ML20128B949
| ML20128B949 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/30/1992 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13319B043 | List: |
| References | |
| NUDOCS 9212040168 | |
| Download: ML20128B949 (125) | |
Text
{{#Wiki_filter:. . _- - - -_ . - - - - - - - - - . - .. - ENCLOSURE 1 i , Preliminary Decommissioning P' an t for the San Onofre Nuclear Generating Station Unit 1 Novem3er 1992 i O!o$ 6
TABLE OF CONTENTS Pace No. 1.0 SUMARY OF PLAN ........................... 1 1.1 G e n e ra l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.2 Major Decomissioning Activities . . . . . . . . . . . . . ... 2 1.3 Organization of Prelimin6ry Decomissioning Plan . . . . . ... 2 2.0 CHOICE OF DECOMISSIONING ALTERNATIVE AND DESCRIPTION OF ACTIVITIES INVOLVED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2.1 Background Information . . . . . . . . . . . . . . . . . . ... 4 2.1.1 Facility Description . . . . . . . . . . . . . . . . . . . 4 2.1.2 Operating History _. . . . . . . . . . . . . . . . . ... 4 2.1_3 SONGS 1 Premature Shutdown . . . . . . . . . . . . . . . . 5 2.2 Site-Specific Factors Affecting Decomissioning Planning . ... 6 2.3 Selection of Decomissioning Alternative . . . . . . . . . ... 7 2.4 Decommissioning Activities . . . . . . . . . . . . . . . . ... 7 2.4.1 Categorization of Systems Required for SAFSTOR . . . . . 7 2.4.2 Planning Phases for Shutdown and Decomissioning . . . . . 8 2.5 Decommissioning Schedule . . . . . . . . . . . . . . . . . ... 9 2.6 Decommissioning Organization and Responsibilities . . . . . . . 10 2.7 Training Program . . . . . . . . . . . . . . . . . . . . . . . 10 2.8 Contractor Assistance . . . . . . . . . . . . . . . . . . . . . 10 3.0 PROTECTION OF OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY . . . . . . 13 3.1 Radiological Status . . . . . . . . . . . . . . . . . . . . . . 13 3.1.1 Operating History . . . . . . . . . . . . . . . . . . . 13 3.1.2 Current Radiological Status . . . . . . . . . . . . . . 13 3.2 Radiation Protection . . . . . . . . . . . . . . . . . . . . . 14 3.2.1 ALARA Program ....................e . 14 3.2.2 Health Physics Program . . . . . . . . . . . . . . . . . 14 3.2.3 Radioactive Ef fluent Program . . . . . . . . . . . . . . 15 3.3 Radioactive Waste Management ._. . . .. . . . . . . . . . . . . 15 3.3.1 Fuel Disposal . . . . . . . . . . . . . . . . . . . . . 15 3.3.2 Radwaste Processing . . . . . . . . . . . . . . . . . . 16 3.3.3 Radwaste Disposal . .. . . . . . . . . . . . . . . . . . 17 3.3.4 Radioactivity Analyses . . . . . . . . . . . . . . . . . 17 3.3.5 Other Radioactive Waste . . . . . . . . . . . . . . . . . 18 3.3.6 Status of Low-Level Dis . . . . . . . . . 18 3.4 Accident Analyses .- . . . . . posal Facility
. . . : . . . . . . . .. . . . . . . 18 3.5 Environmental Protection Program . . . . . . . . . . . . . . . 19 3.6 Fire and Occupational Industrial Safety . . . . . . . . . . . . 19 4.0 FINAL RADIATION SURVEY . . . , . . . . . . . . . . . . . . . . . . . 20 5.0 DEComISSIONING COST ESTIMATE . . . . . . . . . . . . . . . . ... . . 21 5.1 Certificate of Financial Assurance . . . . . . . . . . . . . . . 21 5.2 Decommissioning Cost Study . . .. . . . . . . . . . . . . . . . 21
-i-
_ _ _ - - _ _ - - A
TABLE OF CONTENTS (Continued) Pace No. 6.0 TECHNICAL AND ENVIRONMENTAL SPECIFICATIONS IN PLACE DURING DECOMMISSIONING ..........................23 6.1 Technical Specifications . . . . . . . . . . . . . . . . . . . 23 6.2 Environmental Specifications . . . . . . . . . . . . . . . . . 23 7.0 QUALITY ASSURANCE PROVISIONS IN PLACE DURING DECOMMISSIONING , . . . 25 8.0 7HYSICAL SECURITY PLAN PROVISIONS IN PLACE DURING DECOMMISSIONING . 26 APPENDIX At Letter and Certificate Assuring Availability of Funds for Decommissioning APPENDIk B: Decommissioning Cost Study for the San Onofre Nuclear Generating Station
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1.0 SUPHARY OF PLAN 1.1 General Southern California Edison Company (SCE) has permanentl San Onofre Nuclear Generating Station, Unit 1 (SONGS . As is 1)y shutdown th discussed in Section 2.1.3, the permanent closure of SONGS 1 was the outcome of a mutual settlement agreement between SCE, San Diego Gas and Electric (SDG&E), and the California Public Utilities Commission. l The U. S. Nuclear Regulatory Commission (NRC) was notified of SCE's i decision (Reference 1-1) and SCE subsequently submitted an l application for a Possession Only License (Reference 1-2). The Possession Only License was issued on October 23, 1992 (Reference 1-3), to be effective upon the permanent cessation of cperations and the receipt by the NRC of a letter certifying that all fuel has been offloaded from the core and stored in the spent fuel On August 11, 1992, the California Public Utilities Commissiun p(ool.CPUC) unanimously approved the agreement to permanently shutdown SONGS 1. As discussed in Section 2.3, SCE has selected the SAFSTOR option for the following reasons:
- SAFSTOR provides for reduced occupational radiation exposures as residual radioactivity decays over the dormancy period;
- SAFSTOR allows time for the industry to denlop facilities for the storage and disposal of spent fuel; and
- SAFSTOR allows coordinated d smantlement and restoration of the entire site when SONGS 2 and 3 are decommissioned.
As required by 10 CFR 50.33(k)(2), SCE has certified inat the minimum amount of funds to decommission SONGS 1 is being collected (Reference 1-4). SCE conducted a decommissioning cost study in 1990 that estimated that the total costs to return the site to its original condition would be $238.4 million (1990 dollars). As authorized by the CPUC, SCE's current collection rate is based on this funding goal. Due to the premature shutdown of SONGS 1 on November 30, 1992, SONGS 1 will be placed in SAFSTOR in 1993 as oppsed to the original shutdown date of 2004. Another cost study will be conducted in 1993 in support of SCE's 1995 General Rate Case and SCE will adjust its collection rate. SCE will continue to adjust its collection rate, as appropriate,19 subsequent rate cases. As required by 10 CFR 50.75, this Preliminary Decommissioning Plan (PDP) discusses SCE's tentative plans to decommission SONGS 1 as efficiently as possible. Draft Regt1ctory Guide DG-1005, " Standard Format and Content for Decommissioning Plans for Nuclear Reactors" (Reference 1-5) was used as guidance in preparing the PDP. As recommended in DG-1005, the PDP will be substar.tially lass detailed than the Proposed Decommissioning Plan that is required by 10 CFR 50.82. The Proposed Decommissioning Plan will be submitted within Page 1 of 26
. _ - - - .-- - - -. - . - - . - _ -. . . . = . - - - - - - - - .
i L twoyearsfvllowingplantshutdownandwillincludetheavailable information on SCE s plans to decommission SONGS 1. f-SCE acknowledges that 10 CFR 50.75(f) requires a Preliminary
- Decommissioning Plan to be submitted-"five (5) years prior to the ~
projected end of operation." Since the decision to prematurely shut down SONGS 1 was recently made, this submittal of-the PDP does not comply with the five year requirement. In order to meet the intent of the regulations, however, SCE is submitting the PDP within a reasonable tioe of the decision to permanently shut down SONGS 1. i 1.2 Major Decommissioning Activities 1 SCE's initial decommissioning objective is to safely and efficiently ! place SONGS 1 into SAFSTOR. It is anticipated that SONGS 1 will remain in SAFSTOR until the entire site is decommissioned. The operating licenses for SONGS 2 and 3 tre currently scheduled to- . expiit on October 19, 2013. If the' operating licenses for SONGS 2 and . 2" ienewed SAFSTOR for SC#GS 1 could be extended an
- additi;6a? period.- The major activities associated with the decommissioning of SONGS 1 are listed-below.
- Obtain Possession Only License (P0li
- Obtain regulatory relief from operating requirements that are no longer appropriate for a shutdown plant.
Submit Preliminary Decommissioning Plan i e Shutdown plant and offload core l
- Place plant in SAFSTOR configuration j
- Obtain Permanently Defueled Technical Specifications
- PerfoSm site characterization
- Submit Proposed Decommissioning Plan
$ = Obtain Decommissioning Order
- Implement decccaissioning activities l
Conduct final radiation survey
. Terminate Part 50 License
- 1.3 Organization of Preliminary-Decommissioning Plan The format suggested in the Draft Regulatory Guide DG-1005, " Standard Format and Content for Decommissioning Plans for Nuclear Reactors,"
has been used in preparing this Preliminary Decommissioning Plan. Page 2 of 26 4 e e- t ,, . . , - - ,y - ,, r -r , *y,-- .-
Section 2.0 provides background information regarding the description of SONGS 1, the operating history, and the reason for the premature shutdown of-SONGS 1. It also describes SCE's )roject organization, scope of training, and intentions related to tie use of contractor assistance. Also discussed are SCE's selection of SAFSTOR as the-decommissioning alternative, and the related activities and tasks. Sectior 3.0 describes the radiological status of the-facility and disem 1 the radioactive waste management program for decommissioning. Radiation protection, accident analysis, hazardous ? waste, and fire / industrial safety are also discussed. Section 4.0 discusses the residual radioactive contamination release criteria and the final radiation survey plan. The final radiation survey will assure that the site is suitable for unrestricted use and that the NRC may terminate the license, , Section 5.0 contains a description of the amount of funds that SCE certified would be available for decomissioning funding. The results of a 1990 cost study and plans to conduct another cost study. in 1993 are also discussed. Section 6.0 discusses the Technical Specifications, the environmental specifications, and other administrative controls. Finally, Sections 7.0 and 8.0 discuss the. provisions for Quality Assurance and Security Plan respectively. REFERENCES 1-1. Letter, H. B. Ray, SCE, to T. E. Murley. U. S. Nuclear Regulatory Commission, dated January 15, 1992, 1-2. Letter, H. B. Ray, SCE, to Document Control Desk, U. S. Nuclear l Regulatory Commission, "Aundment Application No. 203," dated April 2,1992, 1-3. Letter, J. O. Bradfute, U. S. Nuclear Regulatory Commission, to H. B. Ray, SCE, " Issuance of Amendment for the San Onofre Nuclear Generating _ Station, Unit No. 1 (TAC NO. M83123)," dated October 23, 1992, 1-4. Letter, H. B. Ray, SCE, to Document Control Desk, U. S. Nuclear 3 Regulatory Commission, "1; CFR 50.33(k)(2); Report Assuring the
-Availability of. Funds for Decommissioning, San Onofre Nuclear Generating Station, Units 1,'2, and 3," dated July 24, 1992, 1-5. Draft Regulatory Guide DG-1005, Standard Format and Content for ;
Decommissionina Plans for Nuclear Reactors, U. S. Nuclear Regulatory Commission, September 1989. Page 3 of 26
2.0 CHOICE OF DECOINISSIONING ALTERNATIVE AND DESCRIPTION OF ACTIVITIES INVOLVED 2.1 Background Information 2.1.1 facility Description The San Onofre Nuclear Generating Station (SONGS) is located on the southern California coast in San Diego Cour ty, approximately 62 miles southeast of Los Angeles and approximately 51 miles northwest of San Diego. Figure 2-1 shows the general location of the station. The site is located entirely within the boundaries of the U.S. Marine Corps Base, Camp Pendleton, California, near the northwest end of the 18-mile shoreline. The site is about 4,500 feet long, 800 feet wide. and includes 84 acres. SONGS is comprised of three nuclear generating units with supporting facilities. SONGS 1 occupies the northern end of the site. SONGS 1 was designed and built by Bechtel and consists of a Westinghouse - pressurized water reactor, a three-loo) Reactor Coolant System, and a Westinghouse turbine-generator set. T1e SONGS 1 Nuclear Steam Supply System (NSSS) is rated at a core thermal power output of 1347 MWt. The turbine generator is rated at a gross output of 450 MWe, The SONGS 1 Reactor Coolant System is comprised of the reactor vessel and three heat transfer loops, each containing a steam generator and a reactor coolant pump. In addition, the system includes a pressurizer, a pressurizer relief tank, and interconnected piping. SONGS 2 and 3 are located south of and immediately adjacent to SONGS 1. SONGS 2 and 3 are essentially identical to each other and were designed and constructed by Bechtel. SONGS 2 and 3 consist of . Combustion Engineering NSSS and turbine-generators by GEC of Great Britain. The NSSS is comprised of a pressurized water reactor with two independent primary coolant loops. Each loop has twc reactor coolant pumps, a steam generator, and connecting piping. An electrically heated pressurizer is connected to one of the loops. The NSSS units are rated at a core thermal power output of 3390 MWt and the turbine-generator output is 1110 MWe. 2.1.2 Operating History SCE received a construction permit (CPPR-13) for SONGS 1 on March 27, 1964. On March 27, 1967, the NRC issued a Provisional Operating License (DPR-13) authorizing fuel loading and cold criticality testing. Initial criticality was achieved on June 14, 1967 and commercial operation commenced on January 1, 1968. The Provisional Operating License was converted to a facility Operating 1.icense on September 26, 1991. As discussed in section 2.1.3, a decisi las made to cease operation of SONGS i at the end of Fuel Cycle A detailed discussion regarding SOFGS 1 operating history was prev .usly provided to the NRC (Reference 2-1). A general discussion is provided in the following_ paragraphs. Page 4 of 26
i l l During its first twelve years of operation (1968-1979), SONGS 1 ; accumulated a lifetime capacity factor of 73 percent, even though significant down time for modifications occurred during this period. These modifications included enclosure of the steel reactor containment building in a surrounding reinforced concrete shield, and the addition, with electrical interconnection, of two large stand-by diesel generators for emergency use if all offsite power is lost. 2 During the succeeding twelve years of operation (1980-1991), SONGS 1 capacity factor has been about half of what it was during the first twelve years. This change resulted from lengthy planned outages.to perform modifications, and does not reflect any significant change in reliability when the unit is in operation. In the absence of the modifications, capacity factor would also have been reduced on two occasions during the period by equipment related problems un-related . to NRC-required modifications. During 1980-1981, many steam generator tubes were sleeved. During Fuel Cycle 10 and 11 refueling outages, thermal shield supports within the reactor vessel required inspection and redesign. Even with these two equipment relited problems, the capacity factor would have remained at about 70 percent if extended outages had not been imposed to perform NRC-required modifications. During 1982-1986, modifications were made throughout the plant and to the protective seawall to strengthen structures and equipment to m^ + new earthquake criteria. Other plant modifications were the result of lessons learned from the THI incident.- In addition to THI requirements, major changes in generic NRC requirements have also occurred in areas such as Fire Protection and Environmental Qualification of safety-related equipment. In summary, between 1979 and 1990, Systematic Evaluation Program, Three Mile Island Action Items, seismic, and other modifications were performed. SCE was ordered by the NRC to implement the remaining regulatory modifications during Cycle 11 and Cycle 12 refueling outages. 2.1.3 SONGS 1 Premature Shutdown 4 On May 1, 1989, the NRC met with SCE to discuss the NRC requirements for conversion of Provisional Operating License No. DPR - 13 to a 4 Facility Operating License. The NRC conveyed that certain actions must be implemented during the next two refueling outages. These actions consist of Three Mile Island Action Plan items, NRC Generic Letter items, and action items resulting from the integrated plant-safety assessment for SONGS 1 (NUREG - 0829). Collectively, these actioat are referred to as the Full-Term Operating ' cense (FTOL) open items because firm commitments to their implementation was considered a prerequisite to conversion of Provisional Operating License No. DPR - 13 to an FTOL. SCEsubmitted(Reference 2-2)andNRCaccepted(Reference 2-3)an integrated schedule for implementing the FTOL open items during
- Page 5 of 26
Cycle 11 and Cycle 12 refueling outages. SCE made significant commitments that involved substantial modifications to the facility. The SONGS 1 Operating License DPR - 13 was ordered to be modified to manda.te that SCE would implement their commitments to_ resolve the FTOL open items in accordance with the integrated schedule, in accordance with the SONGS 1 Operating License, SCE was required to ' ' complete a number of plant modifications prior to operation of Fuel Cycle 12. These modifications were estimated to cost approximately
$125 million.
Pursuant to the NRC-Order, the work on the modifications commenced. In parallel, SCE sought approval from the CPUC to include the required expenditures into the rate base. Extensive evaluations showing the. cost-effectiveness of the expenditures were completed and j submitted to the CPUC and the appropriate hearings were held. The : CPUC's Division af Ratepayer Advocates (DRA) strongly opposed a) proval of the expenditures, based in part on their contention': taat:
- 1) SONGS-1 would not be able to operate at a significantly higher capacity factor in the future than during recent' years;
- 2) the rate of required modifications would continue at a high level, notwithstanding issuance of the FTOL and completion of the work identified in the NRC Order; and
- 3) the steam generators would probably need to be replaced.
While SCE has vigorously sought to refute these contentions, DRA continued to assert that the FTOL expenditures would not be cost-effective. Ultimatelv, SCE, SDG&E and the DRA reached an agreement to permanently shutdown SONGS 1. The'CPUC a) proved the agreement and issued an Order directing SCE to im)lement tie terms of the agreement (Reference 2-4). In accordance wit 1 the agreement, SCE-terminated SONGS 1 operation on November 30, 1992 (at the end of Fuel Cycle 11). SONGS 1 will be staffed at normal levels consistent with work-requirements until all fuel is removed from the reactor vessel in 1993. SONGS 1 staffing and support requirements will be decreased over the following two years to the levels required for long term spent fuel storage. 2.2 Site-Specific Factors Affecting Decommissioning Planning-SONGS 1 was designed and constructed _ fifteen years prior to SONGS 2 and 3. SONGS 2 and 3 were designed and constructed concurrently, and the construction permits were issued on the same date. The operating license for SONGS 1 expires in March 2004, and the operating licenses-for SONGS 2 and 3 exnire in October 2013. It is currently expected that SONGS _1 will be placed into SAFSTOR until SONGS 2 and 3-~are permanently shutdown. When SONGS 2 and 3 are shutdown, the entire site will be decontaminated, decommissioned and dismantled. While-planning for decommissioning of SONGS 1, SCE has assumed continued Page E of 26
._ _. . __m..m___m______
4 i
- operation of SONGS 2 and 3 until at least the end of their currently
-licensed life. >
2.3 Selection of Decommissioning Alternative SCE has reviewed the three decommissioning alternatives (i.e., DECON, SAFSTOR, and ENTOMB) identified in the NRC's Final Decornissioning Rule (Reference 2-5), and has initially selected SAFSTOR for SONGS 1 =; because it can result in reduced occupational radiation exposures since residual radioactivity will decay over the SAFSTOR period.
- SAFSTOR also allows time for the industry to develop _ facilities for the storage and disposal of spent fuel and allows coordinated i
dismantlement and restoration of the entire site when SONGS 2 and 3 " are decommissioned. l The DECON alternative is not a viable option at this time. The DECON alternative consists of the immediate removal of radioactivity from i SONGS 1. Both high-level and low-level waste.would be shipped to licensed disposal facilities for disposition. -The systems, - _ structures and components would be decontaminated and/or dismantled in order to achieve a residual radioactivity level that complies with 4 the current NRC rec uirements (Reference 2-6). Currently, options do not exist for the cisposal of spent feel and, therefore, the fuel 4 must be stored on-site until-the Department of Energy (00E) develops ceceptable spent fuel disposal facilities. Consequently, DECON is not a reasonable alternative for SONGS 1. The ENTOMB alternative is not an acceptable option.- The_ ENTOMB-alternative: involves encasing contaminated structures, systems and components in a long-lived material, such as concrete, until the radioactivity decays to a level permitting unrestricted use of the site. The time required for SONGS 1 radioactive isotopes to decay to ' a level permitting unrestricted release significantly exceeds the 60-year period considered acceptable by 10 CFR 50.62 to decommission nuclear facilities. Therefore, ENTOMB is not.a viable
- decommissioning alternative for SONGS 1.
2,4 Decommissioning Activities i 2.4.1 Categorization of Systems Required For SAFSTOR SCE has evaluated regulatory requirements under the full-power license for SONGS 1 against the anticipated' configuration of the
)lant after permanent shutdown. - As a result of that evaluation, SCE 1as categorized SONGS 1 systems into two-categories:
Required for Operation (RO) - Systems maintained to support the-Spent Fuel Pool Not Required for Operations (NRO) - Systems not necessary to support the Spent-Fuel Pool. These-systems will be left-in a de-energized state. Page 7 of 26 1
SCE will place SONGS 1 into SAFSTOR until actual decommissioning activities Legin, in general, systems and equipment not required for SAFSTOR will be drained and de-energized. Activities will include: transshipping fuel from the SONGS 1 s)ent fuel-pool into the SONGS 3 spent-fuel pool to allow offloading ae entire core into the SONGS 1 spent fuel pool; draining unnecessary systems; de-energizing unnecessary equipment instruments and controls; and isolating NR0 systems from R0 systems. 2.4.2 Planning Phases for Shutdown and Decommissioning This section describe; the four planning phases for permanent shutdown and decommissioning of SONGS 1: Phase 1 - Preparation for Shutdown; Phase 2 - Plant Shutdown; Phase 3 - SAFSTOR; and' Phase 4 - Decommissioning. 2.4.2.1 Phase 1 - Preparation for Shut vn During the first phase, activ' ,es include: preparation and submittal of license amendments and regulatory exemption requests; development of detailed plans for disposit4n of structures, systems and components; review and evaluation of SONGS 1 programs and procedures; and programmatic reductions as allowed by administrative controls. 2.4.2.2 Phase 2 - Final Plant Shutdown The second phase includes termination of SONGS 1 operation. Prior to final core offload, 49 fuel assemblies will- be trans-shipped to the SONGS 3 spent fuel pool in order to allow the entire core to be offloaded into the SONGS l' spent fuel pool. Systems and components not required for spent fuel storage will be drained, isolated and de-energized. 2.4.2.3 Phase 3 -- Implementation of SAFSTOR - During the third phase, structures, systems and components- that are - necessary for safe and secure storage of- the spent fuel will be operated in accordance with applicable Technical Specifications. Activities'during this stage include maintaining:
- the systems and components necessary to support the operation of the Spent Fuel- Pool;.
- the required lighting and ventilation systems; e the structural integrity of structures, systems, and components necessary to support the safe operation of; the Spent Fuel Pool;
- environmental and. radiation monitoring programs; and Page 8 of 26
- . . - - - . - . . - - - - - . . . . - . ~ - . , - -. - . - . - - . . - - - -
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- other necessary administrative controls (e.g., Security Plan,
. Emergency Plan, Fire Protection Plan, Quality Assurance Program,etc.). 2.4.2.4 Phase 4 - Decomissioning The fourth phase will begin.when_ SONGS 2:and 3 are decommissioned.
- At the end of SAFSTOP, systems, structures, and components will
, either be decontaminuted to meet required contamination levels, or dismantled and ship)ed to an approved radwaste disposal site. It is currently planned t1at ultimately, the entire site will be restored to a beach condition. 2.5 Decommissioning Schedule-The major milestones for SONGS 1 include: Milestone Tentative Schedule POL Application . April 2,1992 (Completed) Exemptions / Relief Requests August 1992 - March 1993 (PartiallyCompleted) Tech Spec / Admin Control September 21,.1992 (Completed) Letter Preliminary Decommissioning Plan November 1992 Obtain POL October 23, 1992 (Completed) Plant Shutdown November 30 1992 (Completed) Submit Permanently Defueled December 1992 Technical Specifications (PDTS) Offload Core March 1993-Site Characterization Program June 1993 - June 1994 Submit Proposed November 1994 Decommissioning Plan Decommissioning Order. To be determined (TBD) Decontamination TBD Final Radiation Survey , TBD License Termination TBD Return Site-to Beach TBD Page 9 of 26
,- . - . ~ . . - - . _ - - - - - . ~ . - . - . . . . . . . - - . - - . . . - . - . . - - -
L j 2.6 Decommissioning Organization.and Responsibilities , The current organization chart for the SCE Nuclear Organization is. reflected in Figure 2-P.: The Senior Vice President has C ultimate i responsibility for_the decommissioning activities. Speu iic j responsibilities are held by_ the appropriate managers.- , 2.7 Training Program i SCE will modify existing SONGS 1 training programs so that they include only the specific training commensurate with the varying . requirements of the different phases of decommissioning. Assuming
- that decommissioning activities will commence while fuel remains stored in the SONGS 1 Spent feel Pool, SCE will retain the
, appropriate elements-of the SONGS-1 training program necessary to ! ensure-safe fuel storage and har.dling, including protection of workers from hazards associated with such activities. Training to support NRC regulations, _various station programs, plans, procedures,
- and general administrative and safety requirements will also be maintained as required.
1 2.8 Contractor Assistance SCE contemplates the use of qualified consultants and contractors to j assist SCE in decommissioning SONGS 1. The ultimate responsibility for the overall decommissioning of SONGS-I will be retained by SCE. REFERENCES 2-1. Letter, F.R. Nandy, SCE to NRC, " Plant History input for FTOL, SONGS'1," dated June 7, 1991. l 2-2. Letter, H.B. Ray, SCE to NRC, " Integrated Schedule for FTOL Open Items, dated October 2,1992. l-i 2-3. Letter, G.W. Knighton, NRR to H.B. Ray, SCE, " Order Confirming Licensee Commitments on Full-Term Operating License Open Items - San Onof re Nuclear Generating' Station, Unit 1 (TAC No.11232), dated i January 2, 1990. . 2-4. CPUC Decision 92-08-036, " Opinion on SONGS 1 Settlement' Agreement," dated August 11.-1992. 2-5. General Requirements for Decommissioning Nuclear Facilities, (Final Decommissioning Rule), Fed. Reg. 24,018,; June 27, 1988, 2-6. U.S._ Nuclear. Regulatory Guide 1.86, " Termination of Operation -
. Licenses for Nuclear Reactors," June 1974. -
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- . . - - . - - . . . - , ,,,.nn.,., -, , ,,,-.n. ~ , , , , , , ,w,. ,w. , e.n e- , +m.. . .m--- ,-,sw,,,-.v,ar ap ,
3.0 PROTECTION OF OCCUPATIONAL AND PUBLIC. HEALTH AND SAFETY SCE's management is committed to ensuring that waste, radioactive and/or hazardous, is collected, )rocessed, stored, and disposed of in. such a manner as to protect the lealth and safety of the worker and the public. General plans are to utilize existing programs and procedures for ALARA, health physics, radwaste, efflant, and . environmental protection during the decommissioning process. As necessary, these programs will be revised to accommodate removal of systems and components not required for maintenance of the facility after the core is offloaded and the fuel is stored in the spent fuel pool. 3.1 Radiological Status 3.1.1 Operating History As would be expected for a nuclear power plant that has operated for 25 years, some low-level contamination exists in several plant locations. Additional' details regarding SONGS 1 radiological history will be previded to the NRC at a later date. 3.1.2 Current Radiological Status The extent, magnitude and radionuclide content of activated and contaminated material / equipment at SONGS 1 will be determined during the Site Characterization program.. The program will' quanti fy the radionuclide inventory for the_ following four categories:
- Structures
- Systems
- RPV and internals
- Soils i The principal structures containing significant levels of
' contamination are the Reactor Building, Fuel Storage Building, and Turbine Building. Although some contamination has penetrated concrete surfaces, must contamination is.on the-surface of walls, floors, ceilings and structures. Neutron activation has resulted in-activation products in plant components such as the reactor vessel, the primary shield, and other components located inside the Reactor Building. Numerous systems and-components at SONGS 1 potentially contain radioactivity in the form of contaminated fluids, sludges, and/or corrosion films on surfaces. General area radiation exposure rates = associated with accessible systems and components measure up to 100 mR/hr. Some high (greater than 100 mR/hr) radiation areas do exist in the radiologically controlled area, i l Page 13 of 26 l L
3.2 Radiation Protection 3.2.1 ALAR; Program SONGS 1 maintains an ALARA Program with well-defined goals and objectives. The Health Physics Manager repor ts to the Station Manager, cod is responsible for staffing and implementing the ALARA program in accordance with Regulatory Guide 8.8. SONGS 1 management shares the final responsibility to see that the ALARA concept is understood and implemented. The current ALARA program will ensure that parties involved in the planning and execution of the SONGS 1 decommissioning project maintain compliance with 10 CFR Part 20, and fulfill the regulatory and corporate objective of keeping occupational and public radiation exposure as low as reasonably achievable (ALARA). It is anticipated that the ALARA program for SONGS 1 decommissioning will consist of elements extracted from existing SONGS ALARA programs. The existing programs will be customized, where necessary, to address the specific concerns of the SONGS 1 decommissioning project. As a minimum, the ALARA program will include the following general elements:
- ALARA review of decommissioning task procedures and equipment or modifications prior to use/ implementation
- Establishing ALARA goals
- General training of workers in ALARA techniques and overall ALARA awareness a Qualification and/or mockup training of workers in the set-up and use of specialized equipment prior to actual field application in dose-intensive situations
- Periodic post-task ALARA review of decommissioning activities to identify potential areas for im)rovement in comparable subsequent tasks, and to confirm t1at exposures i1 curred are within anticipated estimates and goals These fundamental ALARA concepts will be integrated with lessons learned from other decommissioned plants and included in decommissioning planning for SONGS 1.
3.2.2 Health Physics Program SONGS 1 Health Physics Program ensures that personnel radiation and offsite direct doses are kept ALARA and within regulatory guidelines. The Health Physics Manager (who has qualifications equivalent to the radiation protection manager referred to in NRC Regulatory Guides 1.8 (Reference 3-1), 8.8 (Reference 3-2), and 8.10 (Reference 3-3)) is responsible for administering the radiation protection programs. These programs encompass the handling and monitoring of radioactive materials, including special nuclear, source, and byproduct Page 14 of 26
materials. The Health Physics Program will ensure the use of suitable protective clothing, equipment, and monitoring devices by decommissioning workers and health physics personnel. Since SONGS 2 and 3 will remain operational, the Health Physics organization for the overall site will not substantially change in the near term. Most of the resources that pr3viously supported SONGS 1 will be transferred to SONGS 2 and 3. Nominal resources will be available to SONGS 1 for the necessary health physics activities to support the operation of the SONGS 1 spent fuel pool. 3.2.3 Radioactive Effluent Program The Manager, C' 'mistry, reports to the Station Manager and is responsible fo, administration and implementation of the Effluent Program. The Effluent Program ensures that:
- releases of radicactive liquids and airborne material are controlled within the limits of 10 CFR 20 and 10 CFR 50; and
- doses to the public as a result of the discharge of radioactive materials from the facility arc kept as low as reasonably achievable (ALARA).
With the shutdown of SONGS 1, proaressively more of the systems used to proces's and discharge radioactive liquids and airborne materials will no longer be required. Since SONGS 2 and 3 will remain operational, the Chemistry organization for the overall site will rot substantially %nge in the immediate future. Most of the resources that previousiy supported SONGS 1 also suoport SONGS 2 and 3. 3.3 Radioactive Waste Management The following is a brief discussion of the current and expected sources of radwaste under consideration fcr processing and disposal. During SONGS 1 decommissioning, a significant amount of plant resources will be expended in disposing of the spent fuel, _s well as the processing of liquid and solid radioactive wastes. Radioactive wastes include neutron activated materials, contaminated materials, and site generated radioactive waste. The following sections address fuel disposal and radioactive waste management. A detailed inventory and description of the types, quantities, and concentrations of current and anticipated wastes; as well as the selected processing and disposal methods will be developed. 3.3.1 Fuel Disposal Although the plans for permanent disposal of high level waste are , currently uncertain, the Department of Energy (DOE) projects that its I Monitored Retrievable Storage (MRS) facility will be available to l begin acceptance of utility spent fuel in 1998. This facility will ' l Page 15 of 26 i l l
hold only limited quantities of spent fuel until DOE o) ens the high-level waste repository at Yucca Mountain, Nevada, whic1 is currently scheduled for 2010. Facilities must be provided to store SONGS 1 spent fuel assemblies on-site until acceptance by DOE. Following final shutdown, SONGS 1 will have 207 spent fuel assemblies stored in the SONGS 1 spent fuel pool with additional SONGS 1 spent fuel stored in SONGS 2 and 3 spent fuel pools (70 assemblies in SONGS 2 and 118 assemblies in SONGS 3). SONGS has established a spent fuel storage project to implement spent fuel management strategies which may include the construction of an Independent Spent Fuel Storage Installation (ISFSI). The spent fuel project will evaluate alternatives to accommodate not only the SONGS 2 and 3 spent fuel exceeding existing onsite storage capacity, but also to provide the c oability to empty the SONGS 1, 2 and 3 spent fuel pools at the end of plant life to facilitate site decommissioning if economically or operationally prudent. 3.3.2 Radwaste Processing It is expected that existing methods will be used to process radwaste generated during SAFSTOR and decommissioning. 3.3.2.1 Gaseous Waste As described in the UFSAR, Section 11.3, SCE currently has a gaseous radwaste processing system. After shutdown, the Radwaste Gas Treatment System will be purged with nitrogen, sampled, and removed from service. 3.3.2.2 Liquid Waste As described in the UFSAR, Section 11.2, SCE currently has a liquid radwaste processing system, which would continue to be used to process the wastes generated during SAFSTOR and decommissioning. The existing system, its processes, and associated procedures will be evaluated during the detailed decommissioning planning in order to determine the modifications that should be made to the existing system. 3.3.2.3 Solid Waste As described in the UFSAR, Section 11.5, SCE currently has a solid radwaste processing system, which would continue to be used to process the wastes generated during SAFSTOP. and decommissioning. Solid wastes will result from the processing of liquid waste streams, processing the activated and contaminated component inventory, and working in radiologically contaminated environments. The existing system, its processes, and associated procedures will be evaluated during the detailed decommissioning planning in order to determine the modifications that should be made to the existing system. Page 16 of 26
3.3.3 Radwaste Disposal The radwaste generated at SONGS 1 is the type and quantity typical of a Westinghouse pressurized water reactor. Solid radioactive wastes generated by plant operation are processed, packaged, or staged until it is shipped offsite for permanent disposal at a licensed burial facility. Solid radioactive wastes include:
- Spent ion exchange resins;
- Spent filter cartridges;
- Miscellaneous dry active waste (e.g., contaminated paper, rags, clothing, HVAC filter media, HEP / filter elements, tools, etc.);and
- Other items / components which have been irradiated, including but not limited to, the control rods, in-core instruments, reactor vessel internals, etc.
Solid radioactive wastes (dry active wastes) are classified into two categories: compactible and non-compactible. Based upon SCE's current processing scheme, compactible solid wastes, such as contaminated protective clothing, plastic, rags, etc., are packaged into 55-gallon drums using a radwaste drum compactor for disposal or sea / land containers for incineration. Non-compactible solid wastes, such as piping, valves, surplus equipment, etc., are packaged in strong, tight boxes for disposal or decontamination and salvage. The entire solid radwaste process, including procedures and systems for disposal of solid radwaste, will be reviewed and evaluated during the detailed planning for SAFSTOR and decommissioning. The large volumes of radwaste expected to be generated during decommissioning, and the availability of a low-level radwaste burial site will be evaluated and appropriately integrated into the planning effort. The packaging, shipment, and disposal of the major reactor components, such as control rods and in-core instrumentation, will also be evaluated regarding their potential high radiation levels. 3.3.4 Radioactivity Analyses In support of radwaste shipment and disposal, radiation surveys will be performed and waste characterization analyses will be performed using standard industry methods. Activation analyses will be performed to characterize the levels of radioactivity of the irradiated reactor components. The radionuclides of importance will be quantified by the analysis using typical material composition data, measured radiation levels, and neutron fluence ar.d energy spectrum data. Burn-up analyses will be performed on the neutron instrument chambers to determine their transuranic content. Contamination analyses will be performed in order to quantify the , levels of fixed surface contamination and any remaining loose surface i contamination present after decontamination is performed. l Page 17 of 26
3.3.5 Other Radio otive Waste 3.3.5.1 Mixed Waste Mixed wastes are materials which are radioactive and considered hazardous under aither the EPA's Resource Conservation and Recovery Act (RCRA) and/or the State of California's Hazardous Waste Control Law (HWCL). As such, management and disposal of these wastes is regulated by both the NRC and the State (on behalf of the EPA). Currently, SONGS has an interim status Treatment, Storage, and Disposal (Part A) permit for storage of mixed wastes. Prior to decommissioning of the facility, a closure plan will be prepared addressing local, state, and federal requirements. All processing, storage, or disposal will be in accordance with the appropriate regulations. Administrative controls will continue to be implemented to minimize the generation of mixed waste. The existing program will be reviewed and adapted, as necessary, during decommissioning. 3.3.5.2 Radioactive Sources There are approximately seventy-five (75) licensed and e':empt radioactive sources containing about fifteen (15) Curies of radioactivity at SONGS 1. These sources will be shipped off-site for disposal or transferred to SONGS 2 and 3 when they are no longer needed to support decommissioning. 3.3.6 Status of Low-level Disposal Facility A low-level radioactive waste disposal facility (Ward Valley) was scheduled to begin operating in California in 1993. Due to delays in the licensing process, the actual operation of Ward Valley is indeterminate. SCE cun'e.itly anticipates that SONGS will continue to send some low-level radwaste to the Barnwell facility until mid-1994, when Barnwell is scheduled to terminate receipt of radwaste from states not in their regional radwaste compact. After mid-1994 SCE will st:re its low-level radwaste on-site in a specially designed facility termed the Multi-Purpose Handling Facility until Ward Valley, or another low-level radwaste disposal facility becou.es operational, 3.4 Accident Analyses Only two of the accidents that are evaluated in Chapter 15 of the SONGS 1 Updated Final Safety Analysis Report (UFSAR) remain credible for the permanently defueled plant: (1) a loss of offsite power (LGP); and (2) a fuel handling accident. The. adverse safety implications of both of these accidents will be reduced once the plant is defueled. Consequently, once the core is permanently defueled, there are no significant design basis radiological consequences to the general public. 1 Page 18 of 26 l
1 3.5 Environmental Protection Program Management of hazardous wastes is under the jurisdiction of the ; Manager, Site Sup) ort Services. Additionally, responsibility for mixed wastes is slared jointly with the Manager, Site Support-Services and the Health Physics Manager. The Environmental Protection Program also ensures that:
- all processing, storage, and disposal-of (non-radioactive) l hazardous wastes are in accordance with applicable state.and federal EPA regulations; and
- underg,round storage tanks are monitored and maintained, as
- required, by county, state, and federal regulations.
Specific details for the closure of each system will be developed as i .part of the closure plan for the faci.lity. 3.6 Fire and Occupational Industrial Safety In addition to radiation safety, fire and industrial scfety will be considered in the planning and implementation of SONGS 1
- decommissioning. This program will be based on a review of current fire and industrial safety considerations. - A program to minimize the likelihood and severity of potential fires and accidents, and to
- ensura the use of proper industrial safety practices will be j
developed. 1 REFERENCES 3-1. Regulatory Guide 1.8, " Qualification and Training of Personnel for i Nuclear Power Plants," (Draft RS 807 5, F,oposed Revision 2, published 2/79; Draft RS 807-5,.Second Proposed Revision 2, published 9/80; Draft OL 403-5, Third Proposed Revision 2, published 1/85), Rev. 2; April 1987. 3-2. Regulatory Guide, 8.8, "!aformation Relevant to Ensuring That Occupational Radiation Emsures at Nuclear Power Stations Will Be As Low As Reasonable Achievable," Rev. 3, June 1978. 3-3. Regulatory Guide 8.10. " Operating Philosophy for Maintaining Occupational Radiation Exposures-As Low As Is Reasonable Achievable," Rev 1-R, May-1977. l l , l
- Page 19 of 26 I
- - - , . - - . - . . . . . - - - - . . - - - - . - - .-.. - .-.. _ .~ - - - -...
4.0 FINAL RADIATION SURVEY The purpose of the' final radiation survey is to demonstrate and document that contaminated materials, structures, systems, components, and areas have been successfully_ removed cr decontaminated to levels delineated in NRC regulations such'that the site and facility is suitable for unrestricted use. The final radiation survey will be performed in a manner to meet the intent of existing regulatory guidance- (References 4-1,4-2,4-3,and4-4). REFERENCES 4 4-1. NUREG/CR-2082, "Honitoring for Compliance with Decomn- sioning l Termination Survey Criteria," June 1981, 4 4-2. U.S. Nuclear Regulatory Guide 1.86, " Termination of Operation i Licenses for Nuclear Reactors," June 1974. ! 4-3. NUREG/CR-2241, " Technology and Costs of Termination Surveys j Associated with Decommissioning of Nuclear facilities," January 1982. l 4-4. NUREG/CR-0586, " Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," August 1988. i 4 l i-4 1 I-Page 20 of 26
- . . .- __ . _ _ _ . __ . . _ _ . _ . a-
5.0 DECOPHISSIONING COST ESTIMATE 5.1 Certificate of Financial Assurance SCE has certified that financial assurance for decommissioning SONGS 1 will be provided in the amount stated in 10 CFR 50.75(c)(1)(i). This amount will be adjusted annually using the rate stated in 10 CFR 50.75(c)(2). The minimum amount required for decommissioning SONGS 1 was calculated to be $86.9 million (1986 dollars). The certification letter and the associated calculation are provided in Appendix A. 5.2 Decommissioning Cost Study In 1990, SCE contracted with TLG Engineering, Inc. (TLG) to conduct a site-specific cost study (referred to as "1990 cosi study"). The 1990 cost study was used to support SCE's 1992 General Rate Case filing with the California Public Utilities Commission (CPur). The 1990 cost study is provided in Appendix B. According to this study, the estimated decommissioning cost for SONGS 1 is $136.2 million (1990 dollars); the estimated cost to restore the site to its original condition is $102.2 million (1990 dollars); and, therefore, the total cost to decommission and return the site to its original condition is $238.4 million (1990 dollars). SCE currently expects to return the site back to its original condition consistent with a grant of easement with the United States Government, which states, in part: That upon the termination of the easement granted herein, the Grantee at their expense may remove, and if desired by the Government, shall remove, any and all improvements installed or constructed hereunder and shall restore the ! Premises to a condition satisfactory to the Director, Southwest Division, Bureau of Yards and Docks; except i that the Grantee shall not oe obligated to restore any l natural material cut or filled in the necessary
- excavation and grading of the Premises. Upon termination
! of the easement, the Grantees shall also, if required by the Government, decor.taminate the Premises and such surrounding area within the Reservation as may have been contaminated by the operation of the Nuclear Station. Accordingly, SCE's collection rate is based on the estimated costs to i return the site to its original condition, and the overall decommissioning funding goal is currently $238.4 million. As of August 31, 1992, SCE and SDG&E have collected approximately $200 million and are continuing to collect decommissioning funds. The collected decommissioning funds are not divided into decommissioning l costs and site restoration costs. The 1990 cost study is the best estimate until ancther cost study is conducted in 1993 to support SCE's 1995 General Rate Case. SCE will Page 21 of 26 l
reassess its decomissioning collection rate structure in the 1995 General Rate Case. SCE will include the results of the 1993 cost study in the Proposed Decomissioning Plan. 1 l l 4 Page 22 of 26
6.0 TECHNICAL AMD ENVIRONMENTAL SPECIFICATIONS IN PLACE DURING DECOMISSIONING 6.1 Technical Specifications SCE is in the process of formulating Permanently Defueled Technical Specifications (PDTS) that will ensure the safe, long-term storage of spent fuel in the spent fuel pool until the plant is decommissioned. The PGTS are scheduled to be submitted to the NRC in December 1992. treas to be ar'ai essed will include fuel storage and handling, aixiliary elec:cical supply, administrative controls, and NRC reporting requirements. Until the POTS are approved by the NRC, the defueled plant will be maintained in accordance with the r_aration and surveillance requirements as defined in Referenc. 6-1. This letter to the NRC describes how the existing Technical Specifications will be applied aftu defueling. The letter was considered appropriate since most of the existing SONGS 1 Technical Specifications do not apply to the permanently defueled condition, and additional administrative The letter controls has been were prucent reviewed to ensure and approved by plant andReference the NRC p(ublic safety. 6-2) with a recommendation to include additional systems and/or Limiting Conditions for Operation in the PDTS. 6.2 Environmental Specifications SCE will continue to comply with the Technical Specifications, Offsite Dose Calculation Manual (0DCM) Specifications, and other app'icable regulations to control releases of radioactive and/or hazardous materials from SONGS 1. ' In 1992, the Radiological Ef fluent Technical Specifications were I transferred to the SONGS 1 ODCM per NRC Generic Letter 89-01. Both the Effluent and Environmental Monitoring Programs will be performed in accordance with the ODCM and maintained dtring SAFSTOR to ensure that any radiation doses to the public are ALARA. All federal, state, and regional permits for managing and discharging " non-radioactive materials / wastes, and for operating equipment will be reviewed for accuracy prior to decommissioning. Licensee activities will continue to be performed to ensure comoliance with the regulations and protection of the health aN safety of the public. REFERENCES 6-1. Letter, H.B. Ray, SCE to U.S. Nuclear Regulatory Commission,
" Operation and Surveillance Requirements for Permanently Defueled Condition for San Onofre Nuclear Generating Station, Unit 1," dated September 21, 1992.
Page 23 of 26 i _ _o
6-2. Letter, J. 0 Bradfute, U. S. Nuclear Regulatory Comission, to H. B. Ray, SCE, " Operation and Surveillance Requirements for Permanently Defueled Condition for San Onofre Unit 1 (TAC NO. M84567)," dated October 30, 1992.
\
\
J Page 24 of 26 m______.._m
7.0 QUALITY ASSURANCE PROVISIONS IN PLACE DURING DECOMMISSIONING An appropriate Quality Assurance (QA) Program will be implemented throughout the decommissioning effort in order to assure that applicable regulations are met. SCE's NRC approved QA Program will be adapted and implemented, as appropriate, for decommissioning. In addition, activities will be conducted in a controlled manner designed to protect the health and safety of both project workers and the general public, as well as to protect the environment. . The QA program implemented by SCE during decommissioning will provide for compliance with appropriate regulatory and license requirements. Specific QA requirements and organizational responsibilities for . implementation of these requirements shall be specified in various implementing documents and procedures. The requirements stipulated in the decommissioning QA program are mandatory and shall be imposed, as appropriate, on personnel and organizations, including contractors, who perform SONGS 1 decommissioning activities. 1 i i l 4 e i l' 4 I Page 25 of 26
8.0 -PHYSICAL SECURITY PLAN PROVISIONS IN PLACE DURING DECOW4ISSIONING The provisions of the SONGS 1 Security and Safeguards Plans will be reviewed in' light of the plans for decommissiontog to detennine the
- measures that are needed for compliance with..MC security regulations. Revisions to the existing plans will be implemented as necessary in accordance with 10 CFR 73.55 and 10 CTF 50.51(p). Since SONGS 2 and 3 will. remain operational. it is expected that the r organizations described in the existing Security Plan will remain intact, with limited changes to reflect the permanent shutdown of SONGS 1.
i L. 3 l i e )- f' Page 26 of 26
I l l I i APPENDIX A Letter and Certificate Assuring Availability of Funds for Decommissioning 1
AD12 S0123 NRC July 24, 1990 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 .
Subject:
Docket Nos. 50-206, 50-361, and 50-362 10 CFR 50.33(k)(2); Report Assuring the Availability of Funds for Decommissioning San Onofre Nuclear Generating Station Units 1, 2, and 3 Gentlemen: As required by NRC regulation 10 CFR 6 50.33(k)(2), this letter submits information to reasonably assure that funds will be available to decommission San Onofre Units 1, 2, and 3. The information reouired by 10_CFR $ 50.75(b) is provided in Enclosures to this letter. This decommissioning information is submitted.by the Southern California Edison Company (SCE) on behalf of SCE and the San Diego Gas & Electric Company (SDG&E). In addition to SCE and SDG&E, the Cities of Anaheim and Riverside are owners and licensees of San Onofre Units 2 and 3. These two cities will submit their decommissioning financial assurance certification reports under separate cover letters. The Certificates of Financial Assurance for SCE and SDG&E (Enclosures lA through IF), Oaths of Affirmation (Enclosures 2A through 2F), trust agreements (Enclosures 3A through 30), and investment management agreements (Enclosures 4A through 40) constitute the required decommissioning financial assurance certification. The minimum funding amount required to demonstrate _ reasonable assurance of funds for decommissioning was determined in accordance with 10 CFR550.75(c). The method of providing financial assurance is an external sinking fund in accordance with 10 CFR $ 50.75(e). If you have any questions on matters concerning SCE, please contact me. On matters concerning SDG&E, please contact Mr. Thomas E. Philips at (619) 696-1894. Sincerely, l Harold B. Ray i
U.S. Nuclear Regulatory Commission Document Control Desk San Onofre Nuclear Generating Station July 24, 1990 Page 2 Enclosures cc: J. B. Martin (Regional Administrator, USNRC Region V) C. W. Caldwell (NRC Senio: Resident Inspector, San Onofre Units 1, 2, and 3) J. E. Tatum (NRC Project Manager, San Oaofre Unit 1) l l
SOUTHERN CALIFORNIA EDISON COMPANY CERTIFICATE OF FINANCIAL ASSURANCE FOR DECOWilSS10NING SAN ONOFRE UNIT 1 10 C.F.R. 9 50.75 (b) Scuthern California Edison Company (SCE) hereby certifies that financial assurance for decommissioning SCE's 80.00Y. interest in Unit 1 of the San Onofre Nuclear Generating Station will be provided in an amount which may be more but not less than 80.007, of the amount stated in 10 C.F.R. 9 50.75(c)(1)(i), adjusted annually using a rate at least equal to that stated in 10 C.F.R. 9 50.75(cl(2). Such amounts will be accumulated in accordance with 10 C.F.R. 9 50.75(4, through the mechanism of an external sinking fund in which deposits are made at least annually, unless any such annual deposits have been prepaid. SCE en'tered into a Deconmissioning Trust Agreements dated NovembeMS,1987 with i Harris Trust and Savings Bank, as Triistee, and the California Public Utilities Commission. (See Enclosure 1.B i.a and Enclosure 1.B.i.b). Pursuant to the Trust Agreement, SCE-has also entered into Investment Management Agreements, dated January 25, 1988 with RCH Capit&1 Management and January 26, 1988 with STW Fixed Income Mana ement. (See Enclosure 1.B.ii.a. Enclosure 1.B.ii.b. and - Enclosure 1.B.ii.c . - San Onofre Unit 1 is a Pressurized Water Reactor licensed to operate at a maximum reactor power of 1347 megawatts-thermal (MWt). Therefore, San Onofre Unit 1 is subject to the 10 C.F.R. 9 50.75(c)(1)(i) minimum funding requirements for a pressurized water reactor producing less than 3400 MWt. Accordingly, the minimum value required in January 1986 dollars is equal to (75 million + ((0.0088) x 1347) million) or $86.9 million. As required, this amount is adjusted annually at a rate which is at least equal to the rate detarmined 'vy the formula stated in 10 C.F.R. $ 50.75(c)(2)- when the latest information available is used. SCE further certifies that deposits will continue to be made into the trust fund in an amount or amounts which are necessary to maintain a calendar year funding level at or above 80.007. of the multiplicative product of (A) and (B);'where: (A) is the latest adjusted / escalated value for the required NRC minimum amount; and (85 is the fractional result obtained by dividing (C) by (D); where (C) is the n%ber of yars, and any portion thereof, between March 27, 1967 (issuance date of the License) and the end of the cahndar year for which the amount is being calculated, and (D) is the number of years, and any portien thereof, between March 27, 1967 and March 2, 2004 (expiration date of the License). Signed: & I4 L A( W
\J N- .
Name: Michael L. Noel
Title:
Vice President & Treasurer Address: 2244 Walnut Grove Avenue City:-Rosemead. California 91770-Telephone No.: 181ft) 302-1086 '
l APPENDIX B Deconsnissioning Cost Study for the San Onofre Nuclear Generating Station /
ll Document 503.:!M Page 1 of 91 4 i
- .I L, I DECOMMISSIONING COST S'!UDY for the i
SAN ONOFRE NUCLEAR < GENERATING STATION .. 4
'l
- O i
Frepared for the SOLTf82RN CALIFORNIA EDISON COMPANY July 1990 P n p d kyr I Fran:Is W. Seymo, n Approved byt s' &
' ' homas S. LaGuardia P
f i Document 503 25 002 l j i l , Page 2 of 91 f 4 , I a. i a 4
- TABLE OF CONTENTS 4
i 1.
SUMMARY
..............................................,.............................................................................P ........ 3 ' ! 2. INTR O D U CT10 N . . . . .. .. . . . . . .. . . . . .. ... ... .. . .. .. .... .. . .. .... . . . . .. . .. .. . . ... ..... .. . . . .... .. . ....... .. ... . ..... . 2.1 Obj e etIve o f S tu dy ................................ ............... ....................................... ........... i . t ! 2.2 S i t e D e scri p ti o n . . .. . ... . .. . . . . .. .. . .. . .... ..... . ... . . ... . .... ... . .. . ....... .........6 ! 23 R e gul a t o ry G uld anc e ................................................................. ............... . ............. ..... ......... 7 L 3. D ECO M MISSION ING ALTERNATIVES .......................................................................... 13 3.1 D ECON ( Prompt Re moval Dismantling) .................. .................................................. 13 ! 3.1.1 Period 1: Prepara ons l 3.1.2 Period 2: Decommissioning Operations and License Termination
- 3.13 Period 3: Site Restoration ,
! Dismantilng)......................................................... 18 2 3.2 SAFSTOR 1' 1 Per (iod 1: SAFSTOR OperationsM othball with Delayed j 3.2.2 Period 2: SAFSTOR Dormancy - i 3.23 Periods 3 5: SAFSTOR Dela i 4. COST ESTIMATE........................................yed Removal / Dismantling
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .22 4.1 B asis o f Es tima te ........................................ ....................................................................... .. 22 i 4.2 M e th odo l ogy... ............................... ................. ................
4.3 Si te.Spe cific Co nside ta tions ........................................... . ................................................
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25
. 43.1 Major Component Removal j 43.2 Transportation Methods 4 4.33 Site Conditions at Facilit Closcou t j 4.4 Assumpt ions ....................................y ................................................... i 4.5 Cos t Es ti ma te S ummary ................................................................................... ....... . ..
- 5. S CHE D ULE ESTI MATE ...................................................................... 58 .....'
5.1 Sche d ule Estimate Assump tio ns ...... ..........................................o...................................
- 5.2 Proje et Sch e d ul e ............................... ................... ............. ........ . ... ........................... .........
l 6. 7. RADIO ACTIVE WASTE VO LUME ........................................................... ........................75 . OCCUPATIONAL EXPOSURE...... ......................... C O N CL U SI O N S ... . .. ...... ........ . . ...... ... .......... . ... . ...... .. ..... . . ... .... 8. 3
- 9. REF.w.NCES....................................................................................................
............................................................ 81 APPENDICES -
t , A Unit Cost Factor Development ' B Unit Cost Factor Listing l+ i i j-jm i e i L
- en-,--. ~ y y-,,4-,,,--,,wwm+,,33q-wr r v"'e""ce,, wr ,- = ,.y y.r,,.y,[
Document S03 25 002 Page 3 of 91 O
- 1.
SUMMARY
The San Onofre Nuclear Generating Station is located on the coast of southern California in San Diego San Diego. TheCounty'ite is located entirely within the boundaries of the United S Corps Base, Camp Pendleton, California, near the northwest end of the 18 mile shoreline. The station !s comprised of three nuclear generating units with supporting facilities. Southern Call-fornia Edison Company (SCE)is the primary owner and hoicis the license for the station's oper. allon. This study provides cost, schedule, waste generation / disposition and radiation exposure estimates associated with the decommissionmg of the three nuclear units at the San Onofre Nuclear Generating Station following the conclusion of their operation. The study involves two different decomruissioning methodsfDECON (prompt removal / dismantling) of Units 2 and 3 with delayed dismantling) of Unit 1. This optimizes the sequential remowil of all th(ree units.and SAFSTOR mothbal DECON,(prompt removal / dismantling) of a power reactor consists of removing from the site all fact assemblies and source material, radioactive fission and corrosion products, and all othr radioactive materials having activities above release limits. The facility operator may then lave p unrestricted use of the site with no requirement for a license. This scenario is equivalent to the DECON mode as described in the rule on decommissioning issued by the Nuclear Regulatorv Commission (NFC),
- General Requirements for Decommissioning Nuclear Facilities." Thi's study further NNmes that the remainder of the reactor facility is dismantled and all vestiges removed, in this returned to a state consstudy,istent with adjacent areas as per the present lease agreem SAFSTOR, (mothball) consists of placing and maintaining the facility in protective storage.
Spent fuel and source material are removed from the site during initial mothball operations. Concurrently, the plant staff conducts teneral plant decontamination activities, radiation sur-veys, and the processing and remcval of any radioactive waste materials remaining from opera. tions, in addition, a possession only license is secured and the securit , surveillance and maintenance plans for the delay period implemented. Delayed dismantli (decontamination activities are initiated such thet license termination is accomplished wit in the 60 ye period set by NRC. As with the DECON alternative, this study further assumes that the remainder of the reactor facility is dismantled and site restoration initiated. 4 While the disposal cost of spent fuel assemblies generated during plant operations is not con-sidered a decommissioning expense, the presence of those assemblies on site does have a bearing on the cost to decommission. This study recognizes that the spent fuel storage facilities at the San Onofre Nuclear Generating Station Units 2 and 3 will be active approximately five (5) years after operations cease at the second and third units. This study'has treated such facilities as if they will be operated as an Independent Spent Fuel Storage Installation until such time that all . pent fuel can be removed from the site. The five year period was based on information received from SCE as well as the DOE current time table to receive spent fuel assemblies at its yet to be developed Waste Managemem System (WMS). This Stationstudy un [er current requirements based en present day costs and available techn and schedule estimates presented herein are based on the complete removal of all components
Docum:nt 503 2$.00 Page 4 of 91 O and stnictures withic the property lines, as the station is presently configured, except as noted within the body of this report. The total cost associated with decommissioning the San Onofre Nuclear Oenerating Stauon is shown in Table 1.1. The numbers in Table 1.1 are summaries taken from the detailed cost tables in Section 4 and the scheduling analysis described in Section 5. An alternative to immediate decommissioning is one which provides for the delayed decommis-sioning of a power reactor under certain conditions, i.e., if decommissioning is completed within 60 years of the conclusion of operations. The NRC can approve a decommissioning plan which provides for completion of decommissioning beyond 60 years if there is some demonstrated bendit to public health and safety (Ref. O. The decommissioning alternatives evaluated in this stud shutdown. However,y assume it should be that the noted station that will be this study decommissioned is not within 60 years of its a detailed decommissioning engineerin6 Pl an, and therefore does not commit the participants to a specific course of action for the station following ultimate cessation of operations. There are definita adyt.atages to the DECON alternative. The alternative is less costly,in 1990 dollars, than the scenarios myolving extended delays in the station dismantling. The ultimate cost for any alternative will depend upon future economic factors such as inflati(on and fat ors such as future NRC reguistions and waste policy decisions and actions.) The NRC endorses DECON princisally because (1) it immediately eliminates a >otential long term safety hazard and (2) those incividuals familiar with the nuclear facility wil still be available to sup. g port the dismantling effort. DECON also relieves the utility of long term obligation and g liability for maintenance of the property. The cost of the SAFSTOR alternative is significantly increased by the cost incurred in maintaining the station in protective stora ' over the DECON alternauve. Primarily, ge. However, SAFSTOR does have so the residual radioactivity, resulting in lower than are incurred in the DECON alternative, personnel and a potential radiation savings exposures in the cost of disposal during for disman l the waste volume generated during decommissioning operations. Conversely, the utility continues to incur the cost of manning and maintaining,the site in the SAFSTOR alternative in addition, at the end of the SAFSTOR dormancy penod, the station must be partially reactivated (those systems necessar and/or replacement services must be arocured.y Refursishment to support decommissionI7 activities wi o)erations) l involve requalifying the cranes and other lifting c evices, reactivating electrical, lighting, air handl,ing, and other service systems. In addition, the procurement of waste processing / treatment services would be necessary,if plent systems could not be salvaged. One of the biggest drawbacks to the SAFSTOR alternauve is the unavailability at the time of decommissioning of station operations personnel, whose knowledge of the station is invaluable in supporting and assisting decommis. sioning operatans. Without personnel familiar with station operations, the decommissioning program may incur additional cost and worker exposure as it compensates for engineering and planning developed from an incomplete data base. O l
Document S03 25402 Page S of 91 O TABLE 1.1 SAN ONOFRE NUCLEAR GENERATING STATION COST AND SCHEDULE ESTIMATE
SUMMARY
Cost,90$ Schedule (thousands) (months) Unit 1 SAFSTOR (Mothball, Donnancy, Delayed Disman!!!ng) Mothball Operations 20,698 12.0 9 year maintenance cost 29,774 109.7 Delayed dismantling 160.941 1994 Total 211,413 181.3 Unit 2 DECON (Integrated Prompt Removal / Dismantling) i Total 275,765 88.8 Unit 3 DECON (Integrated Prompt Removal / Dismantling)- Total 368,909 117.6 Independent Spent Fuel Storage Installation Total 80,920 120.0 STATION TOTAL 937,007. 232.6 1 O 4
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- 2. INTRODUCTION 2.1 OBJECTIVE OF STUDY The objective of this study is to prepare an estimate of the cost, schedule, occupational i
enosure and waste volume generated to decommission the San Onofre Nuclear Gener-l ating Station includng all sup3orting facilities. Two decommissioning alternatives were considered. DECON'for UnLts 2 and 3, and SAFSTOR for Unit 1. The ENTOMD l alternative was not considered having no significant advantage over the SAFSTOR the ENTOMB alternative exhibits most of the disadvantages of the alternative, DECON alternat i.e., ive with little gained, as compared to SAFSTOR, in the long ter This study considers the integration of the three unitd dismantling, as discussed belo./. 4 The first nuclear unit at the San Onofre Nuclear Generating Stat en site was designed , and constructed 15 years prior to the second and third units. The second and third units
- with the construction permits being issued
' were on thedesigned same date.and constructed Operating licensesconcurrently,in expire March of 2004 nitfor L in October I and of 2013 for Units 2 and 3, after an ap year operating life for Units 2It and 3. proximate is expected that ? mal shutdown40 vet.rwould o)erating occur in life for Un . the same sequence, with the same offset in schedule. Since there are advantages to sequential decommissioning, e.g., a learning curve increases the overall pr ran-I (i efficiency, this offset was retained in the decommissioning schedule. Consequent , the decommlssioning sequence for the three units made use of this offset in integrati g the dismantling program for the station.
2.2 SITE DESCRIPTION ! The San Onofre Nuclear Generating Station (SONGS) is located on the coast of ! southern California in San Diego County, approximately 62 miles southeast of Los Argles and 51 miles northwest of San Dlego. The site Is located entirely within the ! boundaries of the United State: Marine Corps Base, Camp Pendleton, Calffornia, near
- the northwest end of the 18 mile shoreline. The property upon which the station is built
! is being leased from ine United States Government. SCE is the primary owner and ! holds the license for the station's operation. Figure 2.1 shows the layout of the site bluff ! area between Interstate Highway 5 and the beach.- SCE also leases property on the ! of Highway 5. This area is generally referred to as the " mesa , and is
..other included side (east)he within t scope of this study. Figure 2.2 shows the layout of the thre
- blocks with identification of the major structures.
' SONGS is comprised of three nuclear snerating units with supporting facilities. Unit 1 occupies the northern end of the site. Designed and built }.y Bechte., the unit is com-prised Of a Westinghouse pressurized water reactor and a Westinghouse turbine. generator set with a net electric capacity of 430 MWe, Units 2 and 3 are located south and immediately a facent to Unit 1. Essentially identical, these units were also designed and constructed b 3echtel. The Nuclear Steam Supply Systems (,NSSS) for Units 2 and , ineerin 3 thewere stationsupplied b Combustion with a net electric capac Engty of 11g MWe per unit.The two GEC tur i The reactor Nuclear and a threeSteam SupplyCoolant loop Reactor System (NSSS) System. The system was suppl l Westin house Electric Corporation. The NSSS unit is rated at a net core power out of 134jMWt. The corresponding turbine generator gross generator output ise.450 MNgut
Document $0345 002 Page 7 of 91 The Unit 1 Reactor Coolant System is comprised of the reactor vessel and three heat tramfer loops, each containing a steam generator, and a reactor coolant pump. In addi-tion, the system includes an electrically heated pressurizer, a pressurizer relief tank and interconnected piping. The system is housed withh a " containment sphere", a seismic Category I reinforcec concrete dry structure. Enclosing the sphere is a secondary con-tainment concrete shell. The NSSS for Units 2 and 3 consist of a pressurized water reactor with two independent primary coolant loops each of which contain two reactor coolant p mps and a steam generator. An electrically heated pressurizer and connecting p ng complete the system. The systems were supplied by Cornbustion Engineering. e NSSS units are rated at a net core power output of 3410 Mwt. -The corresponding turbine Eencrator gross generator output is 1127 MWe. Each system is housed within a containment structure. Each containment :tructure is a Seismic Category,1, steel line, prestressed concrete structure in the shape of a right, vertical cylinder with a hemispherical dome and a flat, reinforced concrete basemat. A welded steel liner plate, anchored to the inside face of the containment, serves as a leak-tight membrane. Fipre 23, a sectional view through the Containmc it Structure, shows the locations of the major NSSS components O Heat produced in the reactor is converted to electrical energy by the Turbine Generator V Systems. A turbine generator system converts the thermal energy of steam produced in the steam generators into mechanical shaft power and then into electrical energy. The Unit 1 turbine. generator is a three cycle tandem com)ound, quadruple exhaust con-1800 rpm unit. The high pressure turbine anc two low aressure turbines are densing,in coupled tandem to drive the generator. De turbine generators for U are each tandem compound, impulse reaction type with two-stage reheat, and consist of one high l tandem. pressure double flow and three low pressure double. flow elements driven in The turbines are operated in a closed feedwater cycle which condenses the steam; the heated feedwater is returned to the neam generators. Heat rejected in the main condensers is removed by the Circulating Water System (CWS). l Water System provides the heat sink required for removal of waste heat l The Circulatin!nnt's in the ower p thermal cycle. The system has the principa heat b absorbing this energy in the main condensers. The circulating water pumps take suctio from the mtake structures and pump the seawater through the main condensers. The CWS cooling water is returned from the main condensers to the ocean. Reinforced concrete conduits placed below the ocean floor provide for intake and discharge of the l seawater. 2.3 REGULATORY GUIDANCE The U.S. Nuclear Regulatory Commission (NRC) provides decommissioning guidance l in the new rule " General Requirements for Decommissioning Nuclear Facihties" (Ref. l ' 1) in addition to that previously set forth in Regulatory Guide 1.86 (Ref. 2). His r.ew rule defines three decommissioning alternatives acce (_') v (prompt removal / dismantling), SAbSTOR (mothball),ptable to the NRC, i.e., DECON and ENTOMB (entombment).
.1 1 Document 503 25 002 I Page 8 of 91 4 !O ! ) DECON (Prnmnt Remnval/Dkmantltnn) is de5ned by the NRC as 'the alternative in i . which the equipment, structures, and poriions of a facility and site containing radioactive ! contaminants are removed er decontaminated to a level that permits the property to be ! j released for unrestricted use shortly after cessation of operations.' SAFSTOR (Mothballi is defined as 'the alternative in which the nuclear facility is ' i placed and mamtained in a condition that allows the nuclear facility to be safely stored i and subsequently decontaminated (deferred decontamination) to levels that permit ] release for umestricted use." ENTOMB (Entombmanti is defined as "the alternative in which radioactive con. l taminants are encased in a structurally long lived material, suen as concrete; the
- entombed structure is appropriately maintained and continued surveillance is carried out until the radioactivity decays to a level permitting unrestricted release of the prop.
! erty.' However, this process is restricted in overall duration to 60 years and therefore limited in application unleu it can be shown that a longer duratloc is necessary to pro-tect health and safety. 4 Prior to the new rule, no endpoint was identified for either the SAFSTOR er ENTOMB process, i.e., a facility could remain in either state indefinitely. This is no longer the case l as the rule places upper limits on the completion of the decommissioning process. Con.
- sequently, with the new restrictions, the SAFSTOR and ENTOMB options are no !coger
- decommissioning alternatives in themselves, as neither terminates the license for the
- site. At the end of the dormancy periods, (up to 60 years), both alternatives would still
+ require site decontamination / decommissioning. 4 i In most situations the DECON alternative is the prefeived mode of decommissioning. l it immediately climinates a l This potentiallong decommissioningterm safety hazard alternative and 2 individuals is favored fam because (1)iliar with the n i will still be available to support the dis (ma)ntling effort. In addition, both the m l and entombment alternatives still require evemual decontamination / decommissioning l even after the maximum allowed dormancy durations. 'Ihis results in higher overalc costs as on going dormancy expense and reactivation costs offset the potential savings j gained from the delay. In this study, decommissioning has been approached on a station basis in order to i optinuze the decommisasioning process. With Units 2 and 3 still operational following : ' the final shutdown of the olc er Unit 1, there is no immediate need for the prompt removal of the single unit. Consequently, for the purposes of this study Umt I was ' assumed to be mothballed and maintained in a dormant condition awaiting the fin.d shutdown of Units 2 and 3. At this time the delayed removal of Unit I would commence with tha intention that Unit 2 would follow and then Unit 3. In this way the decommis.
- sioning of the entire site is optimized.
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Document S03 25 002 Page 9 of 91 0 1.ong term Mothballing or Entombment of the SONGS nuclear units was not considered for this study. Since the site property is ! cased from the U.S. government, the site should be cleared and returned to t3e onginal owner as nuickly as possible. This would relieve SCE of any long term obli tation and liability for maintenance of the property. In addi-tion, the Mothballing and Mntombment options are not decommissiorung alternatives in themselves, as they c o not terminate the L cense for the site. At the end of the donnancy periods,30 50 years for Mothballing, and up to 100 years for Entombment, both alterna-tives would still rec uire site decontamination and, under the terms of the lease, com-plete removal of alll facilities and improvements from the site. This would result in
, higher overall costs as yearly dormancy costs and reactivation costs offset any potential savings gained from the delay.
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Document S03 25 002 Page 13 of 91 0
- 3. DECOMMISSIONING ALTERNATIVE DESCRIITIONS Two specific decommissioning alternatives are reviewed for the San Onofre Nuclear Genera-for Units 2 and 3, and SAFSTOR ting Statica (Tiothball withs'udy:
delayedDECON (prompt dismantling) removal for Unit / dismantling)MB alternative was not
- 1. The ENTO reviewe this study because it does not provide any significant advantage over the SAFSTOR alternative; i.e., ENTOMB required larger up front capital expenditures, incurred greater levels of occupa-tional exposure to the workcr, without eliminating the necessity of eventual plant decontamina.
tion. The dormancy duration selected for use in the SAFSTOR alternative was based on the offset between the shutdown of Unit 1 and Unit 2 and 3. Although the DECON and SAFSTOR alternatives differ with respect to technique, process, cost, and schedule, both alternatives attain the same result: removal of all radioactive materials from the site and ultimate release of the site for unrestricted and/or alternative use. The following sections describe the basic activities necessary for each altemative. Although detailed procedures for each activity required are not provided, and actual sequences of work may vary, these activity descriptions may provide a basis for detailed engineering planning and scheduling at the time of decommissiorung, in the integration of the three units, consideration p was given to the effects of simultaneous decommissioning. Decommissioning activities are V offset between the units to take full advantage of the learning curve, specifically in the disposi-tion of the NSSS. The descriptions of activities herein are applicable to either unit; some of the activities described will be shared between the three units. 3.1 DECON (Prompt Removal / Dismantling) This alternative deals with the immediate removal of all radioactive materials from the site after the cessation of operations. This study does not address the cost of the i removal of spent fuel from the site because such costs are assumed to be covered by the ' 1 mill / kwhr U.S. Department of Energy consider the constramts that the presence of spent(DOE) fuel on surcharge. site may impose However, on otherthe study d decommissioning activities. In addition to the removal of radioactivity, this study also assumes the removal of the remainin structures from the site; thereby permitting return of the San Onofre Nuclear Generati Station site for other use. 3.1.1 Period b Preoarations Prior to the commencement of decommissioning operations, detailed preparations are undertaken to provide a smooth transition from plant operations to site decom-missioning activities. These preparations include engineering planning, surveys of plant areas to determine contamination levels, activation analyses of the vessel and vessel internals, as well as the assembly of a decommissioning management organiza-l tion. Final planning for activities and writing of activity specifications and detailed { rom the NRC.rocedures also begm at this time. Period I ends upon receipt of a dism l b i
Document 503 2MO: P 14 of 91 O O 3.1.1.1 Enrineering and Planning l Pric r to the evmmencement Decommissioning Plan (DP) with the of NRC decommissioning,bing descri how it will rem radioactive components and essentially all radioactivity from the San Onofre Nuclear Station site. This request for dismantling of the reactor and termination of the facility's license should include a detailed plan describing the organization l and pro tram that will be used during the decommissioning of the facility. The l plan wi 1 accomplish the required tasks within the As. Aw.As Reasonably. I Achievable (ALARA as defined ha 10 CFR 20) guidelines for protection of per. sonne! from exposure to radioactive and non radioactive contaminants. It will also clearly describe how SCE will contir.ue to protect the health and safety of the public and the environment during the dismantling activity. Prior to the stan of decommissioning o xrations, work begins on the documenta-tion and planning necessary for bot) licensing change applications and for , accomplishing the work requfred. De development of a decommissioning org$ l nization within the utility is essential to this planning. This development includes ! identifying the staff requirements and commitment of key personnel. In preparation for a change in license, re palatory criteria applicable to decom. missioning are reviewed. De existing tecmical specifications are reviewed and ha modified to reflect decommissioning reguirements and to delete non applicable operating specifications. A Decommissioning Plan (DP) is prepared dunng this time. In addition, an environmental assessment may be required by the NRC and all applicable records, Le., as built or revised drawings and specifications, operating records, and site specific background data, will be needed. Much of the work in '.he development of the DP is also relevant to the develop. ment of the detailed engineering plans and procedures. This work includes: Site preparation plans for decommissioning activities, Detailed procedures a.1d sequences for removal of systems and components; Procedures for sectioning and disposing of the reactor vessel and its inter. nals; Plans for decontamination of structures and systems; Design / procurement and testing of special equipment; Identification / selection of specialty contractors; Procedures for removal and disposal of radioactive materials, and l V ' Sequential planning of activities to minimize confilets with simultaneous activitH.
Document S03 25 002 Page 15 of 91 0 3.1.1.2 Site Precarations Following final )lant shutdown and in preparation for actual decommissioning
! activities, the fol owing activities are initiated:
Prepr e site support and storage facilities as required. Convert the existing spent fuel storage facilities into an Independent Spent Fuel Stora ge Installauon (ISFSI) and isolate the ISFSI from the power block such that cecommissioning operations can commence. This acuvity may be carried out by existing plant personnel in accordance with standard operating technical specifications. Decommisining operations are assumed to be scheduled around the Fuel Buildin 7,, which would contain the ISFSI, to the greatest extent possible such that t1e overall p oject schedule is optimized. Since at this time the Department of Energy DOE) will no, accept spent fuel cooled less than 5 years and present DOE ocations for taking receipt of SCE's spent fuel will most likely result in a substantial number of assem-blies being present in the pools at shutdown. Therefore, decommissioning operations for the fuel storage facility (fuel pool) could not be expected to begin prior to five years after the shutdown of Unit 3 at the earliest, p Clean all plant areas of loose contamination and process all liquid and solid d
- wastes.
Conduct radiation surveys of work area contamir ation and general dose levels; major reactor vessel andcomponent, its internals ; piping, internal pipinand structure do activation profiles from primary s)hieldes.core samp;g contamination lev Calculate residual byproduct material inventory for plant components, struc-tutes and systems, and normaiize neutron flux profilet from operations to ' survey data for development of packaging and shipping requirements and decommmioning safety requirements. Determine shipping container requirements for activated materials and fabri-cate such contamers. Develop procedures fo* occupational exposure control, control and release of liquid and gaseous effluents, control of solid radwaste, site security and emergency programs, and industrial safety. Following approval of the DP by the NRC, the NRC will issue an order authorizing implementation. The DP may then be ima:emented by SCE. Fol-lowing receipt of the order to implement the decommiss aning plan, the reactor is disabled by deactivating /de energizing control rod drive mechanisms and implementing modified technical specifications. O V I
Documen: 503 25 00: Page 16 or 91 0 - 3.1.2 Period 2 DecommMoning operationa and License Termination The dismantling procedures may begin upon receipt of the dismantling order from the NRC. For the DECON alternative the decommissioning operations involve the following: Construct temporary facilities and arrange existing storage facilities to support the dismantling activities. Dese may inc ude: changing rooms and " hot" laundry for increased work force, protected and open laydown areas to facilitate equip. ment removal and shinoing operations, additional roads to facilitate hauling and transportation, and ., airlocked access hatch to facilitate entrance into the reactor building for laage/beavy equipment. Design, arocure, and install water cleanup system for removal of cutting residues and cruc deposits from the reactor vessel. Design and fabricate special shielding and contamination control envelopes, spe-cial tooling andhetivities port segmentation remotelyandoperated pre pare rigging equipment. Modify and for segmentation the removal refueling o canal to rupf piping sections and components, inc) uding the reactor vessel and its internals. Procure required shipping casks, liners, and Low Specific ActMty (LSA) con-tainers from suppders. Conduct decontamination of components and piping systems as required. Remove, packt,ge and dispose of piping and components as they are no longer required to support the decommissioning process. Remove control rod drive housings and instrumentation tubes from reactor vessel head and cut into sections for disposal. Reassemble reactor vessel head and flange (following flange separation from vessel) for shipment and burial as its own container. Segment upper and lower core sttyport structures and in-core instrumentation and package in shielded casks. Dese op: rations are performed remotely by cut-ting equipment within a contamination '.antrol enve, ope. Ship and bury pack-aged items. After the vessel water level drops below the elevation of the reactor vessel inlet and outlet nozzles dudng vessel segmentation, remove the reactor coolant piping and pumps. Package the piping in standard LSA containers; the reauor coolant
) umps are sealed with steel plate so as to serve as their own containcrs. Ship and
)ury piping and pumps.
Segment /section the reactor vessel and package into shielded containers. The operation is pert med remotely in air using a contamination control enve' ope. . Sections are placeo in containe:S under water, e.g., in the refueling canal. The O lower head be shipped isown as its leftcontainer. intact. Once Ship aad removed fro;nthe bury packaged thehead is modified to cnity,iterns. I
- - i
l Document 303 !.002 Page 17 of 91 l O Remove systems and associated components as they become nonessential to the support of vessel disposition, other decommissioning operations or worker health (e.g., decommissiorung waste processing systems, electrical systems, HVAC sys-tems, water systems). Remove concreie biological shield and all accessible contaminated cocerete (excluding steam generator and pressurizer cubicles). If dictated by the steam generator and pressurtzer removal scenarios, remove those portions of the associ-ated cubicles necessary for access and component extraction. Remove steam generators and pressurizer for shipment and burial. Decon. tuninate exterior surfaces, as requircd, and seal weld all openings in steam gen-erators and pressurizer. Dese components can serve as their own burial con. tainers provided that all penetrations are properly sealed. Decontaminate all remaining containment structur; areas includlag steam generator and pressurizer cubicles. Perform radiation survey to assure that the remaining portions of the contain-ment structure are free of s.trface contamination and that containment integrity is no longer required. Remove contaminated equipment and material from the fuel storage facility and IcT any other contaminated areas once the spent fuel pool has been emptied. Utilize V radiation and contamination control techniques until radiation surveys indicate that the structures can be released for unrestricted access and conventional demolition. Ship and bury all remainig radioactive materials. Conduct final radiation survey to assure that all radioactive materials have been removed. This survey may cotreide with final NRC site inspection. Following notification by SCE of completion of the decontamination and disposal ' of compouents and materials from the incility, the NRC regional staff conducts an on site survey to verify that the acceptable activity and contunination levels are satisfied. When the requirements are satisfied, the NRC can terminate the license for the main facility and any further NRCjurisdiction over that facility. 3.1.3 Period 3 Site Restoration Following completion of the decommissioning opers.tions, site restoration activities may begin. All building foundations are backfilled using non contaminated concrete rubble with a structural fill to the grade elevation. Site areas affected by the disman-tling activities are cleaned up and the plant area graded and landscaped as required.
'lhese activities include:
Demolition of the remaining portions of the primary containment structure and interior portions of the reactor bitilding. Internal floors (and walls if above
~N , (V grade) are removed from the lower levels upward, using controlled blasting tech-niques. Concrete rubble and other suitable materials can be utilized on site for fill; otherwise the rubble is trucked off site to a local landfill.
i Document 503a5M i Page 18 of 91 l 1 O V Remaining buildings are then removed using coaventional demolition techniques for andabove other site ground structures, structures. including In addition, outsidethe Turbine storage tan BuildL'g,ks are drained removed.
' Prepare the final dismantling program report.
3.2 SAFSTOR (Mothball with Delayed Dismantling) The SAFSTOR decommissioning alternative provides a condition that ensures public health and safety from residual radioactivity remaining at the site without the need for extensive modifications to the facility. While " mothball"is used to describe this alterna. tive (Ref. 2), it is a misnomer since under SAFSTOR reactivation of the plant is not intended. During the SAFSTOR period the facility is left intact and all structures are maintained in a sound condition. All systems not required to be operational for maintenance and surveillance purposes during the dormancy period are drained, de-energized, and secured. Minimal cleaning / removal of loose contamination and/or fixa-tion and sealing of remaining contamination is performed. All access to contaminated are as is sealed and/or secured to provide controlled access for inspection and maintenance. The engineering and 11anning requirements are similar to those for the DECON q alternative althou a s1orter time period is expected for these activities. Site prepara-Q tions are also Emi at to those for the DECON alternative. However, with the exception of required radiation surveys, the mobilization and preparation of site facilities is less extensive. 3.2.1 Period E SAFSTOR Ooerations Prior to commencement of decommissioning operations, SCE will file a Decommis-sioning Plan (DP) wita the NRC describing how it will remove all radioactive com-ponents and essentially all radioactivny from the San Onofre Nuclear Generating Sta-uon Unit 1 site. Bis request for eventual dismantlin6 of the reactor and termination of the facility's license includes a detailed plan desenbing the organization and pro-gram that will be used during the decommissioning of the facility. The ('n will accomplish the required tasks within the ALARA guidelines for protection of per-sonnel from exposure to radioactive and non radioactive contaminants. It will also clearly describe how SCE will contint to protect the health and safety of the public and the environment during the dismantling activities. Following approval of the DP by the NRC, the NRC issues an order authorizing implementation. De DP may then be implemented by SCE. The DP includes spent fuel disposition, partial decontamination, followed by a delay period before the remaining radioactive components are removed. The NRC may amend the operating license to permit " Possession Only" after final plant shutdown. This amended license would remain in effect until final decontamination of the site and its release is com-plete. (9 w/
Document S03 25 002 Page 19 of 91 The Possession Only" license permits ownershio and possession of fuel, by product material and reactor components, but does not ernJt operation of the reactor. This license status, though permitting significant rel ef from the technical specifications, still requires adequate suncillance, monitoring and reportirig. After final plant shutdown, modified technical specifications are implemented. Spent fuel and in core source materials are removed from the unit. Dese steps may be carried out b lant personnel in accordance with standard operating procedures. All liguld and s l d wastes are processed and removed and plant radiation surveys imtiated. . The decommissioning activities for the SAFSTOR alternative are u follows: Convert the existing site ; pent fuel storage facilities into an ISFS1 and isolate the ISFSI from the power block such that decommissioning operations can com-mence. This activity may be carried out existing technical speci ications. pl. int personnel Decommissionir.g in accordance operations with standard are assumed to be schec operatin; u led around the Fuel Building, to the grea sible such that the overal ject schedule is optimized. Since at this time the j De artment of Ener will not accept spent fuel cooled less than 5 an present DOE a oc(D ations for taking receipt of SCE's spent fuel wil!most years l t likely result in a substantial number of assemblies beint Present in the pools at O shutdown, decommissioning operations for the fuel storage facill not expected to be in prior to five years after shutdown of Unh fuel pool) are
, althou h this !
was not considere as a constraint in placing the remaining facil in SAF TOR dormancy. l Drain decom/de energize / secure all non contaninated systems not required to support nusstorung operations. Dispose of contaminated filter elements and resin beds not required for pro-cessing wastes from decontamination activities. Drain reactor vessel; internals will remain in place. Drain /de energize / secure all contaminated system.. Deconta ninate as required. Prepare lighting n'id alarm systems whose continued use is required. De-energize and/or secure portions of fire protection, electric power, and HVAC systems whose continued use is not required. Install reactor building pressure equalizatioh line. This line should be provided with an absolute filter. C'ean loose surface contamination from building access pathways. Perform final radiation survey of plant; post warning signs as appropriate. Erect physical barriers and/or secure all access to radioactive or contaminated areas, except as required for controlled eccess for inspection and maintenance.
. _ _ . _ _ .. _ _ . ~ . _ . . . . - _ . _ _ _ . . _ _ . . . _ _ .. _ _ . _ ._ _
i l Document 503 25 002 ] Page 20 of 91 !O l i j ' Drain and decontaminate spent fuel pool, using high pressure spray as the water ; 3 level is lowered once all assemblies have been removed from the site or to another storage facility on site. Cover pool with steel plate on steel framework I i and provide a High Efficiency Futiculate Air (HEPA) filter unit. I i 1 Install security and surveillance monitoring equipment and relocate security fence around secured structures as. required j - Nonradioactive structures, located outside the secured area, may be demolished. However, this study assumes that demolition would be d , layed until after license
- termination.
i
- Sections of the site outside the control'ed area may be graded and landscaped as- ,
i required. Part of this site area may be released for unrestricted use or for i restricted use, depending on the terms of the possession only license. ] Prepare final decommissioning program report for submittal to NRC. i j 3.2.2 Period 2! SAFSTOR Dormangy ; r l- Activities required during the planned dormancy period, for the SAFSTOR alterna- -i }/3 tive, include a 24 hour guard force, preventive and corrective maintenance on security ' \_/ systems, area lightin encral building maintenance, heating and ventilation of build-i ings, routine radiol cal inspections of contaminated buildings, maintenance of structural integrity, an . an environmental and radiation monitoring program. l Maintenance and equipment inspection activities are provided by a utility L maintenance staff. Deir duty is to maintain the structures in a safe condition, pro-vide adequate lighting, ventilation, and heating, and perform periodic preventative i maintenance on essential equiptnent. An environmental surveillance program is carried o st during the dormancy period to ensure that releases of radioactivity to the environment are controlled. Such releases are identi6ed and quanti 5ed. Appropriate emergency procedures are estabiished and l initiated for releases that exceed orescribed limits. De emironmental turveillance program will generally be a modlied/ abbreviated version of that carried on during j normal plant operations. - ! Security during the dormancy period is conducted pri narily to prevent unauthorized i entry and to >rotect the public from the consequences of their own actions. Security ! detection ant notification systems used during plant operations are augmented by the - i installation of audible alarms. Since contaminated areas and equipment can con-ceivably be reached by the breach of only a door or window, a full time security force is maintained on site throughout the SAFSTOR dormancy. Additionally, silent ! ~, alarms may be installed to alert off site security personnel to trespass and fire. Liaison with locallaw enforcement agencies is maintained and their assistance
- requested as necessary. -
i
..,me.-,. .--.r,-.,-w-2 .--re #-- -- ,--ww-+v,,v-re,-..- ,,-+--,,---,-----r-.,-wen., -ee ,- , ., * ,w-, ,,y,m,,-v--w.-m-+-nwar-wy r n aiw e<wr
Document S034$ 002 Page 21 af 91 (D v Primary physical security is provided by the securg fence which must be maintained in ood condition for the duration of this period. The facility will also be secured by hi security locks on exterior doors and intrusion alarms. Fire and tr.diation alarms wt be mon.tored continuously by security personnel. In addition, until the fuel assemblies are removed from the site, additional security will be maintdned on site. 3.2.3 Periods 3 5 SAFSTOR Delaved Removal / Dismantling At the end of the dormancy period for the SAFSTOR alternative, the remaining the same dismantling operations as Atnictures are completely those described dismantled. for the DECON Basically,ll alternative wi be xrformed. Penod 3 activities would correspond to the DECON Period 1 Planning Phase, Period 4 to the Period 2 Decommissioning Operations Phase, and Period 5 to the Period 3 Site Restoration Phase. Section 3.1 of this report delmeates the activitics associated with each phase of the decommissioning, process. Because this alternative provides a period of decay of tbs residual radioacuvity, lower personnel radiation exposures are incurred than with the DECON alternative. Many of the dismantling acuvities may employ manual techni ues reher than remote procedures. Thus, dismantling operstlons can be sirapithed.
- Although the initial radiation levels due to Co60 will decrease sir:nificantly during the
('] dormancy period, the internal components of the reactor vesse, will still have suft). ciently lugh radiation dose rates to require remote sectionin presence of long lived radionutildes such as Nb94 and NI59.g under water due to th Therefore, the disman-tling procedure. described for the DECON alternative would be employed. Portions of the concrete shield will still be radioactive because of the presence of activated trace elements with long half lives and will require controlled removal, packaging, and burial procedures, it is unlikely that radioactive corrosion products on inner sur-faces of piping and components will have decayed to levels that will permit i unrestricted use or allow conventional removal. Dese systems and components are surveyed as they are remov:d with disposition dependent upon the existin g release l critena. No systems in this study designated as contaminated in the DECOb alterna-tive are assumed to be releasable after the dormancy; these are removed and dis-posed of as contaminated material. Following notification by SCE of completion of the decontamination and disposal ot components and materials from the facility, the NRC regional staff conducts an on-l site survey to verify that the acceptable acuvity and contamination level requirements are satisned, "' hen the requirements are sadsfied, NRC can terminate the license and any furtl.9 4RCjurisdiction over the facility. Site restoration activities may now be performed, similar to those for DECON, for l structures still remaining on site. De site is graded and landscaped as required. A l final decomrnissioning program completion report is then prepared. t l L] l l 1 i
Document S03 25 00 Page 22 of 91 l O V
- 4. COST ESTIMATE A site. specific cost estimate was prepared for the San Onofre Nuclear Generating Station to account for the unique features of the nuclear steam supply system, electric power generation systems, site buildings and structures. The basis for the estimate (including the source of information), methodology, site specific considerations, assumptions and total costs, are described in this section.
4.1 BASIS OF ESTIMATE A site specific cost 3 stimate was developed using San Onofre Nuclear Generating Sta-tion drawings and the inventory Jocuments provided by SCE. These drawings and docu-ments were used to develop the general arrangement of the facility and to determine estimates of building concrete volumes, steel quantitLs, numbers and sizes of com-ponents, and land area of the site restored. Decommissioning is a labor intensive effort. Representative labor rates for each craft or salaried worker are essential for the development of a meaningful site specific decom-missionin of labor, g cost estimate. Consequently, SCE provided the information on the local cost f s Dispositica of radioactive wastes is a major contributor to the cost to decommissioning. The availability of burial sites is of national concern, with regional compacts being formed to provide adequate burial space for operating and planned reactors, in this study, the Ward Valley burial site is assumed for cost estimating. The cost for disposal at this, as yet undeveloaed, site is based upon information obtained from the current operating facility in Hadord, Washington. Listed below are the major factors considered as the basis of the cost estimates:
- 1. San Onofrs Nuclear Generating Station drawings, equipment and structural speci.
fications, including construction details, were provided by SCE.
- 2. Employee salary and craft labor rates for site administration, operations, construc-tion and maintenance personnel were provided by SCE for positions identified by TLG Engineering.
- 3. En gineering services for such in ms as writing activity specifications, detailed pro-cec ures, detailed activation analy:,es, structural modifications, etc. are assumed to be provided by a Decommissioning Operations Contractor (DOC).
- 4. Material and equipment costs for conventional demolition and/or consuuction activities were taken from R.S. Means Construction Cost Data (Ref. 3).
- 5. Rates for shipping radioactive wastes were provided by Tri State Motor Transit in published tanffs for this cargo (Ref. 4).
O' 6. 8eri i cest> >t tae ie ei re die etiv e - ste oise e s>i r ciii assumed rate of $1f0 00 per cubic foot and supplemental ere d in7ormation see re= == provided U.S. Ecology for the Hanford site. (Ref. 5).
i i ! l
- Document S03 25 002 l
Page 23 of 91 LO i i ~ l 7. All costs l~n this estimate were calculated using 1990 dollars. 'Ihe estimates exclude interest and escalation.
- 8. 1.4ase payments for the property were provided by SCE for inclusion in this study.
l . j 9. This study does not address the remova! or disposal of s)ent fuel from the site. l The costs for such activities are assumc3 to be covered by 3OE's 1 mill / kwhr sur-
- charge. However, this study does consider the constraints that the presence of spent fuel on site may impose on other decommissioning activities due to the
- inability to ship spent fuel cooled less than five years to the DOE repository and the expectation that the spent fuel storage facilities at the San Onofre Nuclear
' Generating Station will be near capacity upon final shutdown. Based upon these . factors anc the information provided by SCE, the Fuel Buildings at the San Onofre Nuclear Generating Station Units 2 and 3 will not be available for decommis- ! sioning until approxunately five (5) years after the final shutdown of these units. i .
- 10. Ultimate license termination for the San Onofre Nuclear Generating Station site is based u)on DOE's current acceptance schedule for the spent fuel assemblies en-ersted c uring plant operation. Furthermore, this study presumes the availabili of
- a Monitored Retrievable Storage (MRS) facility such that DOE can meet its li- .
gation to begin receiving fuel by 1998.
- 11. ufrements during decommissioning va with the level of The SCE staffinkththe various phases of the on site storage o spen effort associated i 12. This study follows the principles of ALARA through the use of work duration adjustment factors which incorporate such items as radiological protection fru,truc-l tion, rnock up training, the use of respiratory protection and personnel protective i
cleting. These items lengthen a task's duration, which increases the costs and i lengthens the schedule. AI ARA planning is considered in the costs for engineering and planning, and in the development of activity specifications and detailed procedures.- 1
- 13. This study is performed in accordance with the published study from the Atomic -
i Industrial Forum / National Environmental Studies Project report AIF i " Guidelines for Producing Commercial Nuclear Power Plant Decom/NESP-036, missioning Cost Estimates" Ref 6 l the review of a(task fo). rceThe contents consisting of those guidelines of representatives from were prepared utilities.' state under ! regulatory commissions, architect - Regulatory Comminion, the Nuclear / engineering Regulatory Commiss firms, ion, and the Nation l Anociation of Regulatory Utility Commissioners. - L
- O
Document S03 25 002 Page 24 of 91 4.2 METHODOLOGY The methodology used to develop the cost estimates follows the basic approach originally presented in the A1F/NESP 009 study report, 'An Enpneering Evaluation of Nuclear Power Reactor Decommissioning Alternatives" Ret. 7
" Decommissioning Handbook" (Ref. 8). These reference (s utilize) and the US DOE a unit cost factor method for estimating decommissioning activity costs to simplify the estimating calcula-tions. costs cutting Unit 5cost factors for concrete removal ($/ cubic yard) steel removal ($/ ton) and Wi were developed from the labor and material cost information pro-vided by SCE(. /in)th the item quantity (cubic yards, tons, inches plant drawings and inventory documents, the activirv-dependent costs are estimated.
The unit cost factors used in this study reflect the latest available information about sioning stoductivity
?roject,incompleted decommissioning, includien in 1989. the Shippingport Station Decommis-worker The activity duration critical path was used to determine the total decommissioning gram schedule. The program schedule is used to determine the oeriod dependent costs for program management, administration, field engineering. equipment rental c ciated with period dependent costs. The costs for convent.onal d asso-radioactive structures, materials, backfill, landscaping and equi q obtained from the " Building Construction Cost Data" pubitsbed by R.pment rental were t
V Exam S. Means (Ref. 3). (Ref. ples of unit cost factor development are presented in the AIF " Guidelines" stu 6 , one of which is reproduced m Appendix A. Appendix B lists the specific factors develop)ed for the San Onofre Nuclear Generating Station ana The activity and period depe". dent costs are summed to develop the total decommis-sioning costs. A contingency is then applied. ' Contingencies" are defined in the Am ican Association of Cost Engineers' Cost Engineers' Notebook Ref. 9) as " sp vision im for unforeseeable elements of cost wiihin the defimed pr(oject scope
>ortant where previous experience relating estimates and actual costs has shown that uforeseeable events which will increase costs are likely to occur." The cost elements this estimate are based upon ideal conditions, therefore a contingency factor has be applied. As with any major project, items which could occur that have not been accounted for in this estimate are changes in the regulatory requirements, the effects of craft labor strikes bad weather halting or slowing down waste shipments to the burial grounds, tions, etc. Inequipme,nt/
the AIF tool breakage, changes in the anticipated plant shutdown c Power Plant Decomm/NESP-036 study," Guidelines for Producing Commercial Nuclear issioning Cost Estimates" Ref. 6 the types of unforeseeable vided for percentage contingency in each category. S examined yielded an average contingency of approximately 25% Application of con-tingency was limited to the estimate's subtotal and not assigned on a line item basis . The unit cost factor method provides a demonstrable basis for establishing reliable estimates. The detail of activities provided in the unit cost factors for activity time labor
/3 costs (by craft , and equipment and consumables costs provide assurance that cost ele-V ments have no)t been onutted. 'Ihese detailed unit cost factors coup specific fidence in theinventory reliabil of ' ing, components and structures provide a fhigh con- degree o?lant.
of the cost estimates. l l
Document S03 25 002 Page 25 of 91 4.3 SITE SPECIFIC CONSIDERATIONS There are a number of site s >ecific considerations that affect the method for dismantling and removal of equipment from the site and the depee of restoration required. The cost impact of these considerations identified below is included in this cost study. 4.3.1 Maior Component Remon) The reactor pressure vessel and reactor internal components are segmented for dis-posal and shipped in shielded casks. Segmentation and packaging of the internals Jackages is performed in the refueling canal where a turntable and remote cutter will 3e installed. The s asel is segmented in place using a mast mounted cutter supported off the lower head and directed from a shielded work platform installed overhead in the canal. Shipping cask specifications and U.S. Department of Transpor'ation (US DOT) regulations will dictate segmentation and packs methodology; allpackages desi nated meet current p sical and radiological 11 tions and regt:anons. All cas hipments are made in S DOT aporoved, currently available, tn ck casks. Both the closure head and the reactor veuel lower head are disposed intact. These com-ponents are modified for shipment as the.fr own containers and shipped to the burial site along with the steam generators, reacter coobit pumps and pressurizer. O Reactor coolant piping is cut from the reactor vessel once the water level in the vessel (V (used for personnel shielding during dismantling and cutting, operations in and around the vessel) is dropped below the nozzle zone. The piping is boxed and shipped b Welded van. The :cactor coolant pumps, moto.s and the pressurizer are lifted out tset, packaged and transported along with the steam generators. The steam generators are assumed to be removed as follows: an auxiliary trolley placed on the Reactor Building bridge crane rail is used in conjunction with an elevated runway with a trolley outside the equipment hatch to extract the The equipment hatch may be enlarged, or a secondary opening created, generators. to accom-modate intact removal or the generators. Once outside the containment structure, the generators are moved to a temporary staging area on site. The generators are then prepared and moved off site by overland transport to the burial site. Prepara-tion may involve the removal of the steam dome such that clestances and payload capacities can be met, The main turbine is dismantled using conventional maintenance procedures; the tur-bine rotors and shafts are removed to a clean i down area for disposal. The lower turbine casings are removed from their anchors y controlled demolition. The main condensers are segmented and transported to the laydown area for disposal as scrap along with the lower turbine casings. p
Document S03 25 002 Page 16 of 91 O b 4.3.2 Transoortation Methqds For the purposes of cost estimation, it was assumed that the NSSS components are moved by a combination of overland transporter and rail to the regional burial facility. These payloads include the reactor vessel head packages, reactor coolant pumps, the steam generatcts and the pressurizer unit. In this study it is assumed that the steam generator units are removed sequentially and stored on site in a temporar,
- i. aging area. The generators are then rigged for loading onto the transports.
4.3.3 Site Condit ions at Facility Closcam It is assumed that the site is restored by regrading to conform to the adjacent landscape. Sufficient topsoil is to be ? laced to permit new growth of native vegeta-tion. De intake structures on site wij be demolished and removed, the circulating water conduits dredged and removed and the underground piping on site excavated and removed and the depressions backfilled. No suburface structures will remain. 4.4 ASSUMPTIONS The following ate the major assumptions made in the dev:.lopment of the cost estimates for the San Onofre Nuclear Generating Station. 1. ,(7 SCE will hire a Decommissioning Operations Contractor (DOC). The DOC wiil V provide sufficient staff to perform the preparatory demolition planning and sched-uling, and manage the demolition efforts. Site security during demo.ition is pro-vided by SCE or its subcontractor. The demolition work is performed by the DOC or a demolition subcontractor who will provide adequate staff, labor, equipment, materials and overhead to coraplete the demolition. 2. Only existing site structures and those presently in the construction stage are con-sidered in the dismantilng cost. Tentative designs and future site improvements are not cotisidered. 3. A burial facility was assumed to exist at Ward Valley. 'Dtis location was taken as the final destination for all radioactive waste shipments from the San Onofre Nuclear Generating Station. 'Ihe cost of burial at this yet to be-developed site was based upon an assumed burial rate of S150.00 per cubic foot and supplemental costs provided by U.S. Ecology for their Washington Nuclear Center in Hanford, Washngton. Out-of-compact surcharges were not included. 4. No plant process system identified as being contaminated upon final shutdown will become releasable due to the decay period, i.e., there is no significant reduction in waste volume in delaying decommissiomng. 5. The decommissioning activities are performed in accordance with the following regulations: 10 CFR 20 Standards for Protection Against Radiation 10 CFR 30 Rules of General Applicability to Licensing of Byproduct Materials
Document S03 *.5-002 Page 27 of 91 10 CFR 40 Licensing of Source Material 10 CFR 50 Domestic Licensing of Production and Utiliza-tion Facilities 10 CFR 51 Licensing and Regulatory Policy and Procc-dures for Environmental Piotection 10 CFR 61 Licensing Requirements for Land Disposal of Radioactive Wastes 10 CFR 70 Domestic Licensing of Special Nuclear Material 10 CFR 71 Packaging and Transportation of Radioa nive Matenah 10 CFR '/2 Licensir.g Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation (ISFSI) 10 CFR 73 Physical Protection of Plants and Materials 10 CFR 170 Fees for Facilities and Material Licenses and Other Regulatory Semces 29 CFR 1910 Occupational Safety and Health Standards 49 CFR 170178 Deor.rtment of Transportation Regulations Go'verning the Transport of Hazardous Materials f's V All environmental regula.tions in force in 1990 are in force during decommissioning effort.
- 6. Nuclear liability insurance provides coverage for damage or injuries due to radia-tion exposure from equipment, material, etc. used durinF de ommissioning.
Nuclear liability insurance is phased out upon final decontamination of the site. Nuclear liability as well as property msurance premiums were provided by SCE.
- 7. Lease payments for the San Onofre Nuclear Generating Statiun site are included in the esumate. These costs were provided3 b ' ' '
- 9. The NSSS (reactor vessel and reactor coole .,ste,ms) are chemically decon-taminated m.ng one chemical flush and two water nnses pnor to segmentation.
Typically, a decontamination factor (DF) of 10 is expected (Ref.10).
- 10. In Period 1 of SAFSTOR it was assumed that the level of effort required to accomplish the activities called for additional labor from off-site personnel. It is these personnel that are costed and accounted for in Period 1. De utility per-sonnel perform the remaining activities as indicated in the detailed cost tables by the de",ignation "a".
N (G
Document S03 25 002 Page 28 of 91
/T V
- 11. R~ctor vessel and internals packages conditions:
Any fuel cladding failure that has occurred or may occur during the ;7: time of the plant is assumed:
- 1) to have released fission products at sufficiently low levels that the buildup of vented from reaching levels exce(edmg those which perm ponents to be shipped es LSA waste and burial within the requirements of 10 CFR 6) or the regional burial ground, or
- 2) to have necessitated systematic decomamination during the operating life of the plant and therefore the radionuclide. Icvels are acceptable for transport as LSA wastc and burial within the requirements of 10 CFR 61.
All control element assemblies are .; .ced, shipped, and buried by the utility along with the spem fuel. This acti vity v gaid for by plant operations and is not considered a decommissiorang exper
'Ite curie contenu of the vegel and internals at final shutdown are derived from l
l those Ci/ gramlisted in NUREG values 'CR-3474 (Ref.11). Actual estimates are derived from the in NUkEG San Onofre Nuclear Genera /CR-3474 and adjusted for the different mass of the n ting Station cocponents, projected operating life, as
' U well as for different periods of decay. Addit: anal short livec' 'sotopes were derived chmarked to the long lived (values fr)om NUREG/CR-3474.from 12.
The reactor vessel and internals disposal costs are based on remote segmentation in place, packagit.g in casks with shielding, and shipping by truck to the burial ground. A maximum no mal road weight limit of 80,000 pounds is assumed for all t:uck shipments including cask shipments. This includes vessel segment s), sup-plementary shielding, cask tie-downs and tractor trailer. The maximum cu( shiprc.ent assumed permissible are based on the license limits of available shielded shipping casks. The number and curie content of vessel segments are selected to meet these hmits.
- 13. Overland transport costs for the steam vided by Reliance Trucking of Phoenix, generators arehandled based theon over-information pro-Arizona. Reliarn has land transport and instalianon of NSSS components for several plants.
- 14. Steam generators are removed sequentially and sto on site until ready to be moved. This scenario will consolidate shipping and reauce mobilization costs for the heavy haul vehicles.
15. The aan Onofre Nuclear Generating Station is isolated electrically from the rest of the transmission system and completely decommissioned (i.e., the plant will be out of service prior to commencing the demolition effort). 3 16. (C SCE provides for the electrical power to be broug'ht on-site required to demolish the plant.
! Document S03 25-002-Page 29 of 91 ,O L -
- 17. Scrap item m, gene' rated during decommissioning is not included as a salvage c this study for two reasons: (1 the scrap value merely offsets the associated '
site removal and scrap reprocessing) costs, and (2) a relatively low value
- exists in the market. Scrap processmg and site removal costs are not included in l the estimate.
i i Decommissioni..g will take place suf6ciently far in the future that all equipment
- will be worn, obsolete and suitable for scrap as deadweight quantities only. No j equipment is salvageable as used equipment.
. 18. SCE removes att items of furniture, tools, mobile equipment such as forklifts, trucks, bulldozers, other similar mobile equipment and other such items of per-
- sonal property owned by SCE that is easily removed without the use of special ,
i equipment. Derefore, no cost of removal is included in the decommissioning cost estimate for such non affixed items.
- 19. Existing warehouses will remain for use by the demolition contractor and its sub-l contractors, as well as SCE. The-warehouses will be diamantled as they are no
!- longer needed to support the decomminioning program. l 20. All contami' sated piping, components and structures other than the reactor vessel and internals are assumed to meet US DOT limits for LSA material.
- 21. Fuel oil tanks will be em atied. Tanks are cleaned by Gushing or steam cleaning as required prior to disposa..
- 22. Acid and caustic tznks are emptied through normal usage.
- 23. Lubricating and transformer oils are drained and removed from site by a waste dis-j posal vendor.
} 24. All structures and site improvements will be completely removed and the local ter-j rain restored to the local grade level. Subsurface structures will be excavated. The - intake and discharge conduits lo~ :d beneath the ocean floor will be uncovered and removed using a barge mounwd clamshell bucket. Scows will dump the sedi-ment out to sea. The conduit will be removed in sections as it was originally i placed. ' [ 25. Below grade excavation will require site dewatering. Conseguently,16 dewatering - t wells have been costed for the site demolition period. This is consistent with what !- was required during construction. In addition two wellpoint systems and steel j sheet piling were used to provide additional dewatering around the intake struc-F tures as the foundations -e among the deepest on site.
- 26. De gunite placed on the bluff Nes will be removed. The station grounds will be-
- planted with vegetable matte. t'or erosion control and will have a final contour
[ s consistent with the surrounding area. i
- . . - -_-.,.a 2- .,.-...-,.:
.. - - - . - - - .. .- . . ~. -. - .-
Document S03 25 002
]
- Page 30 of 91 O
- 27. Concrete in and around the Service Water Reservoir will be removed. Natural berm material will be pushed in and the pond backfilled. The seawall will be com-pletely removed.
l I
- 28. The railroad spur on site will be removed to its junction with the mairc:.
- 29. The perimeter fence is moved as app,ropriate to conform with the technicJ specifi-cations in force at the various stages m the project.
- 30. All road and parking area base material remains in place. Road and parking areas
, with asphalt surfacmg or concrete are broken up and the asphalt and concrete i removed. All gravel road and parking areas remam in place and the area covered with fill.
- 31. This stud estimates that there will be some radioactive wasta generated which is greater than 10 CFR 61 Class C quantities, resulting from disposal of the highly activated sections of the reactor vessel internals. This waste will most likely be dis-posed of as High Level Waste in the DOE's deep geological repository unless an alternative solution is approved the NRC. The cost of disposal, unhke that for the spent fuel,is not covered b DOE's 1 mill / kwhr surcharge, and has been J
estimated from information on hi y radioactive Type C waste disposal costs. q 4.5 COST ESTIMATE
SUMMARY
V A summary of the deccmmissioning alternative costs with annual expenditures is pro-i vided in Table 4.1. Table 4.2 shows the breakdown of tS decommissioning costs mto
- the com egories.ponents These costsofwere labor, taken material from the/cquipment, burial, transportation, detailed cost tables,4.3,4.4 and 4.5. and other cost c
! Tables 4.3,4.4, and 4.5 show the detailed listing and costs of major activities for each unit decommissioning scenario. Note that "Decon" as used in the headings of these ' tables, refers to decontamination. It should be noted that " Total" as used in t 3e heading of tables, is the sum of Decon, Remove, Pack, Ship and Bury as well as other miscel-i laneous items not listed (such as engineerint; and preparations). Staff relocation expenses are those costs associated with movinC X)C/SCE personnel to the site; either for perdiem allowance or for moving expenses. 4-4 i !o 4 p -v- n ,
Document S03 25 002 Page 31 of 91
- O TABLE 4.1
SUMMARY
OF DECOMMISSIONING COSTS 3 (Thousands of Dollars) 3
. Alternative Period Calendar Cosal Year (1,000s)
San Onotte Nuclear Generating Station Unit 1 4 SAFSTOR (Mothball w/8 year Dormancy, Delayed / Dismantling) Preparations 1 2004 16,501.5
-2005 4.1%.2 Subtotal Period 1 20,697.7 1
Dormancy 2 2005 2,597.0 2006 3,256.9 201 3,26.3 2014 1.122.1 Subtotal Period 2 29,774.2 Dismantling Preparations 3 2014 7.999.6
- Subtotal Period 3 7,999.6
- Decommissioning Activities 4 2014 6,148.0 2015 39,813.4 2016 39,813.4 2017 2M49.4
, Subtotal Period 4 109,224.2 Site Restoration 5 2017 10,433.7 2018 25,385.1 ' 2019 7.898.3 Subtotd Period 5 43,717.1 Total Cost for Unit 1 211,412.8 1 All costs reported in 1990 dollars; costs may not add due to rounding
Document 503 25 002 Page 32 of 91 O TABLE 4.1
SUMMARY
OF DECOMMISSIONING COSTS (Thousands of Dollars) Alternative Period Calendar Costl Year (1,000s) San Onofre Nuclear Generating Station Unit 2 DECON (Prompt Removal /Dismantilng) Preparations 1 2013 0.0 2014 13.1 2015 19.825.2 Subtota! Period 1 19,838.3 Decommissioning Activities 2 2015 283.1 2016 69,870.7 2017 69,870.7' Os 2018 2 L 624.6 Subtotal Period 2 161,649.1 Site Restoration 3 2018 22,601.5 2019 32,731.8 2020 32,731.8 2021 6.212.3 Subtotal Period 3 94,277.4 Total Cost for Unit 2 $275,764.8 1 All costs reported in 1990 dollars; costs may not add due to rounding O
. . - - . . - . = . ..-- . . _ . - - . - .. ..
Document S03 25 002 Page 33 of 91
- O TABLE 4.1-SUhntARY OF DECOMMISSIONING COSTS (Thousands of Dollars) l Alternative Period Calencar Costl Year (1,000s)
San Onofre Nuclear Generating Station Unit 3 DECON (Prompt Removal / Dismantling)
- Preparations 1 2013 0.0
- 2014 0.0 2015 7,487.2
' 2016 12.930.5 Subtotal Period 1 20,417.7 i Decommissioning Activities 2 2016 27,254.7 i ( 2017 73,890.4 2018 73,890.4 2019 25A52.4 Subtotal Period 2 200,687.9 i Site Restoration 3 2019 25,799.6 - 2020 39,519.6 2021- 39,519.6. 2022 39.519.6 2023 3.445.1 Subtotal Period 3 147,803.6 , Total Cost for Unit 3 $368,909.2 d 4 1 All costs reported in 1990 dollars; costs may not add due to rounding 4 f
Document S03 25 002 i Page 34 of 91 iO f TABLE 4.1
SUMMARY
OF DECOMMISSIONING COSTS (Thousands of Dollars) Alternative Period Calendar Costl Year (1,000s)
- Independent Spent Fuel Storage Installation
- Spent Fuel Storage 2013 54,082.6 2014 19,618.4 l.
2015 16,957.3 2016 14,655.4 2017 14,294.4 2018 1 L312.2 Total Cost for 15cSI $ 80,920,3 l 5 i i i Total Cost for the San Onoth Nuclear Generating Station $937,007.2 l i 1 All costs reported in 1990 dollars; costs may not add due to rounding i 4
- - _ _ g -
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i Document $03 25 002 Page 36 of 91 O TABLE 4.3 COST FSTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclear , Generating Station Unit 1 (THOUSANDS OF 1990 DOLLARS) l Activity
- Doctm temove Peck ship tury Total Cu N Scrap m hre n tem Pu lap 1: Itethbettire Activities
- 1. temove fuel & source material n/a
- 2. Decon plar.t & process mute e
- 3. Review plant asse & specs. 78 l 4 Perform estatted red survey e
- 5. Estlante tv prome:t inventory 70
- 6. Submit for possession only ticenes 60 7 End proaact description 60
- 8. Detailed try proem
- t inventory 100
, 9 Define mejor work seguance 64 10 Perform safety onelysis of operation 125
- 11. Perfore safetv enelysta of and proma:t 125
- 12. Se mit dienantLing plen 60
- 13. Receive possession only license a Activity Specificetteru 14.1 propere plant and f acilities for motteet 295 14.2 Plant systeen 249 i
14.3 Plant structures and tuulldinge 187 4 14.& Weete sensgement 120 ! 14.5 facility and site dormancy 120 14 Total 970 l Detalled Idart Procedase 15.1 PLent syetema 283 15.? FoctLity closecut & donnancy 72
- 15. Total 355 l 14. Procure vastas drying systen 6 17 Orsin/de-unorgine non cont. systema a
- 18. Drain & dry 18888 a
- 19. Drein/de energine cantaminated systsas a
- 20. Becan/ secure cantaminated sp tens a !
- 21. Decon spent fuel rocks 52 52 1125 <1 ;
- 22. Propere seport e@fpment for storage 243 263 3000 3 i 23. Irwtelt containonnt pressure spot, line 30 30 700 2 Decentaminstian of site Buildirge 24.1'contalement 743 743 16029 53 24.2 Fwl Building 305 30$ 7058 14 ,
24.3 teactor Auxiliary 82 62 1696 6 l i 24.4 taeseste (Ptase I: 29 29 595 4 1 i V 24.5 teaseste Building (Phase ll) 33 ' 33 689 5 26 Totats 1192 1192 26068 81 1
l I Document S03 25 002 l Page 37 of 91 ! O TABLE 4.3 (Continued) i COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclesr Generating Station Unit 1 Activity Decan temove Peck $ hip tury fotel ru id Scrap N hrs N-tem
- 25. Interie survey prior to ooreency 300
- 26. Secure tuilding accesses a Propere & s e it interie report
- 27. 35 S etetet Period 1 Activity Costo 1244 2M 3M4 30093 87 Period 1 Lauff stributed Coste l 1. Decon equipment 163 163
- 2. Oecon a g ties 184 184
- 3. Process ticuid weste 139 75 74 142 431 33 346 <1 4 Insurance 784
- 5. Property temos 219
- 6. Nestth pnyelce supplies 424 424
- 7. SeeLL toct aLLomence 11 11
- 8. Disposal of conteeinsted solid was.J 68 16 1387 1470 342 2515 6
- 9. Plant energy budget 484 S4teteL Perfod 1 Uhdiatributed Caeta 4M 4b 143 90 1529 4174 375 2881 7 C0C Staff Cost 0 utili t y Staff Cost 8460 Suetotel Staff Costs for Period 1 8440 TOTAL CDST TO W NBALL 1730 728 143 90 1529 16558 375 33773 94 TOTAL CnET To uofleALL WITk 251 Cort!uGesCY: $20,697,730 TUIAL NOTNEALLits RA0 WASTE MJAE suRIEO IT5 (U 10s TOTAL SceAP teEMD: 0.0 Tous TOTAL CRAFT (Jala NmJIaBENTS: 33,773.4 nam utmas TOTAL PetSGREL RA0!ATION DEPOEURE: 93.7 genu met TOTA'. G AFT LAa0R CDET WITW 25 1 CONTIueDeCT: $1,542,545 MOTES: "n/es indicates tPat fuel handling, packaging, ehlpping, and disposet are charged to plant operations, not decommissioning
*e indicates that caste are included in the u"flity staff coste.
l Att coste ve romded; cotuens soy not total chae to rowntoff error O d
l Document S03 25 002 l Page 38 of 91 l TABLE 4.3 (Continued) COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclear
- Generating Station Unit 1 4
Activity Decen temove Pack Ship tury Total Cu td Scrap N hrs N tem 9 PEtitB 28 nothhelled Arviust me'ntenance Cost
- 1. Que-terly inspection e
, 2. semi arruel environmental survey s
- 3. Propere reports s
, 4. Meetth physics s e lles 31
- 5. Insurance 530
- 6. Property taxes 219
! 7. Dispoest of contaminates solid waste 5 <1 <1 19 25 5 35 <1 , 8. Bitusinos.e roof reptocement 433 i 9 Maintenance st4apties 67
- 13. Plant enern- budeet 45
- 11. Site mainteneswa stoff 1255 PERIOD 2 ANILIAL MAINTEMmG TOTALS 5 <1 <1 19 2606 5 35 <1 l rh MAlitTEMNG CDET Fat 9.141646 YEARS 90AstaleCT: S 23,819,360 l TOTAL MAINTEMARIG CDST WITu 25 3 CERITINGleCT: S 29,774,200 I
l l l NOT's *s* Iruficates rhet the cost is included in the utility maintenance staff cost. l lO l
Document SOL 25 002 Page 39 of 91 TABLE 4.3 (Continued) COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclear Generating St* tion Unit 1 Activity Decen Remove Pack Ship tury Total Cu td Scrap M hrs M-tem PitI(3 3
- 1. Review plant dues & specs. 275
- 2. Perfore detailed red survey a
- 3. End product description 60 4 Detailed tpr pects.ct inventory 88
- 5. Define sejor mort secuence 453
- 6. Perfore safety enelysis 191
- 7. See!t diementtine plan 31
- 8. Receive dissentilne order a sihtetet Period 3 Activity Casts 1004 Period 3 undistritasted Cosw
- 1. Staff relocation ea, 377
- 2. Insurance 393
- 3. Property taaes 110 Q 4 Neelth phycica sosplies 425 425 Q 5. neevy eiwipment rental 90 90
- 6. Olsposat of contaminated solid weste 7 2 139 147 34 251 <1 7 Ptent energy budget 271 Stanotal Period 3 undistritested costs 515 7 2 139 1813 34 251 <t DOC Staff Coet 2100 utitIty Staff Cost 1389 Subtotal Staff Costs for Period 3 3489
, TOTAL Pfalas 3 COET 515 7 2 139 64Ge 34 251 <1 Pfttap 4 Activity specific tic u 9.1 te artivate plant & temporary facilities 441 9.2 Plant systeen 249 9.3 teactor internets 425 9.4 teactor vesset 389 9.5 Bioloelcat sateld 30 9.6 Steen einerators 187 1 9.7 teinfusted ccacrete % 9.8 Tuttine & condensec 48 9.9 Plant structures & buildines 187 9.10 Weste menneement 275 9.11 Feellity & site closecut 54
\
- 9. Total 2381 i
Document S03 25 002 Page 40 of 91 TABLE 4.3 (Continued) COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclear Generating Station Unit 1 Activity Decen Remove Peck Ship twy Total N Td Scrap N hrs M-tes Plamirg & Site Preparation
- 10. Propere dismantling segaence 144
- 11. Plant prep. & teep, syces 1283
- 12. Design water clean up systes 84
- 13. Rigging /CCEs/ tooling /etc. 1086
- 14. Procure cooks / liners & containers 74 Detelled Wert Procedarse 15.1 Ptent systeme 283 15.2 Vessel head 150 15.3 Reactor internate 150 15.4 Rosetning buildinge 81 15.5 Cao cooling esseemly 60 15.6 CAD houstnce & ICI tw ee 60 15.7 Incore iretrumentetton 60
- 15. tenctor vessel 217 j 15.9 Facility closecut 72 15.10 Missile shielde 27 L 15.11 Biological shield 72 15.12 3 teen eeneratora 275 15.13 Turcine & concensers 187 15.14 mainforced concrete 60 1%.15 Auxillery Building 163 15.16 Reactor building 163
- 15. fotel 2000 Back Runnel
- 16. Spent f*.ael rects 10 12 2 382 405 94 276 <1 uuclear Steam Sigiply System temowel 17.1 teactor Coolant Piping 10 103 8 2 129 251 32 2784 16 17.2 Pressuciter Relief Tent 4 80 3 1 69 157 17 2094 15 17.3 teactor coolant Ptape & Motors 18 34 30 43 837 941 196 1515 10 17.4 Pressuriser 6 43 5 19 308 382 71 1202 6 17.5 steen Generatore 28 3105 118 1027 2910 7109 689 73657 55$
17.6 Caome/ICIs/ service stri.-tt.re tenovel 23 37 19 5 255 340 63 1426 11 17.7 teactor vessel Internate 105 958 279 280 1402 3024 141 14115 27 17.8 Reector vessel 143 1469 295 .183 1272 3362 290 14115 27
- 17. Totale 338 5028 759 1558 7182 15466 1499 110908 669
- 18. Asbestos removal progree 264 56 et 11 332 /11. 7 O '
Document S03 25 002 ) 1 Page 41 of 91 i ( TABLE 4.3 (Continued) COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclear
- Generating Station Unit 1 Activity Decen Remove Peck a fp e m Total Cu id Scrap N hre n tes
; Olep net of Plant Systere 4
19.1 Aunttlery F n dweter 52 52 65 1311 19.2 teactor Cootent & Pressucitei Control 19 14 3 230 266 57 506 1 19.3 tefety Injection & Poet incident Cooting 404 46 8 645 1114 162 10155 6 19.4 contairannt sprey & extreutetton 152 18 3 288 460 71 3841 3 19.5 Letooim & tesiduet neet tenovel 109 17 4 275 405 68 2748 2 19.6 vol me Controt & Charging 195 245 15 3 245 703 60 10816 14 , 19.7 toric Acid 5 5 5 134 19.8 Reactor Cycle Seeplity 9 4 <1 63 77 16 246 <1
- 19.9 Recaseste Llwid Collection 186 197 20 4 330 738 82 9202 14
. 19.10 tech este Cryo 9enic Weste Ces Treatment 211 14 3 225 453 56 5186 2 19.11 Conserwete 137 137 210 3534 19.12 Feedmeter 65 65 104 1692 19.13 tot, 2nd, 3rd Pt. Feedueter Meetera 74 74 178 1904 i 19.14 main, Aun & tatraction Steen 113 113 110 2985 19.15 Low Pressure furnine 13 13 47 333 i 19.16 High Pressure furtins 69 69 384 1760 i 19.17 teessete Limid Processing 6Il 727 33 8 605 2006 149 33770 45 19.1C Condenser Air tem > vel 73 73 66 1885
, v 19.19 Conder4ete Seepting 6 6 7 147 19.20 f eensater Sempting 22 22 20 561 19,21 secondary cheelcel Feed 6 6 4 152 19.22 7 tea's tvaporators 86 Su 237 2222 19.23 Spent ' wet Pit cooling 56 15 2 193 267 48 1443 <1 19.24 Companant Cooting Water 90 90 158 2339 19.25 furcine cooling Water 33 33 104 841 19.26 Circulating hater 84 84 134 2183 19.27 Circ Water Nyqfreulic Stop Cates 8 8 27 209 19.28 sett Water Cooling 37 37 58 966 19.29 Turcine semple Cooting 3 3 4 90 19.30 Primary Make-up Water 27 27 23 690 ( 19.31 Service & Dennetic Water 156 154 79 4062 [ 19.32 Cseeoue ultrogen 19 19 9 493 l 19.33 Cenerator Ces 11 11 6 273 ! 19.34 instrument & Service Air 107 107 a 2769 19.35 Liquid ultrogen 6 6 23 157 19.76 Fire Protection Weter 87 87 51 2255 j 19.37 Fire Protection & Sprey 4 4 3 95 19,38 Centatteent ventitetton 387 42 9 68es 1125 170 7778 2 19.39 Sphere inclosure v ntilation 1 1 2 35 19.40 MiseeiLenseue ventitation 240 240 291 4101 19.41 teessete Drain <1 1 <1 <1 5 6 1 37 <1 ! 19.42 Secausery Stetton suspe & Dreine 151 ift 110 3953 p 19.43 Diesel #1 F0, Lo, CW, SA, CAI, l&C f.,5 65 415 1671 {J 19.44 Olesel 82 70, LO, CW, SA, cal, !&C 19.45 turnine Lime & Controt oft 65 65 414 1668 51 51 86 1320 L l i
Document S03 25 002 Page 42 or 91 q NJ TABLE 4.3 (Continued) COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onot.e Nuclear Generating Station Unit 1 l Activity Decen Remove Peck ship Sury Total Cu Yd Scrap u-hrs M t u Dieposal of Plant Systmee (Continued) 19.46 Generator Seel Oil 8 8 10 212 19.47 Sphere Test <1 <1 <1 10 19.48 mechanical Containment Penetrations 10 *0 10 266 19.49 Electrical (centaminated) &&3 100 21 1768 2332 437 11774 3 19.50 Cloctrical (cteen) 519 519 1868 13371 19.51 Weste Water 7 7 4 192 19.52 Sanitary Sewer 14 14 8 376 19.53 Storm Sewe & Aree Drainese 86 86 93 2237 19.54 5tectrical (oecontaminated) 29 83 112 10' 2852
- 19. Totato 1043 5654 334 70 5571 12676 1375 5572 147859 93 Decentaminstf an of 5Ite sui 1dinge 20.1 Containment 743 317 91 22 1930 3136 476 23475 16 20.2 Fuel Sullding 305 278 17 4 355 960 88 141Lt 6 20.3 teactor Auniliary 82 <1 3 <1 71 157 18 '706 1 20.4 teeseste (Phase 1) 29 1 <1 25 55 6 598 <1 20.5 tedweets Building (Phase It) 33 1 <1 29 $4 7 693 <1
- 20. YotaLa 1192 595 118 27 2410 4342 595 40603 25
- 21. License ternim tion survey 30?
- 22. Terminate posseeston-only License a s etetat Perled 4 Activiry Caeta 2573 1Z351 1253 1 6 9 15555 40851 'l563 5572 326750 795 Perled 4 undf atributed Cests
- 1. Decon e@lpment 163 163
- 2. Pocon steplies 164 168
- 3. Staf f relocation expenses 377
- 4. Process Licpaid meste 545 201 190 404 1343 100 845 <1
- 5. Insurerce 2434
- 6. Pecperty tanee ;01 7 Health phyelga engplies 1164 '1164
- 8. Weevy egalpeant rental 2004 2804
- 9. See!L tce( allomence 118 118
- 10. Pipe cutting agalpment 507 507
- 11. Olsposal of contaminated sol W weste 204 47 41(,0 4.*2 1031 7544 49
*2.
. Plar.t energy taacKet w94 Setetal tmdistributed Cests Period 4 876 4593 404 Z38 45#t 15544 1131 E89 19 00C Staff Cost 1C40 utility Staff Cost 14283
$4 total Staff Costs for Pericxl 4 30944 TOTAL PERICD 4 CDff 3449 16945 1657 1896 20123 87379 4694 5572 335169 814 l
l l l -
Document S03 25 002 Page 43 of 91 TABLE 4.3 (Continued) COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclear Generating Station Unit 1 Activ{ty Decen Remove Pack Ship Sury fotal Cu Td Scrap M*hre Mates PG IOD 5 tamove1 of mejor Equipment l 23. mein Turbine / Generator 50 50 1180 1243 24 main Carmensers 154 156 818 3603 Demolition of sensinirg site sulldfrge 1J.1 Containment 6929 6929 2799 140601 25.2 Turbine Aree 3250 3250 3310 70151 25.3 Fuel tuiLding 1013 1013 292 21225
- 25.4 Centrot/Aasiniatratton 489 489 165 8648 25.5 ventilation twipment Room 11 11 5 227 25.6 eeactor AumiLiery 1548 1548 87 31776 25.7 PW Well & Intate/ Discharge Piping 9593 9"73 480 74384 25.8 Dieset Ger4retor 1161 1161 14 22075 25.9 Mainter/mco Building 44 44 25 712 25.10 to w te (Pnu e I) 31 31 12 502 25.11 sampt(na Statton 41 41 <1 801 g 25.12 Ram mste Building (Phase II) 50 50 24
' 785 25.13 service Water Reserwir 32 52 507 25.14 Misc. site Drta 889 849 493 15687 25.15 Dedicated shutaan system 104 104 2108 6
25.16 Neelth physics 5$ $3 28 834
- 25. Totals 25239 25239 7752 289045 site Cloneaut Activities
- 26. Remove t able 163 1A3 2454
- 27. Grace & Lanescace site 131 531 -275u
- 28. finst report to nac 93 setetat Period 5 activity Caeta 26138 2d232 9750 399294 Perfod 5 undistributed Costa
- 1. Insurance 161
- 2. Property tues 377
- 3. Neevy owipment rental 1270 1270
- 4. sealL tcol aLtousnee 187 187
- 5. Plant energy budeet 127 setatat Perled 5 urullstributed costs 1457 2123 4
DOC staff Cost 3020 utility staff Cost 3599 s e total Staff Costs for Period 5 6619
, v otai. Pu re 5 Cos7 27s95 34974 9750 3,9294
Document S03 25 002 i 4 Page 44 of 91 i
- O TABLE 4.3 (Continued)
COST ESTIMATE FOR MOTHBALLING/ DELAYED DISMANTLING: San Onofre Nuclear , Generating Station Unit 1 Activity W temove Pack Ship tury fotal Cu Yd Scrap Nahre M Ram TCTAL Cosi DELATED OlsMANTLIWG 3449 45055 1694 1896 20262 128753 4728 15122 734715 815 r TOTAL COST MLAftp DisMNrTLIM WiTN 251 CouT!aEOCT: 3160,940,900 i TOTAL MLATED risnerTLluG 4ADuasTE vousEE suRIED: 4,728 CU TDS i TOTE. MLAftD DISMANTLluG SCRAP E IGNT: 15,322.3 Tous TOTAL DELATO DISMMITLibG CRAFT LAa0R REQUltEMMTS: 734,714.9 NAN uQ2$ TOTAL DELATM DimMITL! leg PERSOMMEL BAOIATION Exmomat: 814.7 MAm REM DLLATED 0434A8T. ORAFT LA80R CDET WITN CauTINGD CT: 142,998,?50 J O TOTAL V1EMECT Coff 5179 455:!9 1845 1990 21967(160130) 5147 15322 768007 909 TOTAL CORT
- Mothbell with 9.141666 m dormancy & delayed diamenttirg: $211,412,830 TOTAL PROJECT RADWASTE WLissE tuit!D: 5,147 QJ 70s TOTAL PetWECT SCRAP WIGarT: 15,322.3 Tous TOTAL PEQJECT CRAFT LAact REeuttBEENTE: 764,806.6 IIAN ututs TOTAL Pe0 JECT PGstanEL RAelATitEl EXPORRE: 909.2 MAN-R98 TOTAL CRAFT LAa0R COST WITE 251 CoffluGDCT: $44,542,000 uoTE: O This cast includme 360,770,230 for utility & DOC staff periods 15 cente arus $31,350,190 for engineerirg and preperstlens, prsporty temas, insurance, plant wargy tasiset, and staff retoration espannes.
O
I Document 503 25 002 Page 45 of 91 7;LBLE 4.4 COST ESTIMATE FOR PROMFT REMGVAL/ DISMANTLING: San Onofre Nuclear Genera-ting Station Unit 2 (THOUSANDS OF 1990 DOLLARS) , Activity Decan Betape Pack Ship Bury Total Cu Td Scrap N hre N ten a PEAlm 1 1 Reacrve fuel & source anterial rua
- 2. Decon plant & process weste a
- 3. Review plant ch9e & ssecs. 275 4 Perfore detailed red survey e
- 5. Estimate trr proemt inventory 70
- 6. Summit for license amancament 96
- 7. End proast oescriotion 60
- 8. Detailed tv promet loventory 86
- 9. Define enjor wort ge w ance 453
- 10. Perfore safety analysis 191
- 11. $@ mit diaanntLing ptan 31
- 12. Receive License amencement a
- 13. Receive dissrentting croer a s etotst Period 1 Activity Casta 1263 Period 1 urutistritasted costs
- 1. Decon emissent 54 54
- 2. Doc e s e tles 114 114
- 3. OCC staff relocation expensee 377
- 4. Process Liwid weste 70 38 38 72 217 16 185 <1
- 5. Insurance 1328
- 6. Property taxes 218
- 7. Meetth pnysics supplies 788 788
- 8. Neevy emipment rental 15e 158
?. Cisposes of contaminated solid weste 174 40 3548 3762 876 6433 16
- 10. P!arit ener1r/ taasset 599 I
netotal Period 1 undistritasted Costs 239 947 212 75 3619 7615 892 6618 16
- DOC Staff Cost 4177 utility $tsff Cost 2315 z $ 2 total staff Costs for Period 1 6992-TUTAL Peals 1 alsT 239 947 212 75 3619 15571 892 6618 16 MOTES
- =rvan indicates that fust handling, perdwing, sh@ltg, and disposet are charted to
, ptant cooretiens, not decommiasioning
- *e Indicates that costs are included in the utility staff casts.
- All costs are roundedt columns may not total dae to roundof f error
( a
Document S03-25 002 Page 46 of 91 O TABLE 4.4 (Continued) h COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-ting Station Unit 2 ! Activity Decen temove Peck ship hry Total Cu Yd scrap N hrs M tem 1 PCaloo 2 j Activity Specificatione 14.1 Plant & temporary facilities 295 14.2 Plant systeme 249 14.3 teactor internels 425 14.4 Reactor vessel 389 14.5 Ilotocical shield 30 14.6 steam generatore 187 ( 14.7 Reinforced cargrete 96 14.8 Turtline & cindenser 48 14.9 Plant structures & buildings 18I 14.10 Weste amnegement 275 14.11 FactLity & site clooecut 54 14 Total 2234 Pteming & Site Preparations
- 15. Precere disanntling sequence %
s 16. Plant prep. & temp. svces 1283
~
- 17. Design water cteen w systee 84
- 18. Riggins/CCEs/ tooling /etc. 1086 19 Procure cooks /tiners & cor.teiners 74 Dettiled Work Procee res 20.1 Plent syntene 283 20.2 Vesset he*1 150 20.3 teactor inteinets 150 20.4 eoneining buttdings 81 20.5 Cao cooline eseammty 60 20.6 Ca0 housings & ICI tubes 60 20.7 incore instrumentation 60 20.8 eeactor vesse1 217 20.9 Facility closeeut 72 20.10 Miseite shielde 27 20.11 Stological shletd 72 20.12 steen generators 275 20.13 teinforced concrete 60 20.14 Turt>lne & condeneers 187 20.15 Auxillery building 163 20.16 taector building 163
- 20. Total 2080 l
Deron asss/ tack temovet
- 21. Decon primary Lvan 366 366 800 5
- 22. Remove spent fust rocks 1352 69 84 17 2720 4243 671 34226 208
Document S03 25 002 Page 47 of 91 O TABLE 4.4 (Continued) COST ESTIETE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-ting Station Unit 2 Activity O x on temerve Peck Ship Suty Total Cu Yd scrap M-hrs N ten Nucteer Steen sespty System Removal 23.1 mesator Cootent Piping 187 544 34 11 559 1334 134 17957 106 23.2 Pressuriner cuench fant 6 35 1 <1 30 72 7 1011 7 23.3 tenctor Coolant Pumps & motors 160 45 40 69 2P90 3205 696 5337 34 23.4 Pressurfter 26 43 5 18 424 516 100 1694 0 23.5 stem Ceneratore 176 2070 79 850 7704 1087C 1844 52889 949 23.6 Caome/ICle/ service structure temovat 117 61 27 10 371 586 92 4300 31 23.7 seactor vesset internets 268 1786 749 817 5107 8726 332 22960 147 23.8 teactor vessel 144 1414 291 214 1474 3537 324 22980 147
- 23. Totale 1084 5990 1226 1989 18559 28855 3533 129148 1432 Oleposal of Plant Systeme 24.1 teactor Cootent Puse 1201 139 59 14 970 1183 240 3750 48 24.2 Component tooling Water 1203 376 376 548 9862 24.3 safety Injection 1204 1255 188 37 2820 4301 696 31862 91 24.4 Containment sorey 1206 80 80 107 2089 24.5 teactor cootent CVCs 1208 229 321 35 8 577 1169 142 13321 79 l 24.6 uucteer Plant secoling 1212 49 11 2 152 245 45 1317 3 l
, 24.7 teactor Cootent CVCS 1218 42 51 5 <1 76 175 19 22*5 15 24.8 Fuel Pool cooling 1219 943 116 24 1820 2903 449 23906 72 24.9 Main Steen 1301 956 956 935 25131 24.10 Feedwater & Concensate 1305 863 863 1240 22485 24.11 Aux Fee $seter Nydraulic valveg
- 1306 3 3 5 89 l 24.12 Turtpine Generator Lee 011 1307 35 35 l
145 898 24.13 Auxiliary Sollef *1312 3 3 3 69 24.14 Condenser Air Removal 1313 81 81 121 2130 24.15 main Consenser vents & Drains 1314 12 12 to 301 24.16 Generator Seal Oil 1316 48 44 30 1240 24.17 8Loudoun Processing 1318 80 80 55 2075 24.18 Full Flow condensetr Polisher 1319 97 97 135 2521 l 24.19 Circulating Water 1601 134 134 194 ' 3495 24.20 Turbine Plant Cooling Water
- 1404 315 315 358 8240 24.21 main Generator Cooling 1412 42 42 72 1079 24.22 uucteer service Water 1415 95 95 97 2508 24.23 Miscellanoeum venting 1500 223 223 187 5677 24.24 Containment MVAC 1501 471 77 17 1373 1937 339 10000 21 24.25 Auxiliary sultding MvAC 1509 363 31 6 501 901 124 7176 16 24.26 Miscellaneous ventilating 1510 212 212 168 5176 l 24.27 Aux. Slag. Normal Chilled Water 1513 106 106 64 2747 I
24.28 Fire Protection 2301 86 86 65 2221 24.29 Caseous Fire Protection 2302 12 12 21 305 24.30 Turtaine Plant Sempting 24i5 26 26 28 664 24.31 Instrsment air Oletration 2417 50 50 24 1322 24.32 Auxiliary ces (uitrogen Headers) 2418 40 40 12 1035 (/ 24.33 Susp & Dralne 2419 7 7 6 192 l 24.34 Olesel Generator 2420 55 55 538 1391 l
Document S03 25-002 l Page 48 of 91 A U TABLE 4.4 (Continued) COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-ting Station . Unit 2 Activity Decen Remove Peck Ship tury Total Cu Yd Scrap M-hre N-ten Oleposet of Plant systeme (Continued) 24.35 Auxillery Salter 2421 124 126 114 3280 2". 36 Turtdre Plant cheelcel 4cklition 2422 18 18 5 467 24.37 Ccepts
- ir -
2423 104 104 37 2722 24.38 Suos erus Craine 2426 29 6 1 90 125 22 716 2 24.39 Sewer outelde Structures 1 1 *1 26 24.40 Pluneing & Poteele Water 175 175 89 4548 i 24.41 Leak Detection 97 97 33 250! 24.42 Glend Steam 96 98 83 2559 24.43 CorAent techseste - 1901 171 225 10 2 163 571 40 , 9924 59 24.44 Electrical (cleen) 1374 1374 465' 35478 24.45 Electricet (contaminated) 1125 188 76 6811 8299 1682 29891 39 24.46 Etee.trical (decontaminated) 125 364 490 469 12473 24 Totete 567 11367 825 188 15383 28329 . 3796 10652 303377 444 Decentamination of Site Buildings 25.1 containannt 1221 448 110 25 2444 4049 554 37237 121 25.2 Fuet uendline 644 477 35 8 713 1876 176 26755 53 , (']/ 25.3 Penetration Area
- 25. Totale 242 <1 to 2 211 466 52 5059 3 2107 925 155 36 3164 6391 782 69050 177
- 26. License terminetton survey 300
- 27. Terminate License e sietotal Period 2 Activity Costs 5476 18359 2290 2230 39829 754'A 8784 10652 536601 2270 Period 2 L*1 distributed Costs
- 1. Decon owipment 163 163
- 2. Decon supplies 264 264
- 3. Doc etoff relocation expensee 3 77 4 Procese Ll wid weste 675 664 571 1603 3516 366 1956 3
- 5. Insurance 4314
- 6. Property tease 506
- 7. Health phyelee e # ies 1829 1829
- 8. Neevy swipment rentet 2317 2317
- 9. Smelt tool ettoasence 191 191
- 10. Pipe cutting owipment 507 507
- 11. Oscon ris 659 659
- 12. Oleposet of contaminated solid weste 521 122 10643 11286 2644 19253 48
- 13. Ptent ener9y buneet 1M6 54 total taidletributed Coets Perm 2 1761 4845 1189 693 12245 27756 3010 21254 52 Occ 5taff Coet 14050 j utility Staff Cost 12045
$4 total Staff Coste for Period 2 26095 TOTAL PEttta 2 CatT T237 23203 3480 2923 52074 129319 11794 10652 557855 2322
l Document 503 25 002 l Page 49 of 91 TABLE 4.4 (Continued) COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-
; ting Station Unit 2 Activity Decen genove Pack ship tury Total Cu Yd Scrap N hre n tem PERI (E 3 1
teewel of mejor Egipment
- 28. Main furnine/ Generator 116 116 2676 2894
- 29. Main Condensers 359 359 1881 8746 Demolition of seminim $lte tuildirgs 30.1 Conteineent 15079 15079 1579 303746 30.2 main fransformer Aree 139 139 <1 1666 30.3 furbine 19897 19897 5410 413129 30.4 Fult Flou condensate Polishing Domin. 434 434 116 7039 30.5 Fuel Mandling 3971 3971 781 77139 30.6 Persomel Accets & Electriest GelLery 611 $11 44 11448 30.7 safety Ewipment 3451 3851 450 76707
, 30.8 Penetrr. ion Area 756 756 <1 14942 30.9 Intate structure 12299 12299 17 118370 30.10 Tana Enclosure 628 628 56 7025 Q 30.11 Oleset Generator 584 864 124 16767 30.12 L 2e Oil Storees Aree 61 61 <1 958 30.13 Reserw Aum. Transformer Area 81 81 <1 1044 30, foteLs $8691 58691 8579 1049983 i Site Ctaneaut Activities
- 31. tesow Runnte 780 780 11770
- 32. Grade & tanascape site 531 531 2750
- 33. Finet report to mRC 93 Setetal Period 3 Activity Costs 60476 60579 13137 1076143 Period 3 Wudietriteated Costs
- 1. Insurance 256
- 2. Property tones 631 i 3. Heavy s eisment rental 2093 2093 1
4 Small tool allouence 419' 419
- 5. Plant energy budget 382 subt tal Period 3 urudistributed casta 2512 3751-i DOC Staff Cost 5051
!' utility Staff Cost 6020 Subtotal staff Costs for Period 3 11071 TOTAL PERIOD 3 CotT 62909 75422 13137 1076143 l TOTAL COST TO CECDeciss!Ou 7476 87139 3691 3001 55694(220612)12687 23789 1640616 2338 l
Document S03 25 002 Page 50 of 91 O TABLE 4.4 (Continued) COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-ting Station Unit 2 Activity Decen temove Pact ship Sury Total Cu Td Scrap M hrs N tas TOTAL COET TU DECaettsslau VITu 25 % CONTINGDcT: s275,764,900 TOTAL tAcarit VOLLsE suRIED: 12,647 CU TDS TOTAL SCRAP IETAL RBEMD: 23,7M.7 Tous TOTAL CRAFT LAsta rem; IRS O TS: 1,640,616.0 IIMI is0LAS TOTAL P G 501sIEL RADIATION EXPOEME: 2,DS.2 MAN REM TOTAL CRAFT LAstE cost WITu 25 % CONTIIIGE11CT: S 86,0E5,790 l l O 20TE: O This cost includes $44,158,090 for Utility & Doc staff periods 1 3 costs and S19,454,340 for ergineering and prsperssions, property tanes, insurance, plant enerw budget, and staff relocation expenses. l l O
k 4 Document S03 25 002 Page 51 of 91
\
TABLE 4.5 COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofn Nuclear Genera-ting Station Unit 3 (THOUSAb DS OF 1990 DOLLARS) Activity Decen temuse Peck ship sury Total Cu 1d scrap n hre n-tem PERICD 1
- 1. temove fuel & source estoriet n/a j 2. Decon plant & process maste e
- 3. teview plant asse & specs. 275
- 4. Perfors detailed red survey e
- 5. Estimate tv product inventory 70 4 6. 52 snit fue .w.7.e amortteent 96
- 7. End promet description 60
- 8. Detailed tv product inventory 88 j 9. Define major mort sequence 453
. 10. Perform safety enetysis 191
- 11. Se mit disamnttIng ptan 31
- 12. Eoceive license amendment a
- 13. Receive dieaantling order a
! S htotal Period 1 Activity costs 1263 Period 1 undistributed Casta
- 1. Decon equipment 54 54
- 2. Decon s e ttes 114 114
( 3. Doc staff retocation exponess 377 4 Procese Liwid weste 70 38 38 72 217 16 185 <1 , 5. Insurance 1126
- 6. Property taxes 218
- 7. Health physics amplies 798 738 i 8. Reevy owipment rental 154 158
! 9. Otsposal of contaminated solid i.este 174 40 3544 3762 874 6433 16
- 10. Plant energy budget 1216 l
, Setotal Period 1 IMdistributed Costs 239 947 212 78 3619 3E50 892 6618 16 I l DOC Staff Cast 4177 { utility Staff Cost 2863
$ 2 total Staff Costs for Period 1 7040 TOTAL PERICD 1 CDET 239 947 212 75 3619 16334 892 6618 16 m0TES: - We* Indicates that fuel handtire, packagirg, shipire, and disposet are charged to plant aparations, not decommiselonirg l as a irudicates that costs are included in the utility staff costs.
l - Att costs are raisided; columns any not total das to rossisoff error T J l l l i l
Document S03 25 002 Page 52 of 91 O TABLE 4.5 (Contintiad) COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-ting Station Unit 3 Activity Decen seen Peck ship tury Total Cu Yd scrap n-hrs M tes Pittoo 2 Activity specifications 14.1 Plant & temporary facilities 295 14.2 Plant systems 249 14.3 teactor internels 425 14.4 86ector vessel 389 14.5 Biologiceishield 30 k 14.S St vem gereretors 187 14.7 Reinforced concrete 96 14.8 Turbine & condenser 48 14.9 Plant structures & buildings 187 14.10 Weste menegament 275 14.11 Facility & site closecut 54
- 14. Total 2234 Ptemity & Site Preperstlano
- 15. Propere diesentting some 144
- 16. Plant prep. & teep, svces 1283 y 17. Design water cteen-up system 64
- 18. Rigging /CCEs/ tooling /etc.
1086 19 Procure cooks /tIners & containers 74 Detailed Wert Proca&res 20,1 Ptent aysteen 283 20.2 vesset heed 150 22.3 Reactor internets 150 20.4 Remaining buildinge 81 20.5 Cao cootIng essenety 60 20.6 CR0 housings & ICI ttaes 60 20.7 incore instrsmentetton 60 20.8 Reactor vessel 217 20.9 Facitity closecut 72 20.10 Misatte shields 27 20.11 Biototical shield 72 20.12 Steen generators 275 20.13 kelnforced concrete 60 20.14 Tureine & condoneers 187 20.15 Ausillery building 163 20.16 Reector building 163
- 20. Total 2060 Decen 8888/teck Remowet
- 21. Decon primary Ioop W 22.
W 600 8 Remove scent fuel rocks 1352 69 84 17 2720 4243 671 34226 208
Document S03 25 002 Page 53 of 91
/~'N V
TABLE 4.5 (Continued) COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-ting Station - Unit 3 Activity Decen temove Pack ship tury Total CU Yd $ crap M hrs M tem musteer steen s e ly System genovel 23.1 seector Coolant Piping 117 369 19 6 315 826 78 11904 70 23.2 Pressurlier Quenen Tank 4 35 1 <1 30 72 7 1011 7 23.3 teactor coolant Ptasas & Motors 160 45 40 69 2890 3205 696 5337 34 23.4 Pree w iser 26 43 5 18 424 516 100 1694 9 23.5 steen Generatore 176 2070 79 850 7704 10878 1844 52889 949 23.6 Caome/IC1s/ service structure Removat 117 61 27 to 3 71 586 92 4300 31 23.7 teactor vessel internets 228 1588 633 684 4521 7655 286 20700 133 23.8 teactor vesset 144 1413 291 214 1649 3531 324 20700 133
- 23. fotels 974 5624 1095 1851 17724 27268 3427 118535 1347 Olepenal of Plant Syst C 24.1 Reactor Cootent Pump 1201 101 42 10 682 834 168 2713 36 24.2 Component Cooling water 1203 440 440 604 11534 24.3 Safety Injection
- 1204 1249 186 37 2T78 4249 686 31700 90 24.4 Containment sprey 1206 88 88 113 2296 24.5 teactor Cootent CVCs 1208 123 H3 34 7 561 938 138 7958 47 24.6 Nucteer Plant Sempting 1212 508 25 6 406 945 100 12312 35 tO 24.7 totstor Cootent CYCs 1218 24.8 Cootent & Beric Acid Recycle 1218 42 504 51 5 <1 76 1 75 634 88 17 1339 2582 331 19 2285 15 27665 178 24.9 fuel Poot cooling 1219 912 112 23 1757 2004 434 23107 70
?4.10 Main steen 1301 961 ?tt 934 25252 24.11 Feeenster & Condensate 1305 841 841 1224 21898 24.12 Aux Fooeseter N W aulic Velvee
- 1306 3 3 5 89 24.13 rurtine Generator Like Oil 1307 250 250 293 6474 24.14 Auxillery Boiler '4..: 19 19 28 496 24.15 Conserver Air Remotfel 103 74 74 114 1944 24.16 Mein condenser vents & Dreine 1314 12 12 10 304 24.17 Generator seal Oil 1316 48 48 30 1240 24.18 slowoomsi Processing 1318 99 99 81 2566 24.19 Full Flow condaneate Polisher 1319 1949 1949 1750 49112 24.20 circulatinP Water 1601 190 190 247 4932 24 # Turbine Plant Cooling Water ?404 346 344 370 9059 l 24.22 Main Generator cooling 1412 42 42 72 1089 l
24.23 Nuclear service Water 1415 242 242 158 6301 24.24 Service Water 270 270 160 7005 24,25 Detineralization 1417 93 93 63 2404 l 24.26 Mekey Domin Meutrelltetton 1415 70 70 52 1818 24.27 Miscotteneous venting 1500 228 228 193 5800 24.28 Containment MVAC
- 1501 471 77 17 1373 1937 339 10000 21 i 24.29 Austliery Sulldine NvAC - 1509 444 57 12 934 144 7 231 9287 20 24.30 Miscellaneous ventilatin9 1510 214 214 171 5427 24.31 A8 moraal chilled Water 1513 355 355 311 9205 24.32 Miseetieneous Ll @ id waste 1901 159 280 44 to 725 1219 179 10544 68
\ 24.33 Cootent aseneste 1901 1531 2130 153 34 2625 6473 648 90980 551 24.34 weste Gee 1902 328 15 3 243 589 60 8044 13 i
Document S03 25 002 Page 54 of 91 TABLE 4.5 (Continued) COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera-ting Station Unit 3 Activity Decen Remove Pack Ship tury Total Cu Td ser v M-hrs M tm Disposal of Plant syntame (Conttrued) ' 24.35 toeneste solidification . 1903 52 6 1 104 164 26 1300 4 ! 24.36 fire Protection 2301 183 183 233 4687 24.37 Caseous Fire Protectit.n 2302 7 7 6 188 , 24.38 Turbine Plant sampling 2415 24 24 28 619 24.39 Instr 1 ment Air Olstribution 2417 102 102 51 2655 24.40 Auxillary Gas (ultro9en Needers) 2418 90 90 33 2333 24.41 Swpe & Draine 2419 11 11 8 280 , 24.42 Diesel Generator 2420 40 40 528 1005 24.43 Auxillery Soller
- 2421 153 153 121 3948 24.44 Turbine Plant Chemical Addition
- 2422 34 34 892 24.45 Compressed Air 2423 166 166 65 4324 24.44 Sumpe & Dreiro 2426 47 10 2 158 217 39 1192 3 24.47 Yere Dreinese 205 205 243 5417 24.48 tower outelee Structuree 49 49 32 1269 24.49 Potable Water (katside 13 13 8 340 24.50 Plumbing & Pote4Le water 884 884 448 22906 24.51 LesA Detection 109 109 42 2828 24.52 Gland steam 97 97 81 2528 24.53 Containment Pur9e 13 2 <1 37 53 9 344 <1 24.54 Diesel Generator Air 44 44 33 1142 24.55 Electrical (cleen) 3033 3033 7447 71339 24.56 Electrical (contaminated) 2392 524 123 10798 13437 2666 63454 32 24.57 Electrical (decontaminated) 809 809 1144 22986
- 24. Totals 2360 22793 1379 303 24597 51432 6073 17542 637818 1234 Dec.antaminetton of Site Guildirge 25.1 Containannt 1221 448 110 25 2244 4049 554 37237 121
; 25.2 Auxiliary $29 23 5 441 1018 114
<1 11057 73 25.3 fuel Nandling b44 4TT 35 8 713 1876 176 26755 53 25.4 Penetration Aree 242 <1 10 2 211 466 52 5059 3
- 25. Totals 2634 926 178 41 3629 7410 896 80107 251
- 26. License terminetton surwy 300
- 27. Terminate Licarme a Sietotal Period 2 Activity Casts 760s 29412 2736 2212 48669 98002 11067 1?542 871485 3064 ,
4 0
Document S03 25 00: Page 55 of 91 O TABLE 4.5 (Ccntinued) COST ESTIMATE FOR PROMM REMOVAL / DISMANTLING: San Onofre Nuclear Gen:n. ting Station . Unit 3 Activity U Decen temsee Pact Ship Bury Total Cu id Scrap N nre M tes Perled 2 thdistritwted Caste 1 Decon owlgment 163 163 7 Decon o w lles 310 310
- 3. DOC atoff relocation empensee 177 4 Procese ll%Id weste 940 891 764 2115 4714 484 2702 5
- 5. Insurance e195
- 6. Proserty tease 195
- 7. Neetth phyelce s w Lies 2144 2144
- 8. Noen owlpeant rentet 2720 2720 4
- 9. teoll tool ettouence 305 305
- 10. Pipe cuttitg owipment 507 507
- 11. Decon ri8 659 659
- 12. Oleposet of cont altated solid weste 521 121 10643 11285 2628 19298 48 IJ. Plant ener9y tuove; 3436 SWetet tmdletributed Caste Ported 2 20T3 5680 1410 spe 12757 31914 3112 22000 53 D00 staff Cost O
164M Utility Staff Cost 14141 Sattetet staff Costs for Period 2 30635 TOTAL PE8tos 2 cnsi 9761 35092 4144 31M 61436164550141M 17542 SF36a5 3121 Pfal0B 3 temowel of Mejer E gipment
- 24. Main furtilne/ Generator 116 116 2676 2894
- 29. mein Ceneensere 359 359 1841 8746 Demolitim of Bassinirg lite duHdings 30.1 Containment 150~<9 150M 1540 303758 30.2 Aunt llery 21905 2190) 2712 437264 30.3 Turt>Ine 19714 19711- 5051 40aa21 30.4 full pleu condenects Polishin8 Desin. 4!.4 434 116 7039 30.5 Fust uendline 3460 3MO %7 74571 30.6 Persemet Accese & Electrical Gallery 629 629 79 11864 30.T sef ety ielpoemt 3755 3755 lie 74499 30.8 Penetration Aree 754 75 4
<1 14942 30.9 Inteke Structure 12299 12299 17 118370 30.10 fers incleeure 634 634 73 7229 30.11 Dieset Generator 867 867 91 16371 30.12 L Ao 08L 8torage Arse 61
, 61 <1 954
*% 13 Reserve Aua. Transformer Area 81 h W.14 main fransformer Area 30.15 asley nousee 139 31 139
<1 el 1044 1666 70 70 <1 1119
! Document 503 25 002 } Page 56 of 91 O TABLE 4.5 (Continued) COST ESTIMATE FOR PROMPT REMOVAL / DISMANTLING: San Onofre Nuclear Genera. ting Station . Unit 3 Activity Desen temove Pact thlp tury fetal Cu Td Scrap N bre N tes ! 6esititlen of temninfrg site tulldines (ContWeC l 30.16 8wIten ferd 698 696 300 12182 l 30.17 Sewege treatment Plant 184 184 3471 j 30.18 fasperery iseL Iose 132 132 90 1959
- 3019 maintenance tulldinet me. I thru 6 142 142 107 2802 30.20 make up we er Domineentiser 25 2 252 10 3847 30.21 Fire Water Pwo station 157 157 2478 30.22 Demireretlaer A.ee 119 179 2821 30.23 muttl* Purpose Neiding 'scility 1219 1219 89 21438 j 30.24 seeueLt 1441 1461 21351 30.25 ieLenemmiea Ione sulLdinos 15 1$ 6 2 75
+ 30.26 Constrm tion office 193 173 137 295 7 30.27 South vehicle Processine Facility 2 2 34 30.28 serth teatrees facility 9 9 164 2 30.2+ Ouereausee 16 16 3 271 1- 30.30 Central Processing FaclLity 25 25 15 34 10.31 security Procesette f acility 12.*- 120 44 1662 30.32 mese stristures 43e1 4341 2642 M313 , 30.33 AWs 3517 J517 84 55378 ,' 30.34 site testeretten 1554 1554 6 7621 4
- 30. Totals 94565 94565 14130 1647174 i
site Claessut Activities 31 temwe tele 1574 1574- 23743
- 32. Green & tendecese ette 531 531 2750
- 33. Finst report to mac 93 Setetet Peeled 3 Activity Caste f7145 77238 18647 1725307 Perled 3 LNistriksted Casta
- 1. Insurance
' MT
- 2. Property tones 819
- 3. weevy s w ipment rentet 2718 2718 1 4. Seett tseL ettemance- 645 M5 l S. Plent energy heapot 1780 t @tetet Perled 3 undletrilmsted Casts 3363 4630 I
Doc Staff Cast 6554 utility Stelt Cast 7817
$ 4 total staff Caste for Period 3 14375 TOTAL Pette 3 COST 100508 118243 18687 1725307
' ~ TOTAL COST TO DECOMMit$10W 10000 136544 4360 3180 65045(295127)15072 362 0 2625411 3137 4 4
- .--.,.-----..,n., , . . . , , . r-, --,. ,, - - , . , w -.,.r - , , - - e , - -
Document S03 25 002 Page $7 of 91 O TABLE 4.5 (Continued) COST ESTlhiATE FOR ' PROhtPT REhtOVAL/ DISH 1ANTLING: San Onofre Nuclear Genera. ting Station . Unit 3 Acttvity IMoen temove Pack thlp tury fotet .h Td Scrap M* hrs n ten TOTAL CDET TO DECDelitslot WITu 251 CoutimmuCf 5344,90F,200 total BAbusTE WouM Iutlins 15,772 Cu TDs TOTAL SCRAP IETAL tepuMB 34,228.8 Tous total caAFT LAson teeulteMEsis: 2,625,411.0 stas.esauts TOTAL PEttolaEL LAetATital EXPomat: 3,137.2 NAs essi TOTAL CRAFT LAant 0051 WITu 15 1 CorfluGEtCT: 3133,M3,400 0 mott O This cent testudee $52,050,544 for utility & Doc staff periode 1 3 costs ord 123,MS,750 for engineerire and preparettene, property taase, .*neurance, plant enerw budget, and statt retosetteri sapenses. O E.
Document 503 25 002 Page $8 of 91 a
- 5. SCHEDULE ESTIMATE The schodule for integrated decommissioning considered in this study follows the sequence pre-with minor chang,es to reflect recent experience and sented la the AIF/NESP-036 revised estimat:5. In adddesi, the schedumidy(Ref.6) ling has been revised to reflect the mo the Sea Onofre Nuclec: Gueratm g Station spent fuel storage facility as an ladependent S 3ent Fuci Storage Installation (ISFSI), dry storage cask design, DOE turnover requirements anc the expected pool inventory at shutdown.
TLO has devised a schedule and work force chart for the San Onofre Nuclear Generating Sta-tion. The assumptions are listed in Section 5.1. Figure 5.1 presents the schedule of key activities. Note that 'he activities hsted in the schec ules do not reflect a one to one cor-respondence with the .ictivities in Table 4.2, but reflect dividing some activities for clarity and combining others for convenience. A legend defining the schedule nomenclature and depic-tions is also included. The schedule was prepared using the " Harvard Project Manager" com-puter software (Ref.13). 5.1 SCHEDULE ESTIMATE ASSUMPTIONS The schedule estimate reflects the results of a precedence network developed for the Im) b San Onofre Nu: lear Generating Station decommissioning activities, i.e., a PERT (Pri grammed Evaluation and Review Technique). The durations used in the )rocedence network reflect the actual manhour estimates from Table 4.2. He schedu e output is then adjusted by stretching certain activities over their slack range; other activities were pushed to the end of their slack xrixi. The following assumptions were made in the development of the schedule for t)e San Onofre Nuclear Generating Station.
- 1. All work except vessel and internals removal actirhics is performed during an 8-hour workday,5 days per week with no overtime. There are eleven paid holidays per year.
- 2. De Fuel buildings for Units 2 and 3 will be isolated and serve as an ISFSI until such time that all spent fuel has been discharged from the spent fuel pool, i.e.,
wiLdn five years from shutdown of Units 2 and 3.
- 3. Vessel and internals removal activities are performed by using separate crews for different activities working on different shifts, with a corresponding backshift charge for the seond shift.
- 4. Multiple crews work parrllel activities to the maximum extent possible consistent adequate access for cutting, removal and laydown space, with optimum and with efficiency,fety the stringent sa measures necessary dun,ng demolit ponents and stnictures.
- 5. For plant systems removal, the systems with the longest removal durations in areas p
v on the critical path are considered to determine the duration of the activity.
J l 1 Document S03 25 002 ! Page 59 or 91 i i )
- O :
l t i i 5.2 PROJECT SCHEDULE -t i The petiod dependent costs presented in Tables 4.3,4.4 and 4.5 are based upon the
! durations developed in the schedule for the DECON and SAFSTOR alternatives, ! respectively Durations are established between several milestones in each project ,
period; these durations are used to establish a critical path for the entire project. In i turn, the critical path duration for each period was used as the basis for determining th
- total costs for these items.
! Project time lines for the DECON and SAFSTOR alternatives are included in this sec. 1
- tion as Figure 5.2. Milestone dates are based on the plant operating life from the date - !
- j. of the construction permit. -
d j i + lO 1 l I i I b t i i-9 i [ i I
- n..,..;--,,,u_ a n.-- , , - - , - - .-...,.s _ . , - . , , _. : ~;.,_,,. .,_-_,;.n.,, . , , . , , , _ . . ,, l
Document S03 25 002 Page 60 of 91 FIGURE 5.1 DECON ACTIVITV SCHEDULE Jan 2005 2007 2009 2011 2013 2015 2017 2019 2021 2023 2025 Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan Start $ PreDecomm Ut t t,ic Ac tP h ase0 ShtetdnDelay3 ShutdnDelay2 start ULPert + Remove Fuel . DesignWtrCin .,, Feet 0ut + Fuel X-fer Dcon NSSS Ut . Rmv RCS Ul . . EngrgWrkDone 9( OconRack:Ut . OconWorkDone + Ocon/SecurSy . Final Survey . Site Ready + t Unit 1 Dorm BeginDormUn e SpentruelDet mamm.mme Unit 2 Delay e Unit 3 Down
+
Unit 2 Down 6 Pertod3Ac tiv RmvSysVICrpB -- Per2 Waste Ut LicAct P2-U t ActvtySpecUn RmvSysU t GrpA BeginPeriod4 4 G
.. -- -- - - - /
Document S03 25 002 Page 61 of 91 O
' FIGURE 5.1 DECON ACTIVITY SCHEDULE i
(continued) ' 2005 2007 2009 2011 2013 2015 2017 2019 2021 2023 2005 Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan Jun Dcon NShS U2 c DetByProd U2 e LicAct PI-U2 m Rad Survy U2 m Pertwaste U2 w RmvHacks U2 . , f Start U2Perl <> i Rmy RCS U2 e RPVrmvprepU n . Rmvl NSSS Ut a ' ActvtySpecV2 . Lic Act P2-U2 , R Per2 Waste U2 , R Rmv5ysV2CrpA , I R RmvSy:U2CrpB , R RmvlStCen Ut - , R AB GrpCsy:Ut ., , R TurBigCrpDUI _ 3 Mye NSSSEqp2 R OthrCrp0 Ut R FaelBdCrpCUt R RmvRacks Ut - , End Pert U2 + R Pertwaste U3 - LicAct PI-U3 DetByProd U3 e Rad Survy U3 e R Fuel 8dDecnUI R RPVrmvprepV2 . RB GrpCSysUl _ , AB Decon Un . . t I s 1 I a I a a i E A
. , _ _ _ _ . . , . . ___ .c_,
Document S03 25 002 Page 62 of 91. FIGURE 5.1 DECON ACTIVITY SCHEDULE (continued)
- lan 200$ 2007 2009 2011 20tJ' 2015 4017 2019 4021 200J 'O.;L Jan Jan Jan __Jan Jbn Jan Jan Jan Jan Jan Jan
. i i 1 , . , . .
Dcon R9 Ut AB CrpDaysl11 ' Rmvl NSSS U2 RWPhas t crCU t RB CrpDSysUI RwPhas2CrCUI FuelBdCrpDUI DenRWPhas2U t Actvty$pecV3 LicAct P2-U3 e R RmvSisV3CrpB 1 Dcon NSSS U3 R RmvSysV3CrpA R Per2 Waste U3 ammmmerm End Pert U3 , Rmy RCS U3 m. DenRWPhas1U t ftwPhastCpDUt RWPhas20pDU t FnlSurvey Ut R TurBigGrpDU2 Mye NSSSEqp3 . R FuelBdorpCU2 R PenAreeDenU2--
- . ~*
R RmvlStCen U2 SftyEqpCpCU2
~ R OthrCrt0 U2 '
R FuetBdDconU2 R Sf tyEqCrpDU2 RB GrpCsysV2
-- 4 -
ContintrDmUt 1 1 5 i a a 1 i R i 8 8
, , .,,,,..-.4.-., ,,_..v...n.-.m,m%.m.y #'-.cm,m.,,, . .-rm,_.~, , . , . ,.,mg -<,x-, .,,.-,...,ym.-.o4..,,pe,m,,.w .,.,m. ..w..,.- , . - , .~I,..-
Document S03 25 002 Page 63 of 91 O k FIGURE 5.1 DECON ACTIVITY SCHEDULE (continued) 2005 2007 2009 2011 2013 2015 2017 2019 2021 2023 .>025 Jan Jan Jan Jan Jan Jan Jan Jan Jan Jn Jan len RB Ullntdmin - Term Lie Ut - , ABintrDminUI - ' RmvNEssstrU1 - FuelintDmlUt - B akfilSiteU t - DC In'OminUt - RmvTurbCenUl ar---- - R mvCondnsrU t - RPVrmvprepU3 e DC ExtDminUt DC BackfilUt - , Deon RB U2 ar--- m TBUltntrdmln . AB Backft Un . Rmvl NSSS U3 - FuelBdCrpDU2 i FHBBackfilUI - TBUlExtrDem - , VenEqDekfIUI i TBUlBackfill - , RB GrpDsysV2 ar- , i FnlSurvey U2 . RmvTurbCenU2 , STEqintrDmU2 _ . CondtntrDmV2 - , Rm"CondnsrU2 . DC IntDminU2 m-- , R PmvNEssStrU2 essar- . O) 4 V PnArtntrDmVE - , FuelintrDmV2 .,
Document 503 25 002 Page 64 of 91 FIGURE 5.1 DECON ACTIVITY SCHEDULE (enntinued) 2005 2007 2009 20ti 2013 20tS 2017 2019 2021 2023 202$ Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan
, , , , , , , , 1 - ,
TkEnclntDmO2 . . R RB U2tntDmin , Bakf61SiteU2 _ , IntktntrDmV2 . m Term Lie U2 - - DO ExtDminU2 - - , CondExtrDrnU2 - -m p TkEncBkfDmV2 ar---*--9 CondBackflU2 . . DC BackfilU2 . . R RB ExtrDmUt . R FuelExtrDmU2 _ , TBU2 ntrdmin . , R OthrCrp0 U3 m R TurBigCrpDU3 m [ R PenAresDenU3 arm R RmvRacks 03 ., R FuelBdarpCU3 .
- R SaEqcpCsysV3 arm RmvlStCen U3 .
FuetBdDconU3 en SaEqcpDsysO3 m RB CrpCsysu3 . FuelBackflU2 , , RB BackftlUt , , furbExtrDmV2
- TurbBakfilV2 - ,
Deon RB U3 - . FuelBdCrpDU3 en ' contrExtdmUt . , Con:BektilUt _ m l _ - - _ - _ _ - -J
Document S03 25 002 Page 65 of 91 O O FIGURE 5.1 DECON ACTIVITY SCIIEDULE (ContintteM 2005 2007 2009 2011 2013 2015 2017 Cl9 0001 2023 2025
,an Jan Jan Jan .en Jan _.J a n Jan Jan Jan Jan Jan
[ ] T Landscape Ut - DUMMY 2 - RB GrpDsysV3 m AuxGrpCsysV3 m
$fEqExtrDmV2 -
IntkBkflDmV2 - Dcon Aux U3 m AuxGrpDsyst!3 m DconDone U3 $ SfEqBakfilV2 - FnlSurvey U3 m End Per2 U3 + f~) f RmvTurbGenU3 w, RmvNEssStrV3 _ , RB U31ntdmin amer 9 TkEcIntrDmV3 er, RmvCondnsrV3 er, DG intDminU3 er , CondlntrDmU3 ar, latkintrDmV3 memes FuellntrDmV3 as Term Lic V3 $ SfEqintrDmV3 m, Bakf 61SiteU3 i ABlntrDminU3 - RB ExtDminU2 - DG ExtDminU3 ar , CondExtrDmV3 w, Tk Ec BackflU3 mr , h CondBakfilV3 m, DG BackfilV3 mr , i l l l
Document S03 25 002 Pagt 66 of 91
\
FIGURE 5.1 DECON ACITVITY SCHEDULE (enntinued) 2005 2007 2009 2011 2013 2015 2017 2019 2021 2023 2025 Jyn Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan Jan TwetExtrDmU3 m TBU3intrdmin arm FuelBackflU3 e RDBackfillC2 s . DconDone 'l2 4 > TBExtrDmV3 . TurbBakfilV3 m End Per2 U2 4 > PnArBakfilU2 - , Landoct.pe U2
. i IntkBakfilU3 .
SIEqExtrDmV3 DUMMYl a SfEqBakfilV3 RB Ex.DminU3 DconDone Ut < > End Per2 Ul 4 > RBBackfillV3
.e AuxExtrDmV3 m
AuxBakfilV3 RmvEs:StrU3 Landscape U3 End
+
End Per3 U2 4 > End Pe.3 Ut 4 > f"% v) l i i i 3 a 1 i i 1 $
_ _ . . _ . . _ . _ _ _ _ . - . _ _ _ _ _ . _ . . . _ . . . - - _ - _ _ .___ _ . _ . . . _ ~_ . _ __ __ _ _ ... __ _ _ . ._. -
, Document 503 25 002 i
Page 67 of 91 1 1 i FIGURE 5.1 DECON ACTIVITY SCHEDULE ! (continued) 1 J I 1
.i 4
j 1 f 3 Legend i Tasks Flanned Duration - lanned & Actual , Slack Negatiye SIack .............. . O 8'dIIO I , Overallocated R
- Tags Cade d
Milestones No 51ack + Slack 4 > Negative Slack > < l l Cornpleted A ! Constre ints l c 2 Tags Code l l O
Document S03 25 002 Page 68 of 91 O FIGURE 5.1 DECON ACTIVITY SCHEDULE DEFINITION OF SCHEDULE TERMS Term Definition AB Backfl U1 Backfill Unit 1 Auxiliary Building below grade voids AB Decon U1 Denntnminate Unit 1 Auxiliary Building AB G sul Remove Auxiliary Building systems, group C, from Unit 1 AB sU1 Removal of Auxiliary Building, systems, group D, from Unit 1 ABIn nU1 Unit 1 Auxiliary Buildin intenor demontion ABintrDminU3 Unit 3 Auxiliary Buildin inttrior demolition ActytySpecU1 Write activity specifica ions and procedures for removal of plant systems, Unit 1 ActvrySpecU2 Write activity s systems, Unit 2.pecifications and procedurr.s for removal of plant ActvtySpecO3 Write activity specifications and procedures for removal of plarit systems, Unit 3 AuxBakfilU3 Backfill Un!t 3 Auxiliary building below grade voids AuxExtrDmU3 Unit 3 Auxiliary building exterior demohtion AuxG sU3 g) AuxG sU3 Rernove Unit 3 Auxiliary Building systems, Group C Remove Unit 3 Auxiliar (d Bakfil e 1 Backfi.Il all Unit i voids.y Building systems, Group D BakfilSiteU2 Backfill all Unit 2 voids. BakfilSiteU3 Backfill all Unit 3 voids BeginDormU1 Begin Dormancy for Unit 1 BegmPeriod4 Begm Unit 1 period 4 CondBackflU2 Bac!: fill Unit 2 Full Flow Condensate Polishing Demineralizer building below grade voids CondBakfilU3 Backfil Unit 3 Condensate Polisher builidng below grade voids i CondExtrDmU2 Unit 2 Full Flow Condensate Polishing Demineralizer building exterior demolition CondExtrDmU3 Unit 3 Condensate Polisher building exterior demolition CondIntrDmU2 Unit 2 Full Flow Condensate Pohshing Demineralizer Building interior demolition CondIntrDmU3 Unit 3 Condensate Demin interior demolition ContBekfilU1 Backfill Unit 1 Control / Administration Duilding below grade voids ContIntrDmU1 Unit 1 Control Building interior demolition ContrExtdmU1 Unit 1 Control /Admirustration Building exterior demolition DenRWPhas1U1 Decontaminate Unit 1 Radwaste Phase 1) building. DenRWPhas2U1 Decontaminate Unit 1 Radwaste Phase 2) Building Dcon Aux U3 Decontaminate Unit 3 Auxiliary iding Dcon NSSS U1 Perform Unit 2 NSSS decontamination Gush Deon NSSS U2 Perform Unit 2 NSSS decontamination flush Dcon NSSS U3 Perform Unit 3 NSSS decontamination Gush Dcon RB U1 Decontaminate Unit 1 Reactor Building
/] Dcon RB U2 Decontaminate Unit 2 Reactet Building U Dcon RB U3 Decontaminate Unit 3 Reactor Building
Documens S03 25 002 4 Page 69 of 91 O TIGURE 5.1 DECON ACTIVITY SCHEDULE DEFINITION OF SCHEDULE TERMS (contintied) Term D*finition Dcon/SecurSy Decontaminate / Secure Unit I systems DconDone U1 Unit 1 site decontaminated; radwaste facilities released for removal DconDone U2 Unit 2 site decontaminated; radwaste facilities released for removal DconDone U3 Unit 3 site decontaminated; radwaste facilities released for removal DconRs ':sU1 Decontaminate Unit I spent fuel racks DconWorkDone Decontaminste unit I site DesignWtrC!n Design water cleanup system DetB Prod U2 Establish detailed by-DetB Prod U3 Establish detailed bproduct productinvento inventory for Unit for Unit 3 2 DG ackalU1 Backfill Unit 1 Diesel Gener tin Buffdin below grade voids DG Backf11U2 Backdll Unit 2 Diesel Generatin Euildin below grade voids DG Back.n.lU3 Backfill Unit 3 Diesel Generatin Buildin below grade voids DG ExtDmlnU1 Unit 1 Diesel Generatin Building exterior demolition DG ExtDnunU2 Unit 2 Diesel Generatin Building exterior demolition DG 3xtDminU3 Unit 3 Diesel Generatin Building exterior demolition DG IntDminU1 Unit 1 Diesel Generating Building intesfor demolition DG IntDminU2 Unit 2 Diesel Generating Building interior demolition DG IntDmlnU3 Unit 3 Diesel Generating Building interior demolition DUMMY 1 DUMMY 2 End End of Unit 3 Period 3 activities; project end End Perl U2 End of Period 1 for Unit 2 End Perl U3 End of Period 1 for Unit 3 End Per2 U1 End of Period 2 for Unit 1 End Per2 U2 End of Period 2 for Unit 2 End Per2 U3 End of Period 2 for Unit 3 End Per3 U1 End of Period 3 for Unit 1 End Per3 U2 End of Period 3 for Unit 2 EngrgWrkDone Unit 1 period 1 engine ring work done FHBBackfilU1 Backfill Unit 1 Fuel Handlini; building below grade voids Final Survey Unit 1 Final Survey prior to c ormancy FnlSurvey U1 Perform final Unit 1 site survey by NRC prior to license termina-tio3 , FalSurvey U2 Perform final Unit 2 site survey by NRC prior to license termina- 1 tion (O
.) FalSurvey U3 Perform final Urit 3 site evey by NRC prior to license termina-(lon
Document S03 25 002 Page 70 of 91 O FIGURE 5.1 DECON ACI'IVITY SCHEDULE DEFINITION OF SCHEDULE TERMS (continued) Term Definition Fuel Out All Fu / removed from unit 1 Fuel X.fer Transfer fuel from Unit 1 pool to Unit 2/3 pool FuelBackfiU2 Backfill Unit 2 Fue! Buildm below grade voids FuelBackflU3 Backfill Unit 3 Fuel Buildin below grade voids FuelBdDconU1 Decontaminste Unit 1 Fuel uilding FuelBdDcouU2 Decontaminate Unit 2 Fuel Building FuelBdDconU3 Decontammate Unit 3 Fuel Building FuelBdG CU1 Remove Fuel Building systems, group C, from Unit 1 FuelBdG U2 Remove Fuel Building systems, group C, from Unit 2 FueiBdG CU3 Remove Fuel Building systems, group C, from Unit 3 FuelBdG DU1 Removal of Fuel Building systems, group D, from Unit 1 FuelBdG DU2 Removal of Fuel Build:ng systems, group D, from Unit 2 O FuelBdG DU3 FuelExtr U2 Removal of Fuel Building, systems, group D, from Unit 3 Unit 2 Fuel Beilding extenor demo ation FuelExtrDmU2 Unit 3 Fuel Buildin exterior demolition FuellntDmlU1 Unit 1 Fuel Buildin interior demolition FuellntrDmU2 Unit 2 Fuel Builoin interior demolition FuellntrDmU3 Unit 3 Fuel Buildin interior demolition IntkBakfilU3 Backfill Unit 3 Inta ce Structure below grade voids IntkBkflDmU2 Backfill unit 2 Intake Structure below grade voids Intkint DmU2 Unit 2 Intake Building interior demolition IntkintrDmU3 Unit 3 Intake Structure interior demolition Landscape U1 L,andscape Unit 1 site Landscape U2 Landscape Unit 2 site 3 Landsca U3 Landscape Unit 3 site $ LicAct MU2 Licensing activities for Period ! of Unit 2 LicAct PI U3 Ucensing activities for Period 1 of Unit 3 ' LicAct P2 U1 Licensing activities for period 2 of Unit 1 LicAct P2 U2 Licensing activitics for xricd 2 of Unit 2 , UcAct P2 U3 Licensing activities for :PeHod 2 of Urdt 3 LicActPhase0 LicensMg advities prior to unit I shutdown Mve NSSSE 2 Move vessel cutting equipment to unit 2 reactor building Mve NSSSE 3 Move vessel cutting eqmpment to unit 3 reactor building OthrG D ; , Remove Unit 1 Other Buildings group D systems OthrG D U2 Remove Unit 2 Other buildings group D systems OthrG D U3 Remove Unit 3 Other buildings group D systems PenAreaDenU2 Decontaminate Unit 2 Penetration Area PenAreaDenU3 Decontamination of Penetration Area systems Unit 3 L Per1 Waste U2 Process liquid and solid waste from unit 2 period 1 activities
l Document S03 25 032 1 1 Page 71 of 91 O FIGURE 5.1 DECON ACITVITY SCHEDULE DEFINITION OF SCHEDULE TERMS (continued) Term Definition Per1 Waste U3 Process 11 uid and solid waste from unit 3 period 1 activities Per2Wr;te U1 Process li uld and solid waste from unit i period 2 activities Per2 Waste U2 Process li uid and solid waste from urdt 2 period 2 activities Per2 Waste U3 Process li uid and solid waste from Unit 3 period 2 activities Period 3Activ Unit 17enod 3 activities PnArBakfilU2 Backfil Unit 2 Penetration Arep. betw grade voids PnArIntrDmU2 Unit 2 Penetration Building interior Amolition PreDecomm U1 Pre-decommissionin ( activities Rad Survy U2 Perform detailed raciation survey for Unit 2 Rad Survy U3 Perform detailed radiation survey for Urut 3 RB BackfilU1 Backfill Reactor building below grade voids RB ExtDntinU2 Unit 2 Reactor Building exterior demolition RB ExtDminU3 Unh 3 Reactor building exterior demolition fs) v RB ExtrDmU1 RB G U1 Unit 1 Reactor Building exterior demolition Remove Unit 1 Reactor Building systems, group C RB G U2 Remove Unit 2 Reactor Building systems, group C RB G sU3 Removal of Unit 3 Reactor Building systems, group C RB R Remove Unit 1 Reactor Building systems, group D RB Gc sU2 Remove Unit 2 Reactor Building systems, group D RB G DsysU3 Remove Unit 3 Reactor Building systems, group D RB U ntdmin Unit 1 Reactor Building interior demolition. RB U2IntDmin Unit 2 Reactor Building interior d:molition. RB U3Intdmin Unit 3 Reactor Building interior demolition. RBBackfillU2 Backfill Unit 2 Reactor bullidn below grade voids RBBackfillU3 Backfill Unit 3 Reactor buildin below grade voids Remove Fuel Remove fuel from Unit 1 vesse Rmv RCS U1 Remove Reactor Coolant piping and associated RCS system com-ponents Rmy RCS U2 Remove Reactor Coolant Piping and associated RCS system com-ponents Rmy RCS U3 Remove Reactor Coolant piping and associat<.d RCS system com-oonents RmvCondnsrU1 Remove Unit I main condecser RmvCondnsrU2 Remove Unit 2 mam condenser RmvCondnsrC3 Remove Unit 3 main condenser RmvEssStrU3 Remosal of Utdt 3 essential structures Rmvl NSSS U1 Segmentrion of Unit i vessel intemals RCS/ Pressurizer Rmvl NSSS U2 Segmentation of Unit 2 vessel intemals RCf/ Pressurizer q Rmvl N3SS U3 Segmentation of Unit 3 vessel internals RC3/ Pressurizer Q RmvlStGen U1 Removal of unit 1 Steam Generator:
Document 503 25 002 Page 72 of 91 v FIGURE 5.1 DECON ACTIVITY SCHEDULE DEFINITION OF SCHEDULE TERMS (continued) Term Definition RmvlStGen U2 Removal of unit 2 Steam Generators, RmvlStGen U3 Remove Unit 3 Steam Generators RmvNEssStrU1 Removal of Unit I non-essential structures RmvNEssStrU2 Removal of Unit 2 non. essential structures RmvNEssStrU3 Retnoval of Unit 3 non-essential structures RmvR.acks U1 Remove Unit 1 Spent Fuel Racks RmvRacks U2 Remove Unit 2 Spent Fuel Racks RmvRacks U3 Remove Unit 3 Spent Fuel Racks RmvS sU1GrpA Removal of Unit 1 tant systems, group A Removal of Unit I lant systems, group B C RmvS RmvS sU1GrpB sU2GrpA Removal of Unit 2 lant systems, Group A s RmvS sU2GrpB Re.moval of Unit 2 lant systems, Group B RmvS sU3G A Removal of Unit 3 lant systems, group A Rmy sU3G B Removal of Unit 3 lant systems, group B Rmv tbGet 1 Remove Unit 1 tut ine generator set RmvTurbGenU2 Remove Unit 2 nirbine generator set RmvTurbGenU3 Remove Unit 3 turbine generator set RPVrmvprepU1 Prepare Unit I reactor vessel for segmentation RPYrmv Prepare Unit 2 reactor vessel for segmentation RPVrmy;prepU2 U3 Prt. pare Unit 3 reactor vessel for se mentation RWPhasl DUI Remove Unit 1 Radwatse Phase 1 Building systems, Group D RWPhas1G U1 Remove Unit 1 Radwaste Phase 1 Building systems, Group C RWPhas2GpDU1 "emove Unit 1 Radwaste Phase 2 Building systems, group D RWPhas2GrCU1 Remove Unit 1 Radwaste Phase 2 Building systems, group C SaEqGpCsysU3 Remove St.fety Equioment Building systems, g,roup C, from Unit 3 SaEqGpDsysU3 Removal of Safety l Equipment Building sysm'ns, group D, from Uni: 3 SfE BakfilU2 Backfill Unit 2 Saftey Equipment building below grade voids SE Bald 11U3 Backfill Unit 3 Saftey Eqtupment building below grade voids SfE ExtrDmU2 Unit 2 Safe quipment building exterior demoluton SE ExtrDmU3 Unit 3 Safe qtupment building exterior demolition SfE IntrDmU2 Unit 2 Safe qtupment buildin interior demolition SfE ntrDmU3 Unit 3 Safe pment buildin interior demolition Sf DU2 Removal of Equipment B ilding systems, group D, Unit 2 Sft CU2 pv Sh ay2 Remove Unit 2 S fety Equipment building systems, group C Delay for final shutdown of Unit 2 ShutdnLelay3 Delay for final shutdown of Unit 3 Site Ready Unit I site ready for dormancy SpentFuelDel Spent Fuel Delay for Unit 3
l Document S03 25 002 Page 73 of 91 O FIGURE 5.1 DECON ACTIVITY SCHEDULE DEFINITION OF SCHEDUl E TERMS (continued) Term Definition Start Bogin pre decommissioning engineering and planning for decom-missioning of units 1 & 2 Start U1 Peri Start Unit 1 Period 1 operations Start U2 Peri Start Unit 2 Period 1 Operations TBExtrDmU3 Unit 3 Turbine buPding exterior demolition TBU1 Backfill Unit 1 Turbine Building backfill TBU1ExtrDem Unit 1 Turbine Building exterior demolition TBUlintrdmln Unit 1 Turbine Buildin r., MSSS interior demolition TBU2intrdmin Unit 2 Turbine /MSSS 3uilding exterior den olition TBU31ntrdmin Unit 3 Turbine Building / MSSS interior deme!! tion Term Uc U1 Terminate Unit 1 operatin license Os Term 'ie u2 Ter-i ete u it 2 oPer tie iiee se Term Lic U3 Terminate Unit 3 oaeratin license TkEcBackflU3 Backfill Unit 3 Tanc Enclosure below grade velds TkEcIntrDmU3 Unit 3 Tank Enclosure interior demolition TkEncBkfDmU2 Backfill Unit 2 Tank Eclosure builldng belov. grade voids TkEncintDmU2 Unit 2 Tank Enclositre buildin interior demolition TurbBakfilU2 Backfill Unit 2 Turbine Buildi below grade voids TurbBakfilU3 Backfill Unit 3 Turbine buildin below grade voids TurbExtrDmU2 Unit 2 Turbine Building exterior demohtion TurB1 DUI Remove Unit 1 Turbine Building systems, group D TurB1 DU2 Removal of Unit 2 Turbine Building systems, group D TurB) DU3 Remove Unit 3 Turbine Building systems, group D Unit orm Unit 1 Dormancy Unit 2 Delay Fuel Delay Unit 2 Down Unit 2 end of operatin life Unit 3 Down Unit 3 end of operatin life VenEqBekflU1 Backfill Unit 1 Ventil on Equipment Room below grade voids o
h I i FIGURE 5.2 Decommissioning Tiimeline (not to scale) ! i i San Onofre bucteer Generatieg Statici h it 1 (SAISTOR) 1 1 I i i I I -v i i ! -l ! l Startsp shut- Period l Period l Period l Period l Period l 1 I h 1 1 2 1 3 4 5 ' 1 1 I s i . . . . . j l<--Cons t ruc t iow>< ?Ient operatior. >40 41 50 50 53 55 1964 1968 2004 2005 2014 2014 201T 2019 Mar Jan nor nor ney Now Apr Aus . j i sen ensfre nuclear Generatieg station thit 2 (DECON) ) l l lc vet Isrs -l ; I I I ! j l Stortty Shut- l Period l Period l Period l l I h i 1 1 2 1 3 i t 9 i f 9 f f f 3 5 5 5 4 5 5 4 i l <----Const ruc t ion-->< ?Iant Operstior. >40 41 42 45 45 48 l 1973 1983 ' 2913 2014 2015 2018 2018 2021 Oct Ang Oct Dec Dec Apr Oct nor I i , Sei Oriefre Amsteer Generetleg Station thit 3 (DECON) ; t l C I 14
- t is's: ->l g 2
.I I I I c j l Shut-Stortsp l Period l Period l Period l I ! h 1 1 1 2 1 3 I m E l
l < --C.vis t ruc t i on->< H~ Plant Operatier. >&O 43 44 45 46 50 ( y g tg i 19T3-Oct 1984 Apr 2013 2016 Feb 2017 2018 2019 2023 p ' Oct Feb Cct No ' Aug m cs w C ,
- tJ l i
i I
7_.. Document S03 25 002 : Page 75 or 91 iO i ! 6. PADIOACTIVE WASTE VOLUME I The radioactive waste volumes generated during the SONGS decommissioning are shown by l line activity in the cost tables (Tables 4.3,4.4 and 4.5). Approximately 32,906 cubic yards of material are generated. Waste volumes are quantified consistent with 10 CFR 61 classifica-l tions. The waste volumes shown are calculated based on the gross container volume to be 3 shhed and buried in controlled burial grounds. Most of the materials being trans rted for controlled burial are categorized as I.ow Specific i ne con (tainers must be strong tiActivity t packages. For this IS A) study, material commercially containin available Type steelA quan j containers are presumed to be use for piping, small components and connete. The reactor vessel and internals are categorized as large quantity shipments and, accordmgly, must be shipped in reusable shielded casks with disposable hners. In this case, the liner
- volmne is taken as the waste volume.
The waste volume attributed to site decontamination is primarily generated during Period 2 of DECON and Period 4 of SAFSTOR. The rtdioactive waste generated as a result of the decommissioning of the San Onofre Nuclear Generating Station is destined for disposal at the
!s future Ward Valley burial facility.- At this time there is no operating burial site. Con-sequently,ll SCE as we as the rate structure for an existing and operating burial fac Table 6.1 displays waste vo;ames associated with the decommissioning. No process system containing or har ' ling radioactive substances at shutdown is presumed releasable as non-
) contaminated scrap metal because of the presence oflong term radionuclides. i i l i v 5
. O 4
j
-...,,,m. - ~ w e , ,. ,-- -
w- , -- - - , - e y 9 r- -- -w..w-,-. - , , -----rv ,,
Document S03 25 002 Page 76 of 91 , O l l TABLE 6.1 l RADIOACTIVE WASTE BURIAL VOLUMES FOR DECOMMISSIONING l Alternative Wast Volume 2 Class (cubic yards) Unit 1 A 4,870.2 B 0.0 C 246.6
>C 30.2 .
Total 5,147.0 Unit 2 A O C B 12,214.5
. 0.0 263.5
>C 209.0 Total 12,687.0 Unit 3 A 14,644.8 B 0.0 C 263.5
>C 1612 Total 15,072.0 1
Waste is classified according to the re Code of Federal Regulations, Part 55 61.quirements as delineated in Title 10 o l 2 No esthnate has been made of the LSA waste that will be generated during the i operation of the ISFSI. O
..,n.n , - - , --
-w---- -m-~ , c' - I*^= * ~ * " ~ * * ~ ~ ' " ' " ~ ~
- Document S03 25 002 Page 77 of 91 O
- 7. OCCUPATIONAL EXPOSURE Estimates of occupational radiation exposure were developed by TLG Engineering. Radia-i tion doses to decomnussioning workers are calculated as the product of the estimated radia-l l
tion zone work force requirements and the radiation exposure rates estimated for each decommissioning task. The decommissioning occupa ional exposure estimates are based on the following assumptions:
- 1. Occupational exposure estimates include only the craft labor necessary for decontamina-tion, removal and packaging activities as well as all required health physics personnel exposures fri support of these activities. Casual caposures to the plant staff are not included in this estimate.
- 2. Personnel exposure to radiation is minimized by utilizing shielding and remote handling techniqaes and avoiding higher radiation fields when personnel presence is not necessary.
- 3. Local exposure rates near items such as tanks and pipes are reduced by a successful chemical decontamination program prior to work in that area.
- 4. Careful prompt accounting of accumulated radiation exposure is maintained to rapidly
/ \ identify tasks causing excessive dose accumulation by workers so that corrective action can ce taken.
- 5. Cobalt-60 is the primary cuntributor to radiation exposure. The reduction in personnel l
exposure from area and components during the activities performed after the SAFSTOR dormancy period is assumed to be that of the reduction in Cobalt-60.
- 6. Exposures as the result of s therefore are not included. pent fuel storage activities are expected to be minimal and It should be noted that the radiation exposure rates used to calculate the exposures shown in Tables 4.3 and 4.4 amd 4.5 are based on optimum conditions; factors such as alant age, maintenance and operating history could cause the expected exposure rates at the time of decommissioning to vary significantly. Table 7.1 summarizes the occupational personnel exposures which are presented by line activity in the cost tables (Tables 4.3,4.4 and 4.5) that are projected in the performance of the variotis decommissioning alternatives.
Implementation of the DECON alternative yields the highest occupational radiation exposure because the work is performed soon after shutdown without the benefit of any extended decay time for the radionuclides on site. The SAFSTOR alternative yields a lower cumulative dose, primarily due to the decay during dormancy and because almost all of the dismantling opera. tions are performed after the dormancy penod. (Q
.. ~ . - - _ _ _ .... _-- . .-. - - .--- . -.- .- -.. - . _ - - . . ..-
Document S03 25 002 Page 78 of 91 O j TABLE 7.1 OCCUPATIONAL EXPOSURE FOR DECOMMISSIONING 1 Decommissioning Alternative ManReml l - H ! Unit i 909.2 . Unit 2 2,338.2 ~ Unit 3 { 3.137.2 4 Station Total 6,384.6 i l i 1 No estimate has been made of the occupational radiation exposure that will be incurred during the operation of the ISFSI due to the low residency times required in any radia. ! tion field. A
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Docume 503 25 002 Page 79 of 91 O
- 8. CONCLUSIONS l'ecommissioning technology is well established and the tools and equipment necessary to e *mpletely dismantle the San Onofre Nuclear Generating Station are available and have been uemonstrated. The projected costs to decommission the plant, presuming the use of an integrated Removal / Dismantling alternative, including the five year operation of the facility as an independent spent fuel storage installation, is 5937,007,200. This projected cost includes shipment of all wastes and dismantled materials to a regional burial site and demolition of the remaining site structures. The estimate reflects the site specific features of th Nuclear Generating Station and the projected cost of radioactive waste shippm,e San Ono g and burial costs. An analysis of the major activities contributing to the total cost is shown m Table 8.1.
The decommissioning and utility staffs along with the reinoval activity combine to represent the majority of the cost to decontaminate the San Onofre Nuclear Generating Station. This a direct result of the labor intensive nature of the decommissioning process. Burial is the next largest cost component reflecting the costs associated with the development of new regional waste disposal facilities. Transportation costs are most sensitive to increases in fuel costs and distances to existing or new burial facilities. Removal costs are dependent on the degree of remotely operated equipment available in the future and the associated higher cost of that equipment versus the savings in labor costs. O This stuav ror the s = oeotre secieer oe=er ties statio# vrevioes == esti-ete ar decommis-sioning the site under current requirements based on present day costs and available tech-nology. As additional dismantling experience on large reactors becomes available, cost estin.ates must be modified to reflect this experience. In addition, there are costs associated with decommissioning activities that historically increase at rates significantly greater than inflationary trends. For example, the cost of radioactive waste burial has increased rapidly in the last few y/ revised as requiredears. It is therefore appropriate that this cost es and updated .
Document S03 25 002 Page 80 of 91 O '
' TABLE 8.1
SUMMARY
OF DECOMMISSIONING COSTS Costs Percent of Work Category . (thousands) Total Costs Unit 1 Decontamination 5,179 3.06 Removal 45,829 27.09 Packa 1,845 1.09 Shippm,ging 1,990 1.18 Burial (g off site 21,967 12.99 Decommissiom)ng Staffs 60,970 36.05 a Other 31.350 18 14 100.00 Subtotal 211,413 - Unit 2 Decontamination 7,476 3.39 Removal 87,139 39.50 Packapng 3,691 1.67 Shippm 3,001 1.36 Burial (goff site) 55,693 25.24 Decommissioning Staffs 44,158 20.02: Other
- 19.454 _jj2 100.00 Subtotal 275,765 Unit 3 Decontamination 10,000 3.39 Removal 136,546 46.27 Packapng 4,360 1.48 Shippmg 3,180 1.08 Burial off site 65,045 22.04
- Decom(missiom)ng Staffs 52,050 -
17.63 Other* 23.946 _821 i 100.00 Subtotal 368,909 O s' 'i ree i c /2
- co ti e c7) 854.a=7 l
- i Other includes: engineering & preparations, property taxes, insuunce and plant ;
. energy budget
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Document S03 25 002 , Page 81 of 91 O
- 9. REFERENCES
- 1. U.S. Code of Federal Regulations, Title 10, Parts 30,40,50,51,70 and 72 " General Requirements for Decommissioning Nuclear Facilities", Nuclear Regulatory Commis-sion, Federal Register Volume 53, b umber 123 (p 24018 +), June 27,1988.
- 2. U.S. Nuclear Regulatory Commission Re ting Ucenses for Nuclear Reactors", June, pilatory Guide 1.86, " Termination of Opera-1974.
- 3. " Building Construction Cost Data 1990", Robert Snow Means Company, Inc., Kingston, Massachusetts.
- 4. Tri State Motor Transit Company, published tariffs, Interstate Commerce Commission (ICC) Docket No. MC 10939, and Supplements.
- 5. U.S Ecology, Washington Nuclear Center, Hanford, Washington, Rate Schedule.
- 6. T.S. LaGuardia et al.," Guidelines for Producing Commercial Nuclear Power Plant Decommissioning Cost Estimates", AIF/NESP.036, May 1986.
- 7. W.J. Manion and T.S. LaGuardia, "An Engineering Evaluation of Nuclear Power O+ Reactor Decommissioning Alternatives", AIF/NESP-009, November 1976.
j 8. WJ. Manion and T.S. I.aGuardia, " Decommissioning Handbook", U.S. Department of Energy, DOE /EV/10128 1, November,1980.
- 9. Cost En 22, Rev.gineers Notebook: American Association of Cost Engineers, AA 4.000, pg 3 of 2 (January 1978) (Updated periodically).
10. R.L Smith, GJ. Konzek, W.E. Kennedy, Jr., " Technology, Safety ano Ccm of Decom-missioning a Reference Pressurized Water Reactor Power Station," NUREG and addenda, Pacific Northwest Laboratory for the Nuclear Regulatory mmission. Co/CR 013 June 1978. 11. J.C. Evans et al., "Long-lived Activation Products in Reactor Materials" NUREG/CR - 3474, 1984 Pacific Northwest Laboratory for the Nuclear Regulatory Commission. August
- 12. H.D. Oak, et al., " Technology,-Safety and Costs of Decommissionin Boiling Water Reactor Power Station," NUREG west Laboratory for the Nuclear Regulatory Com/CR-0672 a mission. June 1980.
Pacific North-13.
" Harvard Project Manage,r", Computer Software and User's Manual, Version 3.0, Soft-ware Publishing Corporauon,- Mountain View, California. August,1988 O 14. u.S. oegart e=t of Trans
" Transportation", Parts 173 b<tatio#.
ough 178. Section 49 ef tae code ef reder i ae8ui tiees. b'
Document S03 25 002 Appendices A .11 Page 82 or 91 O APPENDIX A UNIT COST FACTOR DEVELOPMENT O O
Document S03 25 002 Append.ces A B Page 83 of 91 O UNIT COST FACTOR DEVELOPMENT femals: Unit C~ Factor for Removal of IIeavily Reinforced AcLvated or Contaminated Concrete.
- 1. SCOPE F
i4 Concret:, tr.at has been contaminated or neutron activated will be removed by controlled bir. sting. holes will be drilled ve-tically into the concrete with a track drill; the holes loaded Nr with explosives; and the face of the cor. crete blown off. An oxyacetylene torch will be used for
} reinforced concrete rebar cuttink or other misc. structural steel. Rei:tforcing is assumed to be n No.18 rebar (21/2" OD) on i." centers. Each sequence removes 7.4 cy of concrete. The rubble will be lonced into ccatainers, transferred to t!'e packaging area, and :oaded into boxes for @ ment and burial.
2. EQUIPMENT AND MATERIALS REQUIRED
- Pneumatically operated track drill
" Compressor 750 CFM; diesel. driven
- Air hoses and connections s
- Blasting mats (minimum 6 to 10' x 12' steel) $.
r i;
- Fog spray system - multiple spray heads
- Explosives magazme
- Oxyacetylene torch, gas bottles, hoses fire uiwguishers
- Front end loader with backhoe
- Rubble transfer container
- 3. J' ;? LATIONS Requitec Operation 5 Durations:
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . se qTFence Int e grat e d a ..................
Clock all equipment (drills, compressor fog spray, blast mats) b Move drilling equipment to location 15 15 c 15 (a) Drill boles on 2'cen:ers,2'x 20'x 5'(depth) 160 d Place charges in hMes 160 e 100 100 Piace blast mats and start fog spray f Evacuate ares and detonate charges 30 30 g Verify charges have been shot 15 15 n 10 10 Remove fog spray & blasting mats i 30 30 Sa.mple concrete rubble /rebar for radioactivity 15 Cut rebar with torch 1g0 )
< 120 .
Remove rubble into transfer container 60 60 1 Move transfet antainer to packaging area Total Durations: 10 10 600 570 3
I. i
- Document S03 25 002 Appendices A . Il
_l 4 Page 84 of h t F APPENDIX A Cont'd. 8 Base Activity Duration = 570 minutes to rernove 7.4 cy I Work . Hei tDifficulty ht (20 %) Factors Against Base Duration 114 i Mascs (50%) -285 Radiation 40% .225 Actual Dur(ation) 1197 4 Work Difficulty Factors Against Actual Duration PCs (30%) _319 Productive Duration 1556. Nonproductive Time Factors
- Work breaks (833%)
F Work Duration - n0 , 1686 Total 11me in Minutes = 1686 minutes or 28.1 hours per 7.4 cy, Duration Rate Cost Labor Crew No. 1
- (hrs) ($/hr) ($)
i Laborers 4 28.10
- Operator
- 20.80 - 2,337.92-2 28.10 24.9u 1,402.75
- Blasting expert 1 28.10 21.42 601.90 t Assistant 1 28.10 l Foremen -21.42 601.90 I
1 28.10 .21.12 601.90 i Subtotallabor costs 5,54638-OH&P on labor 1 4,034.99 Total Labor cost 9,58137 Materials Equipment
- Cor < Ref. "
Rate, $ i 3 Blasting mats (10'x12') 2.78 hr 23435- 1 Fog spray system (1 hr oper time) ?.27 hr- -2.27
- 750 CFM compressor 2 1$.,8 hr 434.99 3 Front end loac er w/ backhoe 9.77 nr
- . Track drill '274.54 4 Subtotal materials 17.44/[hr - 490.06- '
5 z
$1,436.21 i
4 4
- Document S03 25 002 Appendices A. 8
, Page 85 of 91 O
APPENDIX A Cont'd. Materials Equipment Cost + Ref. " Rate, 3 Oxya:etylene torch 6.36 hr 12.72 6 Compressor consum/consumables ables (2 hrs) 14.95 hr 420.09 3 Bucket loader consumables 5.86 hr 164.67 4 Drill: bits, etc. 8.72 hr 23.26 5 Plastic snects/b(2.67 ags (250) hr oper time) .05 sf- 12.50 7 40 pounds exp,iosive 1.31 lb 52.40 8 20 Blasting caps 1.77 cap ._3140 9 3ubtotal consumables $P1.04 Total equipment & materials (ine OH&P @ 17.25%) $2,529.38 Total Cost (labor & materials for 7.4 cy) $12,110.75 - O roTitunircoSrricroR: $1. 634.599 er er
+ Adjusted for regional material costs; for SONGS use San Dieco, California @ 101.0%
Based c;-:n appiitable ratcs References
- 1. R.S. Means (1990) 022,23 6
- 2. McMaster<arr Ed. 94
- 3. R.S. Means 1990 016,pp 424 0700 735 4.~ R.S. Means 1990 016,406 4 400
- 5. R.S. Means 1990 Crew B-47
- 6. R.S. Means 1990 016,420 6360
- 7. R.S. Means 1990 015, 602-0200 :
- 8. - R.S. Means 1990 022, 234-3700
- 9. R.S. Means 1990 022, 254-3500 O
Document S03 25 002 Appendices A B Page 86 of 91 O , APPENDIX B UNIT COST FACTOR USTING l l l l l l 1 O l 1 1
Documcnt S03 25 002 Appendices A B Page 87 of 91 O APPENDIX B-1 UNIT COST FACTOR LISTING Non contaminated Factors Unit Cost Factor Value Remove pipe <2.5 inches diameter, S/ linear foot 7.63 Remove pipe 2 5-8 inches diameter, S/ linear foot 13.18 Remove pipe > 8 inches diameter, S/ linear foot 27.85 Remove valves 2.5-8 inches 161.41 Remove valves > 8 inches 315.28 Remove pumps, <300 unds 158.90 Remove pumps,300-1 unds 355.17 Remove pumps,1 pounds 2,090.31 Remove pumps, > 10000 pounds 3,619.37 Remove heat exchanger.% <3000 paunds 716.05 Remove heat exchangers, >3000 pounds 2,032.23 . fh .d Removal of moisture separator / reheater Remove tanks, <500 gallorc 15,201.19 257.34 Remove tanks,500-3000 gallons 614.81 Remove tanks, >3000 galons, S/ square foot 5.93 Remove misc. componems, <300 ds 95.72 Remove misc. components,300-1 unds 335.55 Remove misc. components,1000-1 pounds 671.10 Remove misc. cc,mponents, > 10000 pounds 2,029.09 Remove electrical cable tray, S/ linear foot 8.80 Remove electrical conduit. S/ linear foot 5.84 Remove feedwater heater 6,509.45 Removal by manual Game cutting, S 4.46 Removal of electrical transformers 30 tons </ inch 1,056.88 Removal of electrical transformers > 30 tons 3,043.61 Removal of standby diesel generator 4,988.22 Removal (st UVAC ductwork, S/ pound .63 Removal of tbine-driven pumps < 10000 pounds 2,162.57 - Removal of turbine-driven pumps > 10000 pounds 3,570.66 Removal of PWR turbine-generator 117,938.10 1 I h
Document S03 25 002 Appendices A B Page 88 of 91 1 l- APPENDIX B-1 l UNIT COST FACTOR LASTING i ' Non-contaminated Factors (continued) Unit Cost Factor Value !- Removal of PWR main condenser 329,729.10 Removal of small bore p,ipe hangers 21.43 Removal oflarge bore 83.45 Removal ofinstrument/ pipe hangers' sampling tubing, S/ linear foot .35 Remove clean concrete Doors, S/ cubic yard 198.12 Remove heavily reinforced concrete, S/ cubic yard 186.56 Removal of concrete Door sections, S/ cubic yard 779.87 t Demolish subterranean tunnels, S/ linear foot 87.96 Excavation. S/ cubic yard 2.11 Perform bldg demohtion (volumetric), S/ cubic foot .20 pJ s Remo ral of foundation concrete, S/ cubic yard Remcve structural steel, S/ d 429.23
.26 Remove steel Door gratmg, / square foot 3.02 Remove free-standing stsel ner, S/ square foot 10.40 Remove grade slab concrete, S/ cubic yard 162.63 Remove concrete rubble, S/ cubic yard -8.75 L T nadmping, S/ acre 14,337.91 Remove monolithic concrete, S/ cubic yard .549.25 Remove concrete anchored steel liner, S/ square foot 4.44 Remove standard reinforced concrete, S/ cubic yard 270.00 Remove masonrylblock, cubic yard 47.77 Placement of scaffolding, /s 3.51 g Backfill of below grade voids,quare S/ cubic yard foot 14.62 t
Removal of overhead cranes 457.18 R:moval of overhead cranes /monorad's < 10 ton cap
/ monorails > 50 ton cap 4,345.41
- O
Document S03 25 002 ! Appendices A B Page 89 of 91 O APPENDIX B 2 UNIT COST FACTOR LISTING Conts,minated Factors Unit Cost Factor Value l Remove pipe <2.5 inches diameter, S/ linear foot 57.21 Remove pipe 2.5-8 inches diameter, S/ linear foot 84.05 Remove pipe > S inches diameter, S/ linear foot 168.77 Remove valves 2.5-8 inches 484.01 Remove valves >8 inches 843.85 , Remove pumps, <300 pounds 497.03 l Remove pumps,3001000 pounds 1,239.46 l Remove pumps 5,450.68 Remove aumps,,100010000
> 10000 pounds 11,303.77 Remove leat exchangers, pounds
<3000 pounds 2,217.29 Remove heat exchan , >3000 pounds 6,7 % .29 Remove tanks, <500 allons 897.99 Remove tanks, >500 allons, S/ square foot 20.36 Remove misc. components, <300 unds 352.93 Remove mim camponents,3001 pounds 906.53 Remove mise. components,1000-10000 pounds 1,695.27 Remove misc. components, > 10000 pounds 4,315.15 Remove electrical cable tray, S/ linear foot 33.08 Remove electrical conduit, S/hnear foot 28,85 Plasma are cut of cont. equip, S/ square inch - 13.11 Surface decontamination, S/ square foot -5.77 Procure and prepare LSA 4' x 4' x 8' box 940.76 Remove activated / contaminated concrete, S/ cubic yard 1,636.59 Drill & spall contamii.aed concrete surfaces, S 8.63 l Decontaminate large components, S/ tsquare foo/ square foot 20.88 1
Decontamination rig hookup, each 5,526.22 Remove concrete anchored steelliner, t/ square foot 25.06 Decon flush of components / systems, # dlon 3.99 Remove free standmg steel liner, S 28.47 Scabble concrete surfaces, foot S/ square /squa,re foot 6.96 O i t _
Document S03 25 002 ' -Appendices A B Page 90 0f 91 iO 4 l i . APPENDIX B 2 < i l UNIT COST FACTOR LISTING - l Contaminated Factors (continued) 4 Unit Cost Factor Value , Placement of scaifolding, S/ square foot 5,% - Removal of HVAC ductwork, $/ pound 2.08 Removal of turbine-driven pump < 10000 pound '5,010.05 Removal of turbine driven pump > 10000 pound - 9,4 0.69 - Cost of LSA drum & preparation for use 127.55 Cost of cask liner for CNSI 14-195 cask 6,214.67 i Cost of cask liner for CNSI 8-120A cask (resin) 9,377.24
- Cost of cask liner for CNSI 8 120A cask (filter) 9,370.81 Removal of small bore p,ipe hangers 52.02
, Removal oflarge bore pipe hangers 205.08 Removal ofinstrument .60 Decontamination of sur/ sampling tubing, $/ linear foot faces by vacuunung, $/ square foot 2,67 I l i.j-l .I i 4 i
Document S03 25 002 Revision Log Page 91 of 91 Revision Lag Rev. Date Page Description Approval A 7/9/90 Draft FWS B 7/31/90 Final FWS i r O d , d d m - _ _ - J}}