 4. Op:n Equipment IIstch and begin shipment of containers. i
- 5. Final Hwalth Physics containment survey, decontamination. l and release for unrestricted use. i 1, .
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Reactor Vessel & Associated Components Removal & Disposal / 8. 3 SCHEDULE LOCic An order of magnitude Level Two schedule logic for Option IV, which shows activity sequence and estimated durations is shown on the next page. Page 8 8 l uOr
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I i t Reactor Vessel & Associated Components Removal & Disposal / 8. 4 i a ! ESTISf ATE ASSU5tPTIONS j Manpower . Union cref tsmen that performed the original installation of the components. Operations personnel remove reactor head and {' internals to climinate training craf t personnel, i
%' age Rates . The existing wage rates for Seabrook Station under the Nuclete Stabilization Agreement in effect at the time of the estimate.
No allowances for shift differential are included since all activities are scheduled on one shift. *
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Average on contact radiation levels from fixed contamination or cobalt 59 I actisation is 300 mR/br. (Conservative). ' No surface contamination exists in Containment Building, l Reactor Coolant System drained. Fuel is removed from vessel and stored in Fuel Storage Luilding. l q Station air compressors available for use in breathable air. 1
' l Statien electrical distribution system available.
) ! I Estimated manhours adjusted for a 50 percent productivity loss duo to L working in protectisc clothing, full respirators with hoses, dressing time and ! i radiation access control. { ] Decontamination liquids used disposed of through normal statio.s procedure 4 g gnd systems, f Estimate excludes health physics Personnel, since they are covered under ! Supporting Operations. I r i [ .i f l I I I ( f I l l Page g . 10 l [
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, t Reactor Vessel & Associated Components Removal & Disposal / 8. 5 l I
i i I a 4 ( COST ESTIMATE Page 8 11
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CLIENT : kNY DESCRIPTION OF UORIC : DEC0petISSION REACTOR VESSEL (POST LOW POWER TESTING) ESTIMATE NO : 0-1
................................. . ............................................................................................ 2 g < < < - - - - - - -Ug I E R A T E S - -- - - - SUS DESCRIPfl0N QT M-NR S g
t:. 4 MAT'L S M NRS MATERIAL LABOR CONTRACT TOTAL MANHOURS n
.....c2.....................r.. ....'T... .sJa ........ ....... ........ ......s..... .......... ........ ............ ........ re REMOVE REACTOR COVER 1 LS l 360 $25.60 10 59,216 19,216 0 360 REMOVE BREATNING AIR,LIGNTING, 1 LS 264 117.78 50 $4,694 14,694 264 POWER AND WENT EQUIPMENT AND PLACE IN $ NIPPING CONTAIMER I
O REMOVE mERCULITE COVER Au0 LS 840 S17.63 114,809 PLACE JN C0h!AINERS 1 SO 514,809 840 $ m REMOVE fCAMES Au0 SCAff0LDInc 1 LS 1,440 517.96 SD $25,862 125,862 1440 REMOVE IuCORE IhSTRUMENTATION 1 LS 240 117.40 SO S4,176 54,176 240 D TummEL EhCLOSURES REMOVE SREATMING AIR 1 LS 24 516.20 50 5389 DEC04 INCORE TUmwEL 1 LS 600 516.20 SO 19,720 S389 19,720 24 600 DECOM REFUEL POOL 1 LS 1,200 S16.20 SO S19,440 519,440 o 1200 n CNEMICAL CLEANIhG OF SYSTEMS 0 ~5 C 1 LS 50.00 SO SO SO O re m LOA 0 347 SNIPPING CouTAlutRS On 1 LS 780 S18.33 So $14.297 514,297 780 E TauCx5 o n m 347 S8,640 Q ** DISPOSAL OF CONTAINERS CONTAINERS 347 EA EA $600 0 0 S0.00 S0.00 S2,998,080
$208,200 SO SO S2,998,080 S208,200 0
0 g LAU40RY SERVICES 12 Mu 15,000 0 S0.00 160,000 O 00 So S60,000 0 o PURCHASE TORCNES AhD ROBOTICS 1 LS S250,000 0 10.00 1250,000 10 S250,000 0
*** LEAD SMIELDisG 416,400LSS 3 , 1 LS $208.200 0 50.00 1208,200 SO S208,200 0 m 3
k re MISC. DIRECT MAT'L en
$32,583 S35,583 (51 0F DIRECT LA80R) y m
SUS-TOTAL DIRECTS 53,760,063 1711,657 SO S4,471,720 31,993 SMALL TOOLS & ConsuM. 50 10 h 12tRECT L ASOR: (151 0F DIRECT LAe0R) SO Slu6,749 SO S106,749 4,799
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monMAmual O (25% OF DIRECT LABOR) SG S177,914 10 S177,914 7,998 g* NEALTu PuYSICS TECHNICIANS g SO 10 SO 10 0 O in fuGINEERING: UEEC 0 MN j 1 SO SO muY 0 MN SO SO YAsC 0 MN g SO SO CONSULTAsT 0 MN SO SO m
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l Sus-TOTAL S3,760,063 5996,320 S4,756,383 SO 36,772 uf
yu~ .t . - . - - . , _ m s -L CLIEmi : NNY DESCRIPTION Of WORK : DEC0poIISSION REACTOR VESSEL (POST LOW POWER IESTING) EsitMATE NO.: D-1
................................................................................................................................... 2 to g u < - -- - -- -Un l i RhlES-- ---- - SUS g DESCRIPTION Qi'Y UN MAT't S M-HRS M-NR S MATERIAL LABOR CONTRACT TOTAL MANMOURS n
............................... ....... .......... ....... ........ a........... .......... ........ ..r......... ........ re O
s monMAmuAL FEE & 04 134,693 14,693 q (N0= MAN S . 302)*15x (D in EbGlhEERING FEE & ON 10 10 in (UE&C thGIN S +30%)*30% ts TOTAL ESTIMATE S3,794,756 1996,320 10 S4,791,077 j 36,792 (MANNOURS ARE CRAff outT)
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................................................................................................................... ................ g) ll <" -------UNIT RATES------- SUS n QI'T UN mal *L S M-hts M-NR S MATERIAL LABOR CONTRACI TOTAL MANNOURS 5'
' ..........DESC2tPTION
...........m......... ....... .. .......... ....... ........ ............ .......... ........ ............ ........ re StmKARY Of COST:
$2 TOTAL DIRECT COSI S3,760,063 1711,657 SO S4,471,'70 31,993 O O
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- n. 3 g TOTAL Im01 RECT iOST SO S106,749 SO 1106,749 4,799 g O
co 3 TOT AL an. nam se $34,693 1177,914 10 S212,608 ft (thCLUDES FEE & ON) U re ta in TOTAL ENGimEERIuG 10 SO SO $0 % ft (INCLUDES FEE & ON) g TOTAL ESTIMATE S3,794,756 5996,320 10 14,791,077 36792 O
............................... ....... .. .......... ....... ........ ............ .......... ........ ............ ........ 4, g
S3,794,800 1996,300 10 Sc, m .iOO 36792 -
.I...............uSE ................................................................................................................... p ITEft, MOT REQUIRED If PL AN ASStMPTIC485 DO PROVE 10 SE CONSERVATIVE C QUAuflTIES REDUCED TO 116 If PLAN ASSUMPitCMS 00 PROVE TO BE C0kSCRVATIVE $*
139,200 LS$ !F PLAN AssuMPi!ONS DO PROVE 10 SE CONSERVATIVE -Q O in W
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Reactor Vessel & Associated Components Removal & Disposal / 8. 6 RE510V AL AND DISPOSAL ESTISTATLB ACK-UP
- 1. RE510VE CRD515 AND SERVICE STRUCTURE A. Remove stud tension hoist and monorail 4 hicehanics x 6 hrs / day / man x 2 days x 1.5 = 72 hrs 1 Operator x 8 hrs /d:.y/ man x 2 days x 1.5 - 24 hrs B. Remove HVAC shroud 3 Boilermakers x 8 hrs / day / man x ! day x 1.5 = 36 hrs C. Remove CRDht service structure 5 Boilermakers x 8 hrs / day / man x 2 days x 1.5 = 110 hrs
! Operator x 8 hrs / day / man x 2 days x 1.5 = 24 hrs D. Retnove CRDht's 57 ca. include storage in containment for later removal 5 hicchanics x 8 hrs / day / man x 20 days x 1.5 = 1200 hrs TOTAL I476 hrs Say 1500 hrs Duration 25 days
- 2. RE5f0VE REFLECTIVE INSULATIOA ' EAD 2 Insulators x 8 hrs / day / man x 3 days x 1.5 = 72 hrs
- 3. ERECT TE5fPOR ARY ENCLOSURE FOR REACTOR IIEAD
- Erect and brace scaffold towers including herculite support 3 Carpenters x 8 hrs / day / man x 2 days x 1.5 - 72 hrs 2 Laborers x 8 hrs / day / man x 2 days x 1.5 = 48 hrs llams not required if Plan usumptione do prove to be conservative Page 8 - 16
Reactor Vessel & Associated Components Removal & Disposal / 8. 6 Install herculite und seal 25 f t. x 27 f t. x 12 f t. high 1296 cu. ft. 3 Carpenters x 8 hrs / day / man x 1 day x 1.5 = 36 hrs 2 Laborers x 8 hrs / day / man x 1 day x 1.5 = 24 hrs Total 180 hrs
- 4. INSTAL l. I IGIITING AND BRE ATlilNG Ada Lighting 2 Electricians x 4 hrs / day / man x ! day x 1.5 = 12 hrs
- Air
- Laborers x 4 hrs / day / man x 1 day x 1.5 = 12 hrs Total 24 hrs
- 5. DE5101 ISil CRDN1 SEllVICE STRUCTURE
- Service structure approximately 18.25 high with an outside diameter of 12.5 f t. Assumed thickness 3/8" plate WT = 717 sq. f t. x 1532 lbs./sq. f t. = 10.984 lbs.
Demolition cost
- Cutting with torch iforizontal cuts 3 at 39 f t. ca. x .08 hrs /f t. x 1.5 = 14 hrs
. Vertical cuts 14 at 6 f t ca. x 3 x .08 hrs /f t. x 1.5 = 30 hrs
- Rigging 4 Boilers x 2 hrs / piece x 3 pieces x 1.5 - 36 hrs 80 hrs Say 90 hrs Duration 3 days Page 8 17
Reactor Vessel & Associated Components Removal & Disposal / 8. 6
- 6. REN10VE SCR AP FRO 51 CONTAINNIENT TO S ALV AGE ARE A 4 Boilers x 8 hrs / day / man x 1 day x 1.5 = 48 hrs
- 7. SET UP CUTTING EOUIPS1ENT Fabricate revolving track support system 3 men x 8 hrs / day / man x 3 days x 1.5 = 108 hrs Move and install track support system in containment j 3 men x 8 hrs / day / man x 2 days x 1.5 = 72 hrs
- Move and install plasma torch including hoses electrical supply 3 men x 8 hrs / day / man x 1 day x 1.5 - 36 hrs
- 8. CUTTING llE AD Head Weight 165,150 lbs.
Assume 29% shielding for 6000 lb. shipping Container = net load of 4800 lbs. Head = 165,150 lbs.
- Cutting Time Two horizontal cuts = 16 hrs Segment Cuts = 70 hrs 86 hrs Cutting crew I Torch Operator x 86 hrs x 1.5 - 645 hrs 4 Mechanics Page 8 18
Reactor Vessel & Associated Components Removal & Disposal / 8. 6 Rigging Pieces to continue cutting x 3 picks x 3 hrs ca x 1.5 = 67 hrs chanics Total = 712 hrs Say 7:0 hrs
- 9. LO AD PIECES INTO S111PPING BOXES can load four boxes per day ife'hanics 17 boxes for head flange = 7 men x 8 hrs / day / man x 4 days x 1.5 = 336 hrs 16 boxes for head pieces = 7 men x 8 hrs / day / man x 4 days x 1.5 - 336 hrs 448 hrs
- 10. REN10VE TORCII AND FR AS1E 3 men x 8 hrs / day / man x ! day x 1.5 = 36 hrs
- 1 1. REhlOVE IIERCULITE AND PLACE IN BOX 3 Carpenters x 8 hrs ca. x 1.5 = 36 hrs 2 Laborers x 8 hrs ca. x 1.5 = M hrs 60 hrs
- 12. RES10VE FR AS1E FOILLN. CLOSURE 3 Carpenters x 8 hrs / day / man x ! day x 1.5 = 36 hrs 2 Laborers x 8 hrs / day / man x 1 day x 1.5 = 24 hrs 60 hrs
- 13. CUi REACTOR COOLANT LOOPS AND COVER
- 4 Cold Legs
- 4 liot Legs 50 hrs per leg x 1.5 - 600 Srs
- Use crew of 5 fitters Page 8 - 19
r i Reactor Vessel & Associated Components Removal & Disposal / 8. 6
- Install dams in loops for protection 5 Fitters 16 hrs / loop x 1.5 = 120 hrs Total 700 hrs 14 ERECT ENCLOSURE IN CORE TUNNEL ENTR ANCES 6 Carpenters 4 Laborers Installation of frames 2 days Covering of frames with herculite i day 10 men x 8 hrs / day / man x 3 days x 1.5 = 360 hrs
- 15. INSTALL BRE ATilING AIR 2 Laborers x 8 hrs x 1.5 = 24 hrs
- Use permanent lighting
- 16. REN10VE REFl.ECTIVE INSULATION FRON1 VESSEL
- 3 Insulators 5 days 3 men x 8 hrs / day / man ~ 5 days x 1.5 = 180 hrs
- 17. RES10VE REFLECTIVE INSULATION FRO 51 CONTAINS1ENT 3 men x 8 hrs / day / man x 8 days x 1.5 = 288 hrs
- 18. CUT AND RE510VE INCORE INSTRUNfENTATION CONDUIT
- Incore l' diameter heavy wall pipe weighing 2 lbs./lf.
- Installed quantity 5,225 If. = 10,450 lbs.
- Assume 20% shipping container for shielding yields net load of 4800 lbs.
- Will require 3 boxes Page 8 20
Reactor Vessel & Associated Components Removal & Disposal / 8,6
- Tubes will have to be cut into 5' 6" pieces which yield 950 cuts
- Cutting tubing 1/2 hr/ cut x 1.5 = 713 hrs
- Cutting supports 58 tubes x 10 supports x 1/2 hr/ cut x 1.5 = 435 hrs
- Cutting seal table x 1.5 = 60 hrs Total = 1208 hrs
- Assume crew of 5 pipefitters in tunnel
- 19. LOAD INCORE Ttf BES INTO SillPPING CONTAINERS
- Handling tubes 0.20 hrs /ft x 1.5 = 1568 hrs Assume 5 men in tunnel and 2 at elev. 26.0 f t.
- 20. RE510VE REFLECTIVE INSULATION 4 Insulators x 3 hrs / day / man x 5 days x 1.5 = 240 hrs
- Remove insulation from pool 4 Insulators x 8 hrs ca. x 1.5 = 48 hrs 1 Operator x 8 hrs x 1.5 = 12 hrs
- Remove insulation from building 4 Insulators x 16 hrs ca. x 1.5 = 96 hrs Total - 396 hrs
- 21. REh10VE ttPPER INTERNALS 5 Mechanics x 8 hrs / day / man x 2 days x 1.5 = 120 hrs
! Operator x 8 hrs / day / man x 2 days x 1.5 - 24 hrs 144 hrs
- 22. REMOVE LOWER INTERNALS 5 Mechanics x 8 hrs / day / man x 3 days x 1.5 = 180 hrs 1 Operator x 8 hrs / day / man x 3 days x 1.5 = 36 hrs 216 hrs Page 8 21
Reactor Vessel & Associated Components Removal & Disposal / 8. 6
- 23. COVER RE ACTOR VESSEL
- Fabrication cover 5 men x 8 hrs / day / man x 10 days x 1.5 = 600 hrs
- Install cover over vessel 6 men x 8 hrs / day / man x 5 days x 1.5 - 360 hrs Total = 960 hrs
- 24. COVER REFUELING POOL
- Fabricate Frames 6 Carpenters x 8 hrs / day / man x 15 days x 1.5 = 1080 hrs
- Erect scaffold, towers assemble frames and install herculite 10 Carpenters 4 Laborers x 8 hrs / day / man x 15 days x 1.5 - 2700 hrs i Operator Total - 3780 hrs
- 25. RIG AND SET UP CUTTING EOUIPMENT
- Remove non essential equipment, refuel bridge cranc 5 men x 8 hrs / day / man x 5 days x 1.5 = 300 hrs
- Modify fuel bridge to increase capacity and reduce height 5 men x 8 hrs / day / man x 10 days x 1.5 = 600 hrs
- Fabricate torch track supports 3 men x 8 hrs / day / man x 10 days x 1.5 = 360 hrs
- Install torch track supports and track 5 men x 8 hrs / day / man x 5 days x 1.5 - 300 hrs
- Install gas lines and torches controls, etc.
5 men x 8 hrs / day / man x 2 days x 1.5 = 120 hrs Total = 1680 hrs Page 8 22
Reactor Vessel & Associated Components Removal & Disposal / 8. 6
- 26. INSTALL BRE ATIIING AIR. LIGIITING. VENTIL ATION
- Breathing Air 4 Laborers x 8 hrs / day / man x 3 days x 1.5 = 144 hrs
- Install lighting and power 2 Electricians x 8 hrs / day / man x 5 days x 1.5 = 120 hrs Install ventilation hiodify filter unit @ elev. 25' 0*
4 Sheetmetal x 8 hrs / day / man x 5 days x 1.5 = 240 hrs Install flexible ductwork 2 Laborers x 8 hrs / day / man x 2 days x 1.5 - 48 hrs
$52 hrs
- 27. DEMOLISil REACTOR VESSEL INTERN ALS
* - Upper internals 114,500 lbs.
Volume !$37 cf = 74.5 lbs./cf. Shipping Container = 6000 lbs. Allow 20% shielding yields net load of 4800 lbs. 4800 lb, net load will allow 64.4 cf. of upper internals Upper Internals 14 f t. in dia, and 10 f t. high Pieces 5 ft. in length yields pieces 3' 6"x3'6' Make I horizontal cut = 16 hrs . hiske 30 vertical cuts = 100 hrs Handle pieces and place in boxes on reactor cover 6 pieces per day for 32 pieces = 6 days
- Cutting Crew I Torch Operator 4 Boilermakers
* - Cutting Time 5 men x l16 hrs x 1.5 = 870 hrs
- Rigging Crew 1 Operator 5 Boilermakers Page 8 - 23
i Reactor Vessel & Associated Components Removal & Disposal / 8. 6 Rigging Time 5 men x 8 hrs / day / man x 6 days x 1.5 = 360 hrs Load shipping boxes onto operating floor 32 boxes Handling 16 boxes per day
- Rigging Crew 2 Operators 5 Boilermakers 7 men x 8 hrs / day / man x 2 days x 1.5 = 168 hrt 1398 hrs Lower Internals 275,100 lbs.
Volume - 2699 cf. = 102 lbs./cf. Shipping container 6000 lbs. Allow 20% shielding yields net load of 4800 lbs. 4800 lb. net load will allow 47 cf./ box Lower internals 14' 5' in dia. and 16' 7' high Pieces 5.53 ft. in length yields pieces 3'x3' hiske 2 horizontal cuts = 32 hrs hiske 72 vertical cuts = 240 hrs liandling pieces into boxes 6 pieces per day for 75 pieces
= 13 days Cutting Crew
- 1 Torch Operator 4 Bollermakers Cutting Time 272 hrs x 5 men x 1.5 = 2040 hrs Rigging Crew I Operator 5 Boilermakers Rigging Time 5 men x 8 hrs / day / man x 13 days x 1.5 = 780 hrs Loading shipping boxes onto operating floor l 75 boxes llandle 16 boxes per day l Page 8 24
(
Reactor Vessel & Associated Components Removal & Disposal / 8. 6 Rigging Crew 2 Operators 5 Bollermakers 7 men x 8 hrs / day / man x 5 days x 1.5 = 420 hrs
- 28. DENf 0LISH RE ACTOR VESSt.L '
Remove Vessel Flange 84000 lbs. 17 blocks 3'x2' 4x18' = 5032 lbs. ca. liorizontal cut 8 hrs Vertical cuts 12 hrs Remove Blocks to south end of pool 8 blocks / day - 2 days Cutting Crew 1 Torch Operator 4 Boilermakers Cutting Time = 37 hrs
, 5 men x 37 hrs x 1.5 - 278 hrs Rigging Crew 1 Operator 4 Boilermakers Rigging Time 3 days i
5 men x 8 hrs / day / man x 2 days x 1.5 = 120 hrs
'.oad shipping containers Total of 29 pieces Crew 2 Operators 5 Boilermakers Crew can load and plan on operating floor 4 boxes per day 7 men x 8 hrs / day / man x 7 days x 1.5 = 588 hrs Remove Vessel to top of reactor coolant nozzles 44.3 f t. x 3 f t. = 133.3 sq. f t. x 40 lbs./sf/in x 10.75' = 57,412 lbs.
12 blocks 3'x3' 9'x10.75" = 4838 lbs. ! liorizontal cuts 8 hrs Vertical cuts 9 hrs Remove blocks to south end of pool 8 blocks / day = 1 day Remove Vessel below bottom of reactor coolant nozzles ; 16.67 f t. x(14.41 f t. ) = 733 sq. f t. x 40 lbs/sf/in x 8.63 - 300,000 ( Page 8 - 25 __ -s.----,
Reactor Vessel & Associated Components Removal & Disposal / 8. 6 60 blocks 5.5 long x 2' 8" x 8.63" Horizontal cuts 24 hrs Vertical cuts 48 hrs Remove blocks to south end of pool 8 blocks / day = 8 days Remove Lower Head 339 sf x 40 lbs./sf x 5.33 lbs = 42,953 lbs. 16 segments however segment would be 12.2 ft, will require two cuts horizontal Horizontal cuts 16 hrs Segment cuts 70 hrs Remove blocks to south end of pool 8 blocks / day = 4 days
- Cutting Crew 1 Torch Operator 4 Boilermakers Cutting Time = 158 hrs 158 hrs x 5 men x 1.5 = 1185 hrs
- Rigging Crew I 1 Operator 4 Boilermakers Rigging Time 11 days 5 men x 8 hrs / day / man x 11 days x 1.5 - 660 hrs
- Loading shipping containers Total of 92 pieces Crew 2 Operators 5 Boilermakers Crew can load and place on operating floor 4 boxes per day 7 men x 8 hrs / day / man x 23 days x 1.5 = 1932 hrs Pick reactor vessel nozzle ring from supports and > lace on north end of pool 5 men x 8 hrs / day / man x 3 days x 1.5 = 180 hrs Remaining wt. 147,300 lbs.
Yield 30 pieces Vertical cuts 20 hrs r Page 8 - 26
Reactor Vessel & Associated Compone.nts Removal & Disposal / 8. 6 Cutting Crew I Torch Operator 4 Mechanics Cutting time 20 hrs 20 hrs x 5 men x 1.5 = 150 hrs Rigging Pieces 1 Operator 4 Mechanics Rigging time 5 men x 8 hrs / day / man x 2 days x 1.5 = 120 hrs Load Shipping Containers Total 30 pieces Crew 2 Operators 5 Mechanics Crew can load and place on operating .*loor 4 boxes per day 7 men x 8 hrs / day / man x 8 days x 1.5 - 672 hrs
- 29. REMOVE REACTOR COVER 6 men x 8 hrs / day / man x 5 days x 1.5 - 360 hrs Remove breathing air, lighting, power and vent equipment and place in i shipping container
, Air 4 Laborers x 1 hrs / day / man x 3 days x 1.5 = 144 hrs Elect. 2 Electricians x 8 hrs / day / man x 3 days x 1.5 - 72 hrs Vent. 2 Laborers x 8 hrs / day / man x 2 days x 1.5 = 18 hrs 264 hrs
- 30. REMOVE IIERCULITE COVER AND PLACE IN CONTAINERS 10 Carpe tiers 4 Laborers = 1 week 14 men x 8 hrs / day / man x 5 days x 1.5 = 840 hrs Page 8 - 27
Reactor Vessel & Associated Components Removal & Disposal / 8. 6
- 31. REN10VE FR Ah1ES AND SCAFFOLDING TOWERS 10 Carpenters 4 Laborers i Operator 15 men x 8 hrs / day / man x 8 dafs x 1.5 = 1440 hrs
- 32. RES10VE INCORE INSTRUS1ENTATION TUNNEL ENCLOSURES 6 Carpenters 4 Laborers Remove covers place in boxes 10 men x 8 hrs / day / man x 1 day x 1.5 = 120 hrs Remove frames 10 men x 8 hrs / day / man x ! day x 1.5 = 120 hrs 240 hrs
- 33. REh10VE HRE ATJIING AIR 2 Laborers x 8 hrs / day / man x ! day x 1.5 = 24 hrs
. 34. DECONTA511NATE INCORE TUNNEL 5 Laborers 10 days 5 men x 8 hrs / day / man x 10 days x 1.5 = 600 hrs i
- 35. DECONTAA11NATE REFUEL POOL 10 Laborers x 10 days i 10 men x 8 hrs / day / man x 10 days x 1.5 = 1200 hrs Page 8 28
Reactor Vessel & Associated Components Removal & Disposal / 8. 6
- 36. SHIPPING CONTAINERS
- 33 Containers Reactor 11ead
- Internals Upper 32 Containers Internals Lower 75 Containers Reactor Vessel 151 Containers Incore Tubes 3 Containers Control Rods 11 Containers Miscellaneous Materials 41 Containers 347 Containers Loading containers on shipping trucks j 1 Operator 2 Laborers 30 min./ container = 1.5 hrs / container 347 containers x 1.5 hrs x 1.5 - 780 hrs i
i 4 d Page 8 29
STORAGE & FUEL REMOVAL TABLE OF CONTENTS SECTION DESCRIPTION PAGEe 9.1 Storare & fuel Remosal 9-1 9.2 Schedule Logic 94 9.3 Cost F. stimate / D 8 9-6 9.4 Estimate Back up 9-9
-V
Storage & Fuel Removal / 9.1 STOR AGE ANJ_ FUEL RES10V AL PURPOSE: Storage of irradiated fuel assemblics and removal from the Seabrook Site. ASSl \1PTIONS:
- 1. Fuel shipped offsite for reprocessing.
- 2. Shipment and reprocessing cost excluded.
DESCRIPTION OF ACTIVITIES Upon completion of fuel building preliminary activities Section 5 and preparation for fuel removal from the sessel, the full reactor core inventory 193 fuel assemblies will be cff loaded and stored in the fuel storage pool of the fuel storage building. Based on the following heat load calculations the fuel storage (FS) pool cooling system will be placed on a recirculation mode to remove decay heat through convection to the fuel building atmosphere and prevent thermal stratification of the fuel storage pool water The component cooling water side of the FS heat exchanger will not be required. Decay Heat Load Estimate Decay heat as a function of irradiation time and shutdown time is estimated by the following equation: 1 P/P, = 6.1 x 10 8 [( + - t.) 8 - G 8) Where S- - Time af ter shutdown (days) t, - Operating time (days) P/P, - Ratio of decay heat power to operating power (dimensiohless) The low power test program for Seabrook Unit I calls for heatup and initial criticality followed by ten days of intermittent testing at a power level of between 0.01 percent (1/100th of I percent) and 0.1 percent (1/10th of I percent) of full power and 12 hours of intermittent testing in the 1 a.r.r.nc.: clu tone & s. nik. Scleu R.utor Engineennt, c.pynghi ix.f. Page 9 I
i Storage & Fuel Removal / 9.1 range of 2 to 3 percent of full power. This testing program results in the operation of the reactor for the equivalent of approximately 45 minutes or 3/4 of one effective full power hour. The Plan conservatively assumes an irradiation time of approximately twice that expected during low power testing. Decav flest Load Tim. Af ter Reactor Shutdown P/P- liW BTU /IIR 30 days 2.02 x 10 8 3.45 1.18 x 10' 60 days 8.88 x 10 8 1.51 5.17 x 108 90 days 5.48 x 10 e o,93 3,39 xjos I80 days 2.39 x 10 8 0.41 1.39 x 108 365 days (1 yr) 1.03 x 10 8 0.17 5.97 x 108 730 days (2 yrs) 4.47 x 10 7 0.08 2.60 x 108 1095 days (3 yrs) 2.75 x 10 7 0.05 1.60 x 108 1460 days (4 yrs) 1.95 x 10 7 0.03 1.13 x 108 The estimated time of storage of fuel onsite is 47 months from the day the first fuel assembly enters the fuel storage pool until the final fuel assembly is loaded for shipment. Since the decay heat load is an insignificant value no specific provisions will be made for the fuel storage pool cooling. The heat load will be dissipated through surface evaporation from the fuel storage pool, ambient , losses through the walls of the fuel storage pool and ambient ;osses through I the fuel storage pool cooling system which will be run in the recirculation ' mode. Makeup to the pool for evaporative losses will be supplied on an as needed basis. For the purpose of this study the fuel will be shipped overseas to Europe for reprocessing. Fuel shipments are estimated to take 30 months by l initially utilizing the NRC and DOT approved TN 8 shipping cask ; manufactured by Transnuclear, of which two are avaliable for use, and then, i after NRC approval, the Isrser capacity TN-12 cask. Each shipment , utilizing the two TN 8 casi:s will move 6 fuel assemelles and take the ' following tim:: . ! t l 1 t
- Page 9 2 .
_ _ _ . _ _ - - _ ~ -, -- _--
Storage & Fuel Removal / 9.1 Load and wash cask, ship to U.S. Port 2 days Travel by sea U.S. Shipping Port to LaHague, France 14 days Transportation from port to processing facility 3 days and off loading
- Return cask to port 2 days Travel by sea La Hague, France to U.S. Port 14 days U.S. Port to Seabrook Station Iday Total Round Trip 36 days 32 shipments at 36 days = 1152 days I load remaining assemblics ship to U.S. Port = 2 days 1154 days This equates to approximately 38 months. However,it was assumed that this time can be reduced to 30 months as stated above by having a new TN.12 shipping cask approved by the NRC in parallel with the contracting and permitting cycle which is estimated to take 18 months.
Page 9 3
Storage & Fuel Removal / 9. 2 SCIIEDULE LOGIC Page 9 4
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Storage & Fuel Removal / 9. 4 ETOR AGE AND PREPAR ATION FOR REh10 VAL OF FUEL ESTIhf ATE BACK-UP
- 1. PURCIIASE OF 48.000 GALLONS OF DEhflNER ALIZED WATER
- 2. OFF LOADING WATER Cle w ,
4 Men Duration 18 months at 4 hours per month 30 months at 8 hours per month 2 men x. 4 hrs / man / month x 18 months = 144 hrs 2 mou x 8 hrs / man / month x 30 months = 480 hrs 624 hrs
- 3. LOA DING FUEL ELENf ENTS INTO CASK. WASIIING AND DECONTAhtlNATING CASK EXTERIOR LOADING TRUCK Crew
$ Mechanics Duration 2 days 5 men x 8 hrs / day / man x 2 days / ship. x 33 sh.'oments = 2640 hrs
- 4. DfCONTA5flNATION AND CLEAN UP OF FUEL BUILDING AFTER EACil
, SIIIPSf ENT Crew 4 Utility Technicians Duration i day per shipme.it 4 men x 8 hrs / day / man x 1 day / ship. x 33 shipments = 1056 hra Page 9 9
DECONTAMINATION OF FUEL STORAGE BUILDING l TABLE OF CONTENTS l t SECTION DLSCRIPTION PAGEe i 10.1 Decontamination of I' vel Storace 10 1 i Huilding Schedule Logic 10 - 3 l 10.2 10.3 Cost Estimate / D 5 10 - 5 f 10.4 Estimate Back up 10 - 8 l l l l 1 l i h l I i k t i
Decontamination of Fuel Storage Building / 10 . 1 DECONTAS11N ATION OF FUEL STOR AGE BUILDING PURPOSE: Sample, monitor, and decontamination, if necessary, of the fuel storage building to release it for unrestricted use upon shipment of the final fuel assemblics from the site. ASSUNIPTIONS:
- 1. Local decontamination of building is performed after each fuel shipment to maintain cleanliness and reduce contaminatioa levels.
- 2. IIEPA filters perform as designed and no radioactive contamination occurs down stream of the filters.
- 3. Fuel Building Control Center abandoned in place.
- 4. Single shift operation five days per week.
- 5. Decontamination work performed by contractor utilizing construction craf ts.
DESCRIPTION OF ACTIVITIES Upon the ship.nent of the last fuel assembly, the fuel storage building will be decontaminated if necessary, in order to release the facility for unrestricted use. The first step will be the drainage and processing o the water contained in the fuel storage pool followed by flushing and cleaning of the fuel storage cooling system piping system and the pool walls, racks and floors while the portable resin demineraliter system is on site. The fuel storage pool cooling system will be flushed with potable water similar to the process utilized in Section Seven to decontaminate the piping
, systems. The solution will be dumped into the fuel storage pool in order to process the water through the portable resin system. While the portable system is still on sit e the fuel storage pool walls, racks and floor will be ; wushed utilizing a hydrolaser in order that water can be processed. Final decontamination of the fuel storage pool, racks and fuel handling equipment will be due utilizing hand wipe downs.
Pate 10 I
Decontamination of Fuel Storage Building / 10 . 1 t Simultaneously with cleaning the fuel storage pool and fuel handling equipment the balance of the building will be surveyed and if required decontamination of the datwork, disposal of the HEPA filter units and decontamination of t! e filter housing will be performed. Decontamination will be schieved by hand wipe downs. Radiation surveys by liesith Physics personnel will be done throughout the aforementioned decontamination processes to insure that relesse levels for unrestricted use are a:hieved, maintained and documented. Wall surfaces, t liner surfaces, and other components will be swiped and tested on pre-determined intervsts to insure release levels for unrestricted use. Piping and ductwork systems will be swiped both internally and externally through removsl of valse and damper internals, removal of mechanical equipment, and removal of system low points where contamination maybe likely to settic. Upon completion of decontamination work, a final survey will be taken of the building and its contents prior to the release for unrestricted use. An estimated 288 cubic feet of low level waste will be generated from rags, protective clothing and other consumables utilized in the decontamination l process. In addition 918 cubic feet of HEPA and charcoal filter media will i have to be disposed. Disposal of low level radwaste will be accomplished by packaging the waste in an estimated eleven Department of j Transportation approved transportation containers and shipping to an approved low level waste disposal site. ; l i e i Page 10 - 2
Decontamination of Fuel Storage Building / 10. 2 SCHEDULE LOGIC Page 10 - 3 1
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CLIEmi : #41 DESCRIPil0N Of WO8E DECoulAmtmATION OF Tuf F E L STORAE SulLDluG (POST LOW POWER lE5f th&) ESTIMATE u0.3 D-5
<<<.......Unil 84fES--+--~ SUS OT*f l DESCRIPT80m um MAT *L S lmmeslm-meS MATE RI AL g LA80s CCmIRACT TOTAL Mamma Jes FUEL 510kAM SLDC:
ftU5m PipleG Amp SET UP PORT- 1 L1 546,000 320 122 60 S46,000 57,212 553,232 320 ASLE REstu SED DEnsuf:Att2Ets Deals Amo Pe0E 55 FUEL SioeArd 1 L1 160 122.60 50 13,616 S3,616 160 wife FLUSN fuel STORAE POOL PIPC ST 1 L1 200 122.60 SO S4,520 S4,520 200 Pa00F fLUSN 1 L1 40 S22.60 SO 5904 1904 40 REmowt wALVE5 1 LS 268 122.60 SO 16,057 56,05T 268 CUT LOW P'sINT PIPmG 1 LS 93 $22.60 SO S2,102 S2,102 93 OPEN mEf,E ENCmAeGEts 1 ts 40 $22.60 SO $904 5904 40 g uANDLE PIPE 1 15 408 122.60 SO 19,221 19,221 408 an PROCE'-5 WiER 1 LS 16 $22.60 SO 1362 1562 16 f4 rem 0wE TEMP PIP 3mG 1 LS 160 S22.60 SO S3,616 S3,616 160 0 CLEAu FUEL STORAE Poot DECom DUCfwomit 1 1 L1 LS 1,280 810
$22.60 S17.30 SO SO S23,9?8 S14,013 S28,928 S14,013 1280 810 as etmowt REPA & CHAeCOAL FILitts DECon FILTEa ConPAafmEmi 1 LS L1 96 160 S16.20
$17.30 SO S1,555 S2,768 51,555 12,768 96 g 1 SO 160 -.
.g so NP SAMPLE SulLDitG ST5 FEM ENTERIORS 1 L1 48 S24.86 SO 11,193 S1,193 48 g y 5 etmowE 5F ST5ffe PeoCE55 1 15 96 S22.30 SO S2.141 12,141 96 y InsietsIEmis i f DECom INSTRUMEuT1 1 LS 80 S22.60 SO S1,808 S1,808 80 O m!$CELLANEOUS BUILDluG MC0m 1 LS 640 516.20 SO S10,368 S10,368 640 Amp CLEAN tr
- MP SURVETS i L5 T20 124.86 SO S17,899 517,899 720 T fImAL SUILDimG CLEAs UP S16.20 13,240 S3,240 etm0WE CNECK WALwE IuTEenALS 1
1 15 L1 200 16 S22.60 SO 50 S362 1362 200 16 - h DECON CNECC wAtwE tuTEseALS 1 L5 16 122.60 SO S362 S362 16 SNIP 40W LEwEL WA$iE CouTAlutti 1 L5 S99,840 0 122.60 S99,840 10 $99,840 0 (f,3 c IhCLUDING DISPOSAL O
==
DE SEI MISC. DIRECT mAi*L S6,158 S6,158 m E5E OF DieECT LAeos) g Sus TOTAL DIRECTS $151,998 S123,170 50 S215,768 5,867 b CL. SMALL TOOLS & Consist. SO SO -- 3 OEI N INDIRECT LASOR: E15% OF DIRECT LAeon) SO S18,4T5 to S18,4T5 880 p C WoumANUAL SO S30 T92 So 1,467 . (25% OF DinECT Lae0R) S30.T92l g 3
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j m... . . . .uu g t R A TE S--- ---- 508 l DESCRIPTION l ST Um senT*L S lM-Ne$lM-NRS MATERIAL EABOR C047RACT TOIAt lasAm#0URS
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IIEALIN PWT5ICS TECNulCIAm$ SO SO SO S0 0 ENGINEER!bGs UEEC 0 seu 10 10 ansi 0 au SO SO TAEC 0 nn SO SO CONSULTAmi 0 sue SO SO SUS-TOTAL S151,998 S172,433 SO S324.4 % 6.74 7
=0mm auAt REC & On u ,005 u ,005 O m
(houseAs S . 30%)*152 C1 O ENG1mEEkluG f EE & ON SG 10 g (U[1C EmCIN 5 +301)*30% re TOTAL E5fisen1E 3 (peases 0URS ARE CRAf f OnLY) sis 8,003 S172,438 SO S330,441 6,747 --- 7 i
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" C TOTAL DIRECT COST S151,996 1123.170 50 S275,168 5,867 m M S18,475 S0 $18,475 800
- TOTAL INDIRECT CDST SO O
==
SB 101 At esomsensuAL S6,005 530,792 SO SM,797 54 8 (ImCiteES FEE & On) G C 101AL ENGINEERimG SO SO SO So =: (luCLLSES FEE & On) Q.
.3 TOTAL E5f tsenTE S158,003 5172g*33 SO S330,441 6747 gg usE l l l l l ll Si5s,0m l sit 2,4m l SG 1 Sm,400ll 6747 %
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Decontamination of Fuel Storage Building / 10 . 4 DECONTAbflNATION OF FUEL STOR AGE BUILDING ESTISt ATE B ACE-UP
- l. INSTALL ATION OF FLUSH PIPING AND SET UP OF PORTABLE RESIN BED DE511NER ALIZERS Crew
$ Pipefitters to install piping, make connections to system and portable demineralizers.
Approximately 150 cf of 6* pipe required Duratior. 8 ds); 5 men x 8 hrs / day /msn x 8 days - 3:0 hrs
- 2. DR AIN AND PROCESS FUEL 2 TOR AGE: POOL WATER Crew 2 Pipetitters standby Duration Parallel train of resin demineralizer will process approximately 100 gnm with a volume of 466,000 gals. in the fuel " ,4ge pool it will take 10 days working 8 hrs /osy to process the water men x 8 hrs / day / man x 10 days = 160 hrs
- 3. FLUSHING FUEL STORAGE POOL PIPING SYSTENI
. Crew 5 Pipefitters to perform valve 1.8ne ups, string hoses, install sample filters Duration 5 days 5 men x 8 hrs / day / man x 5 days = 200 hrs Itema not required tr Plan tuumptione de prove to be conprvative Page 10 - 8
I Decontamination of Fuel Storage Building / 10 . 4
- 4. PROOF FLt1SH ,
Crew 5 Pipefitters Duration I day for flush 5 men x 8 hrs / day / man x ! day = 40 hrs (
- 5. NBtOVFVALVES Disconnect remote valve operators !! @ 8 hrs /es = 88 hrs Remove motor or air operators 7 @ ll/ hrs c2 = 77 hrs Remove valve internals 21/2 to 4' 00 @ 3.25 hrs /es = 65 hrs
{ Remove valve internals 6 to 8' 7 @ 5.4 hrs /ca = 38 hrs 268 hrs i Crew ( 4 Pipefitters [ Duration 8 days
- 6. CtfT t.OW POIN T PIPING f
Assume 25% of piping in system is of either a configuration that could trap contamination or low points in the system Cuts: I 2' 1645 If x 0.25%/10 pt/ cut = 41 cuts @ 0.9 hrs = 37 hrs 21/2 to 4* 1388 If x 0.25%/10 f t/ cut = 35 cuts @ 1.24 hrs = 43 hrs ' 6 to 8' 1 6 If x 0.25%/10 f t/ cut = 3 cuts @ 2.23 hrs = 7 hrs l 10 to 14* 1:0 if x 0.25%/10 f t/ cut - 3 cuts @ 5.2 hrs = ifLhn i
, 93 hrs (
llandle Pipe O' and less 40 pieces x 3 hrs /ca [
= 120 hrs
- 1/2 to 4' 34 pieces x 4.8 hrs /es = 163 hrs [
6 to 8' : pieces x 7 hrs /ca = 14 hrs ! 10 to 14' : pieces x 9 hrs /ca = 1R hrs 315 hrs Tetal 408 hrs Crew 5 Pipefitters Duration 10 days Page 10 - 9
Decontamination of Fuel Storage Building / 10. 4 t
- 7. OPEN llE AT EXCil ANGERS '
P Crew 5 Piperitters Duration I day 5 men x 8 h../dsy/me.n x 1 day = 40 hrs
' 8. PROCESS WATI d Crew 2 Pipefitters Durstion Parallel train of resin demineralizer will process approximately 100 gpm with a volume of 15.000 gal, in the FS system and 10,000 3s1. from waning fuel storage pool it will take i day working 8 hrs /dsy to process the water
- men x 8 hrs / day x ! day = 16 hrs
- 9. REMOVE Tf31P PIPING Crew 5 Pipefitters Duration 4 days 5 men x 8 hrs / day /msn x 4 dsys = 160 hrs
- 10. CLE AN FUEL STOR AGE POOL Crew 8 Laborers to wash pool with hydro laser including racks. Rig staging and hanc* wipe walls, racks and floor including the fuel handling equipment.
Duration 20 days 8 men x 8 hrs /dsy/ man x 20 days = 1280 hrs s Page 10 - 10
Decontamination of Fuel Storage Building / 10 . 4 I
' 1 1. DECONTAS11NATE DUCTWORK Crew 8 Laborers to hand wipe interiors !
2 Sheetmetal workers to open ductwork Durttion 10 days 16.200 sf @ 0.05 hrs /sf = 810 h : o
- 12. REMOVE IIEPA AND Cil ARCO AL FlJMS Crew 3 Laborers - remove filter elements lower to ground floor and place in shipping containers Duration 4 days 3 men x 8 hrs / day / man x 4 days = 96 hrs 6
- 13. DECONTA A11N ATE FILTER CON 1P ARTS 1ENT Crew !
4 Laborers to hand wipe filter compartment Duration 5 days ' 4 men x 8 hrs / day / man x 5 days = 160 hrs i i
- 14. HE ALTil PflYSICS S ANtPLE BUILDING SYSTEN1 E\*TERIORS l Crew 2 Ilealth Physics Technicians f
Duration 3 days 2 men x 8 hrs / day / man x 3 days = 48 hrs l l I 1 I Page 10 - 11 ;
l Decontamination of Fuel Storage Building / 10. 4
' 15. RESIOVE FS SYSTES1 PROCESS INSTRifS1ENTS Crew ,
2 Pipefitters 2 Electricians Duration 3 days 4 men x 8 hrsiday/ man x 3 days = 96 hrs s
- 16. DECONT ASilN ATE INSTRlf SIENTS Crew ,
2 Pipefitters hand clean instruments Duration 5 days 2 men x 8 hrs / day / man x 5 days = 80 hrs
- 17. 511SCELL ANEOtfS Btt!LDING DECONTASilN ATION AND CLE AN lf P
{ Crew i> 2 Laborers . sweep and wash floors, etc. < Duration 40 days [ 2 men x 8 hrs / day / man x 40 days = 640 hrs ! L
- 18. IIE ALTil PilYSICS Stf RVEYS l Crew f 2 Health Physics Technicians !
Duration 45 days 2 men x 8 hrs / day / man x 45 days - 720 hrs l t
- 19. FIN AL BtflLDING CLE AN tf P Crew ,
l 5 Laborers , Duration 5 days 5 men x 8 hrs / day / man x 5 days = 200 hrs l Page 10 - 12
t i Decontamination of Fut ; Storage Building / 10 . 4 l
- 20. REMOVE CIIECK V ALVE INTERNALS I Crew '
2 Pipefitters Duration I day I
- r. ten x 8 hrs / day / man x ! day = 16 hrs [
t
- 21. DECONT A\11N ATE Cl!ECK V ALVE INTERNALS Crew j
Pipefitters Duration 1 day , men x 8 hrs / day / man x ! day = 16 hrs
- 22. SHIP LOW LEVEL WASTE CONTAINERS INCLUDING DISPOSAL 630 cf of charcos' media = 21,600 lbs 288 cf of HEPA media Will require 9+ containers to ship filter media
( Assume two additional containers required for misc. rags, visqueen, etc. and the remaining media equals 11 containers to ! b: purchased at a cost of 5600.00 c3 and the shipping and ; disposal of 1036 cf @ 590.00/cf . l t i
. r l
t i l I Page 10 - 13 L
I Supporting Operations j r f I TABLE OF CONTENTS r i SEC1f0N DESCRIPTION EAGEe ( l 11.1 Supporting Operations 11 . I " 11.2 Non Manual Manpower & Cost 11 3 Estimate ,
! !.3 NRC Fees 11 6 11.4 Insurance 11 7 !
6 I i l I i I l t l ( i
Supporting Operations / 11.1 SUPPORTING OPER ATIONS PURPOSEr To identify activities and their cost that are associated with the direct work activities discussed in the previous sections of this report,
- l. Management
- 2. Supervision
- 3. Regulatory Services 1 Engineering .
- 5. Operations
- 6. Chemistry 2
- 7. Ilealth Physics
- 8. Administrative Support
- 9. Security 1 10. Quality Assurance
- 11. NRC Fees
- 12. Insurance I
Y DESCRIPTION OF ACTIVITIES
- 1. Mannaement: Personnel required to oversee the various organizations necessary to return Seabrook Station to unrestricted use. This group is comprised of the Project Manager responsible for the actual work activities and a Corporate Executive to assist licensing, contractual
] items and corporate matters.
- 2. Sumer*lilon: Personnel required to oversee the specific work activities of the groups performing the work and administrative duties of time card approval, salary administration and staffing levels.
- 3. Reaulatory Servleen: A group of personnel required to prepare the documentation and support the lleensing process necessary to obtain approval of The Plan for returning the facillt) to unrestricted use, obtain a possession only license, obtain necessary permits for shipment of fuel and low level waste and support contract preparation for fuci and low level waste disposal, and determination of the license.
.i . Ennimeering Personnel required to determine flushing paths for decontamination of systems, prepare valve line ups and identify the j valves. Identify location of piping to be removed for health physics i
surveys, prepare pipe routing for temporary piping runs necessary for ] flushing the systemt. This group will also identify the sequence of events and prepare schedules as well as resolve engineering problems such as rigging and supporting of components as they are cut. Page 11 1 i
Supporting Operations / 11,1 Preparation of an Environmental Report Supplement addressing activities associated with interpretation of the Plaa.
$. Oserations: The personnel that operate the permanent plant equipment necessary to return the plant to a saft unrestricted condition, such as auxiliary boiler, fuel handling equipment, station alt, circulating water and HVAC systems. This organization will staff the job site around the clock by utilizing five shifts, until the majority of activities are completed.
- 6. Chemistrvt This group will be responsible for supporting direct work through the analysis of samples and maintaining water chemistry.
- 7. Health Phssics: The organization responsible for surveying the facility and its components for radiation !cvels. Initially, during r.Il decontamination operations and finally, prior to releasing Seabrook Station for unrestricted use. This group has functione throughout the direct activities; however, they also have times when they can be doing surveys that are not restraints to the direct activities. Therefore, to simplify estimating, they were considered as support.
j 8. Adrainistrathe Summert: The category is made up of the following: A. Clerical: Secretaries preparing reports, letters, etc. l B. Recordkeeping: Personnel responsible for maintaining and filing l the necessary documentation to satisfy the regulatory
. requirements.
l C. Materials and inventory: Individual responsible for maintaining inventories of equipment and supplies required to support returning the facility to unrestricted use.
- 9. Securitrr The organization responsible for the security and protection of fuel in compliance with NRC requirements, including the owners property.
- 10. Omality Assurgggg; The organization responsible to insure quality is maintained throughout the process of decontaminating the project and removing the reactor vessel from the site, and to insure compliance to procedures and regulatory requirements.
II. NRC Fees: The cost imposed by the Nuclear Regulatory Commission in the form of annual fees, inspection cost and review and approval of license amendments.
- 12. Isaurance: The cost for nuclear property and liability insurance as required by the NRC as well as general liability insurance carried to protect the owners.
l
' ?ge II
- 2
h Supporting Operations / 11, 2 1 1 i 4 NON St ANUAL. .\t A N POWER
& COST ESTI5f ATE c
i 4 1 1 4 f i 1 J l 1 k Page 11 3
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. m u. m . m .u . .. - m m . .. .u m .. m u - m u..u m . m . .... m .o.u m m . m m .. m .. m m . m m m u m .
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- OPtaatOus manacts 1 1 1 1 1 1 1 1 1 1 1 1 1 1
$e0*$ 15 15 15 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 h AO*s 25 1
25 25 3 3 3 3 3 3 3 1 1 1 1 1 1 1 1 1 3 1 3 1 3 1 3 1 1 1 1 m surroni 1 1 1 1 1 1 1 C Catels1Rf SurfRVISOR 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 s 1 1 1 1 1 1 *13 Catelsis 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 *13
..................... ........................................................................................................................... C3 Cate stav ftCws 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 E MP suPtevis0R 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 {
MP ftCumIClaes 3 3 8 3 ft 8 8 3 3 3 8 3 3 3 1 1 1 1 1 1 1 gg suPPott 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 assus suPtevison 2 2 2 2 2 2 2 2 2 2 2 2 2 2 O
..................... ............ .............................................................................................................. T utillists sur'evison s(Cuelty surt#wison 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 as situatir suanos 40 as 40 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 15 15 15 15 15 15 15 15 15 C. IEC surtevisca 1 1 1 1 1 1 1 1 1 1j 1 1 1 1 g O
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.-=. . .-
31 32 33 m34 35 36 3r 38 39.n40..41 it 43 44 45 46 4r 48 49 50 51 52 monius mours tuttuityt
. .. . . .m.m . . -. .. . . .m.m. n .m . . . . u . . .m . . . .u..n u ..u m . . m um 24 8 4,159 5110,218.80 Pe0 JECT mamacts 24 4,159 S110,218.80 tNwIRommtsiAL inG 24 4,159 5110,218.SC futt&t0W twt W5T teG 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 52 9,012 1238,50r.t3 uCutaiO.f stevlCts 10 1 7s us,924.50
.....,..3. ............_..
futt SNIP & LISCtest && 6,912 S193,698.00 CatalCAL SUPromi 48 8,318 S190,241.81 e4 , 48 8,318 $220.43r.60 DEConDS at[PimG 48 8,318 S190,241.81 . natteints & Isute10af r6 5501,216.20
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....... ......... ............... g 9 STSif#5 ftCimites 84 14,55r S585,r65.80 en 8E ACTOR ENGluttet 3,639 l 88 21 996,441.45
** SCutDULitG 21 3,639 996,441.45 teGlettPS J r,2r9 S192,882.90 s
** Ortaallons menacts 14 2,426 964
..................... ........................................................................................ ........ ......... ........,294.30 ta smo*1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 115 19,930 S528,131.r5 A0*S 188 18,r16 S428,044.Or SUPPosi CatMister supe #wison 24 4,159 995,120.90 y 24 4,15 9 S110,21s.80 Cut #I5fS 6
.D 35
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28 4,159 4,852 5 ,5,i20.90 S128 o c
........ ......... ........,588.60
....... vg WiltITIES SUPf tvison 2,426 14 S64,294.30 Q SECualTV suPtevl50s 21 3,639 995.441.45 c.
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W I I DO 3
Supporting Operations / 11. 3
,Nac rrrs Fees paid to the Nuclear Regulatory Commission as prescribed by law for services rendered. Such services include inspections, review of licensing requirements, development and compliance with regulatory requirements and notification of inoustry trends, i
For the purpose of this estimate fifty percent of the annual fee was includ ed, approsimately 5640,000, along with an estimated cost of 5150.000 i for review of the license adjustment to possession only, inspection fees i we,e also included at 518,000 per month for three months until the l
- incense is adjusted. Three montns at 59.000 per month during the initial phases of the decontamination operation,53,300 per month for fifteen months or until reactor demoliticin and disposal is successfully completed, and twen'y seven months at $1700 per month or until the final fuel shipment ! caves the site for a grand total of 5966,400.
n i 1 4 4 4 I f Page 11 6
1 1 Supporting Operations / 11. 4 l INSURANCE i l i Cost of the insurances imposed by law on nuclear utilities which include l l Nuclear Property insurance and Nuclear Liability insurance as well as i i General Liability insurance carried by the owners, t 1 For the purpose of this estimate three months of Nuclear Property ! Insurance was included at the present premium equaling an amount of l 51,154,000 and $1 0.000 for three months of Nucle,ar Liability, With the l e change of the license to posses. tion only at the end of three months Nuclear Property insurance was dropped and Nuclear Liability premiums reduced to a rate of $2,000/ month for the balance or a total value of 598,000. General Li.ibility estimated to be 52,626,000 for the full duration of the operation for a grand total of $3,998,000, i e h I i t
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