ML17339A334
| ML17339A334 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 10/27/1979 |
| From: | Marshall R, Rogow B MARSHALL, R.A., ONCAVAGE, M., ROGOW, B. |
| To: | FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 7911290446 | |
| Download: ML17339A334 (96) | |
Text
TPg) go~ >O~~C UNITED STATES OF ANER1CA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter ox Docket Nos. 50-250 50-25k FLORIDA POWER AND LIGHT COMPANY (Proposed Amendments to Facility (Turkey Point Nuclear Generating Operating Licenses to Permit Steam Generator Repa'c Uni,t Nos. 3 and A 0}
~
INTERYENOR MARK P. ONCAVAGE'S gag,V INTERROGATORIES TO, AND REQUEST 6 FOR THE PRODUCTION OF DOCUMENTS FROM, LICENSEE FLORIDA POWER. AND LIGHT COMPANY pe ~
Pursuant to lO CFR 8 2.'740(b}, Intervenor Mark P. Oncavag requests that the following interrogatories be answered. fully, in writing, and under oath or affirmation by licensee Florida Power 5 Light Company.
For each response to the interrogatories listed below, identify the person or persons who prepared, or substantially contributed to the preparation of, the response.
The interrogatories attached are to be considered licensee's continuing obligation. Accordingly, if, after these interrogatories have been answered, additional information comes to attention of the licensee with respect to one or more of'he answers, the answers should be amended in a timely manner to provide such additional information.
Intervenor further requests that licensee, pursuant to 10 CFR 9 2.701, provide copies of, or make available for inspection and copying, the documents designated by licensee in response to these interrogatories within 30 days. of service.
Il For each response to these interrogatories:
A. Identify all documents, reports and studies, and the particular parts thereof, relied upon by the licensee;. now or in the past, which serve as the basis for the answer. In lieu thereof, at licensee's option, a copy of each such document and study may be attached to the answer.
B. Identify all documents, reports and studies, and the particular parts thereof, examined. but-not relied upon by the licensee, which pertain to the subject matter questioned. In lieu thereof, at licensee's option, a copy of each such document and study may be attached to the answer.
C. Identify by name, title and affiliation each licensee employee or consultant that has the expert knowledge required to support the answer to the question.
.D. Explain whether licensee is presently engaged xn or intends to engage in any further planning, consultation, research, or work which may affect licensee's answer. Identify such planning, consultation, research or work.
E, Identify any person or persons, if any, whom licensee intends to have testify as expert witnesses, or otherwa.se, on the subject matter questioned. Provide the names, addresses, educational background, and professional qualifications of each such person.
P. Provide summaries of the views, positions or proposed testimony from all.person@, identified in E above that licensee intends to present during the proceedings.
G. Identify by author, title, date of publication and publisher, all books, documents, and papers that licesee intends to.
employ .
or rely upon in presenting a direct case on the subject matter questioned and provide copies of, or make available for intervenor's inspection and copying these items.
H. Identify by author, title, date of publication and publisher, all books, documents,,and papers that licensee intends to I
employ or rely'upon in conducting cross-examination of prospective intervenor witnesses testifying on the subject matter questioned.
ntention i 1-1. State in detail what assurances licensee can provide f
that upon completion of the steam generator repairs the nuclear units 3 and 0 at Turke y P oint vrill provide maintenance free operations for the remaining life of the units.
A. t St ate the basis for any such assurance proffered.
B. Provide all data and calculations, testing results, and consultation reports that support th e b ases or any such assurance.
I 1-2. Does licensee forsee any ". '= major repairs or major i
maintenance to the nuclear reactor un t s 3 an d 0 at Turkey Point in the next ten years of'peration of the units?
A. If so, what?
B. If not, vrhy not?
1-3. State the details of or produce any guarantees or warranties, ll contractural or otherwise that exist or viz ex'.st between the manufacturer of +he replacement steam generator assemblies and licensee who.ch ensure that the redesigned, assemblies vrill fulfill their intended function without breakdown and further tube degradation 1-4.'tate ate vrhen vr the steam generator assemblies which vrill serve as replacements'n the proposed. repairs were ordered from the manufacturer.
1-5. State the date s of the fabri.cation and construction of the
."eplacement -steam generator assemblies.
1-6. Do the re p lace ment steam generator assemblies incorporate
- he most recent improvements in steam generator design?
A. If so, state in detail the nature of those improvements.
B. If not, state details of all modifications or improvements made by the-manufacturer in steam generator design since manufacture of the replacement steam generator assemblies.
1-7. State the bases relied upon by licensee that the replacement steam generator assemblies will perform without tube degradation for the remaining 3.~fe of the units. Provide all test data in support of any such bases..
1-8. Estimate any potential tube degradation after installation of the steam generator assemblies'pon resumption of reactor operation.
Provide data and calculations supporting any such estimates.
1-9. State. whether there .is any corrosive chemical material t
in the steam generator system left from phosphate treatment system that will not be removed by the replacement of the steam generator lower assemblies.
A. If none, explain how such material was removed.
B. If. there is, provide details on each chemical substance present.'nclude:
(i) Identification of each such substance.
(2) The amount present.
(3) Location in the steam generator system.
(0) The estimated effect on operation's of the steam generators after the repairs are completed.
A (5) Test data, measurements, calculations, and any other analysis made in determining the presence and significance of any such substance.
1-10. Describe in detail the chemistry of the coolants that will be used in the primary and secondary coolant systems in the replacement steam generator assemblies when operational.
i-ii. State whether licensee has or is considering or has been directed by the NRC Staff to consider any retrofitting or backfitting to incorporate safety features, which the NRC Staff has determined as being necessary since review of the Three Nile Island accident, while the units to be repaired are shut down.
A. If not,
~h why not?
B. IZ so, provide 'details of any such considerations.
C. If by NRC Staff direction, provide details, of any correspondance or communication transmitting such direction.
1-12. Describe in detail or provide all data, calculations and any other information used in licensee's analysis and evaluation of the cost effectiveness of total decontamination of the defective steam generators and work areas prior to initiation of repairs as a method for reducing the total operational .exposure required by the repairs. ,Describe in- detail the procedures that were considered. "
1-13. Mhat is meant by "uncertainties in estimating job man-hours and radiation intensities" stated in the EIA on page 4-2, paragraph 1?
A. Provide data and calculations f'r estimating the range for job man-hours.
B. Provide data and calculations for estimating range of radiation intensities.
C. Provide the ranges of radiation field intensities.
1-14. Describe in detail all testing and inspection that will be performed to-assure:
A. Meld quality for all welds done during repairs.
B. Tube integrity.
C. Containment building integrity.
D. Primary loop integrity.
E. Secondary loop integrity.
F. All other inspections needed prior to the generation of electricity at full power per reactor.
1-15. Provide task descriptions, man-hour requirements, radiation intensity data, and man-rem exposure incurred for all tasks associated I
with all testin'g an'd inspections that will be performed prior to the generation of electricity at full power per reactor.
1-16. State the names, addresses and telephone numbers, and job titles of all individuals who prepared, or substantially contributed, to the preparation of the SGRR and identify the sections of the SGRR each person or persons worked, including all amedments to the SGRR.
1-17. State whether any firms or corporate entities other than FPL contributed to the preparation of the SGRR or any amendments there- P to ~
A. Give the name, address and telephone number of any such firm or corporation that contributed to preparation of the SGRR.
- 3. Give the name of any person or. persons responsible f'r the preparation of any such firm or corporation's contribution to the SGRR'.
C. Specify which firm or corporation contributed to which sections of the SGRR.
1-18. Xs there at the present time or any time in the last three months that local contamination procedures are being or were employed at Turkey Point? If so, describe in detail:
A. What local decontamination is being done.
'I B. The system or structure being decontaminated, and its location.
C. The employees or workers who are implementing local decontamination. Include their race, place of geographic origin, rate of pay, training, previous skills, and knowledge of nuclear labor techniques and attendant dangers, their sex, their age and how and by
=whom they were recruited for the'mployment.
1-19. Describe in detail all contingency plans prepared by licensee to safeguard the repair project and/or to protect the public from releases of radioactivity, in the event of a major hurricane occurring during the time projected .for the repairs to the steam generators. Include all plans considered but not prepared.
1-20. Describe in detail all plans prepared by licensee or considered by licensee to protect the public and the environment from radioactive contamination, in the event of a major hurricane, failure of the steam generator storage building, rupture of seals or casings of stored steam generator assemblies, and immersion of those assemblies in salt water.
1-21. Describe in detail how licensee intends to dispose of all solid radioactive waste generated during the repair project in the event that all waste disposal sites that receive radwaste from nuclear power plants are closed.
1-22, Describe in detail how licensee .intends'o dispose of defective steam generator assemblies, in the event that'icensee is prohibited-from or decides not to store such assemblies onsite as proposed in the SGRR. For any disposal method stated, provide~
A. The amount of occupational exposure that will be incurred, task by task for the method of disposal to be used.
B. The amount of time that will be required.
C. The cost breakdown for all aspects. of the disposal method.
D. The location of the ultimate disposal site the assemblies will be transported to.
E, The form of transportation that will be used.
1-23. State under what conditions is cooling water from the cooling canals allowed or permitted to be directly discharged into Card Sound.
1-24. Does licensee contend that water, chemical effluent, and liquid radioactive waste contained in the cooling canals does not reach Card Sound or Biscayne Bay other than through controlled releases to the Card Sound canal?
A. If so, state why.
B. If not, why not?
1-25. What study, research, analysis, measurement and, testing has licensee made to assess the potential impact on the environment, including all life forms present, of all forms of pollution generated as a result of construction activities and materials for the proposed steam generator repairs, construction of the steam generator storage building, and installation and construction of buildings to house the condensate polisher demineralizer system. Provide all data, calculations, and all reports, studies, memorandum, and any forms of correspondance used. in making such an assessment. If no assessment has been made, state why not.
1-26, Has licensee assessed the potential impact on the environment and all its life forms of the cumulative and synergistic effect of pollution generated as a result of the combined construction activities and materials for the repair project, additional levels of effluent from installation of the condensate polisher demineralizer
system discharged into cooling canals, further radioactive releases during repairs and upon resuming reactor operations, and the residual
,concentrations of radioactive nuclides already present in the environment as a result of plant emmission or discharge. Provide all records, data, and calculations and documents considered in making any such assessment, If no 0%
assessment has been made, state why not.
1-27. State whether or not there are any endangered species, as listed in the Federal Endangered Species Act, living onsite or in the vicinity of Turkey Point. If so:
A. Identify the species present'."
B. The numbers of each species present.
C. Describe the location and nature of each species habitat.
D. Describe in detail any plans prepared or considered by licensee which insure any endangered species present are not threatened or their habitat endangered by any aspect of the steam generator repairs or installation of the condensate polisher demineralizer system.
E. If any species are present, state why potential impact of the repairs on them was not addressed in the SGRR.
1-28. Has licensee assessed the potential impact of the repairs on the surrounding communities, as to:
C A. The effect of an influx of transient. workers.
k B. Any increased demand on services both public and private.
C. Effect on traffic in the area.
D. The effect on the availability of housing during the farming season when large numbers of migrant workers are present.
E. Provide any data, reports, and calculations used to make any such assessment,
1-29. Describe in detail any assessment made by licensee of the environmental impact of.'roviding replacement'ovrer during the repair outages at Turkey Point by reactivating decommissioned fossil fuel plants If none has been made, provide such an assessment, to
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inc iud e:
A. Which generating plants will provide replacement power their location ".md capacity, .and the fuel used to generate electricity
- 3. An assessment of such plants potential for environmental degradation from thermal, air, and water discharges C. The effects of'he use of'onrenewable fuels on cost, and availability of energy supplies.
D. Whether such plants are, fitted with doub 1 e im j ec tor fue 1 systems to allow f'r i the burning of o 1 or gas, lf so, whi ch E. The generating capacity for each plant
~
P ~ The amount of replacement power each plant will provide during the outage for repairs .
G. The service area f'r each plant H. The effect of recommissioning on employement in the area I . A compl ete cost analysis for the recommissioning of any plants, and for any plant providing replacement power a cost analysis for its operation during the outage time . Specif iy the date used for establishing costs of r ecommissioning and operation Z. If any of the above inf'ormation is contained in already I
prepared reports or other documents, pl ease provide such documents and reports ~
l-30. Provide a complete cost analysis of the steam generator repairs and the instal lation and- housing of the condensate polisher demineralizer system based on 1979 cost data for all aspects of the pro ject.
l-3i. State the methods which licensee intends to employ to raise
)
capital to finance the steam generator repa'irs and installation of'he condensate polisher demineraliser and for replacement power during the repair outages.
A. What will be the interest rates on loans made by licensee to obtain capital financing7 B. What will be the costs for bonds used to obtain capital' C, Did licensee ascertain the effect the, cost of the proposed proj ect will have on the availability of capital. If so, what will be the effect.
1-32. Does licensee intend to pursue a rate increase from the Public Service Commission of the State of Florida as a result of the project to repair the steam generators'? Provide data and calculations on any plans to increase rates to consumers based on the repair cos s, or any other costs related to the repair project.
1-33. Provide a cost analysis of the costs to operate Turkey Point nuclear reactor units 3'&; 4.
1-30. Provide details on:
A. The total generating capacity of Turkey Point units 3 0 4.
B. Licensee's total generating capacity.
C. The total amount of electricity sold, and the amount of electricity supplied by units 3 5 0 for those sales.
D. Iicensee's pricing and rate structure for the sale of electricity.
E. Any contracts for the sale of electricity to any other public utility. Include the amounts of electricity contracted for.
F. Any demand/need estimates, predictions or studies through the year 2000 A.D.
G. All previous unit 3 h 0 shutdowns.
H. Costs of all previous shutdowns and for all other
major maintenance repairs.
1-3$ . Describe in detail any planning, research, consultation, and any other study which licensee has made, is making, or will make in the future for implementing conservation measures and/or technologies other than nuclear for the generation of electricity as alternatives
- to the proposed;Z;epairs of the steam generators, or as alternatives for future generation of electricity. Include:
A. The division or department at PPL responsible for conservation planning and for alternative technologies.
B. Any firms, corporate or otherwise, providing consultation or design information on conservation and any alternative technologies.
C. The. person or persons responsible for and, most knowledgeable about conservation measures and alternative tectuzologies. Provide their names, addresses, telephone numbers, and their job titles.
D. With regard to conservation measures, state:
(1) All plans to develop consumer incentives to encourage conservation of electricity. Provide any reports, data or documents used, in consideration of any plan.
(2) The amount of energy savings that would accrue were any conservation plan to be implemented. Provide data and calculations on any such analysis.
(3) Details of any proposals made to either the Federal Department of Energy or the State of'lorida agencies having authority.
E. With regard, to alternative technologies for generating electricity, state:
(l) Any plan, research or study concerning the implementation of solar photovoltaic cells for the generation of electricity.
(2) Any plan, research, study and report considered. by licensee for implementing the generation of electricity by production
of'ethane.
(3) Any plan, research, study, or report considered by licensee for implementing the generation of electricity 'by the production and combustion of hydrogen.
(0) Any plan, research, study, or report considered by licensee for implementing the generation of electricity through the development of".Ocean -Thermal Energy Conversion.
(5) Any plan, research, study, or report of any other alternative technology for the generation of electricity presently under consideration, or that has been considered by licensee.
F. Does licensee have under consideration any plan for aiding consumers to finance the purchase and installation of solar hot water heaters. If so, provide details.
G. For any conservation plan or alternative technology under consideration by licensee state the amount of research funds and development funds expended for each in the last ten years and the amount budgeted for each f'r the next ten years.
l-36. State whether or not licensee is presently obligated to any contracts for the steam generator repairs and installation of the condensate polisher demineraliser system, to include, but not limited to, contracts for:
A. Materials.
B. Labor.
C. Component fabrication and. construction.
D. Engineering and design.
E. Remote tooling and other equipment.
- -'-Z. 'Replacement f'uel.
If'o, provide a copy of any such contracts.
Contention 2 2-1 7ihat are the tasks involved in the preoperational testing program for placing a unit back in service with modified steam generators 7 2-2 '>7hat w. 11 be the radiation intensity fields for each
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of the following tasks:
a Unload entire'ore.,
- b. Survey containment work areas, perform local decontamination, and shield areas where necessary.
- c. Install cover over the reactor cavity to provide protection to the reactor vessel and associated eouipment and to provide a contiguous work area.
- d. Assemble special prefabricated scaffolding to permit access to all work areas.
- e. Remove biological shield wall and transport debris from the containment.
- f. Remove. insulation from steam generators, feedwater piping, steam line piping, reactor coolant piping, and other components and transport debris from the containment.
- g. Install local control structures, such. as tents, ducting, temporary filters, etc.
- h. l..stall the steam generator transport system, e.g.,
rails, inside the containment and on ecuipment hatch.
- i. Enlarge and/or reinforce ecuipment hatch platform outside of the containment.
Inspect and test containment polar crane.
- k. Remove miscellaneous small piping, such as blowdown piping, and instruments and controls, such as level transmitters, to facilitate removal of the steam gen-eratois.
- l. Cut steam line piping at the steam nozzle on the upper'hell and downstream to allow a section .of'he piping to be removed so that the. upper and lower shells can be f'itted.;
- m. Cut f'eedwater piping at its junction with the upper shell'nd upstream f'rom the junction to allow a section oZ the piping to be removed so that the upper and lower shell can be removed.
rl. Cut and remove reactor coolant in'et and outlet piping. A section of'he hot leg(inlet) piping (an elbow) will be removed by cutting the pipe at the steam generator nozzle and on the outlet side of'he reactor coolant system isolation valve.. A larger section of'old leg .
(outlet) piping, consisting of two elbows and two straight section's, will be removed by cutting the pipe at the steam generator nozzle and upstream f'rom the reactor coolant pump.
- o. Cut steam gend'rator wrapper and internal blowdown piping to f'acilitate lif'ting of'he upper shell.
- p. Cut steam generator shell on the transition cone.
- q. Lift off the upper shell of the steam generator with the polar crane and store in the containment.
r..Inspect and remove moisture separation equipment, feedring, and other associated equipment.
- s. Disassemble and/or remove the steam generator
~ I supports to allow the lower steam generator assembly to be. lifted by the polar crane.
- t. Lift the steam generator lower assembly from its supports using the polar crane.
- u. Remove the steam generator lower shell assembly from the containment through the equipment hatch.
- v. During removal and thereafter, clean and decontaminate the containment work area to the extent practicable.
- w. following the transport of the steam generator lower" assemblies through the ecuipment hatch, remove them from the ecuipment hatch platform by means of mobile cranes and transport them to an interim storage location.
- x. Remove cutaway pipe sections from containment.
- y. Dispose of steam generator.
- z. Deliver replacement steam generator lower assembly by barge.
aa. Lift, the steam generator lower assembly from the transporter onto .the eouipment hatch p"atform by means of mobile cranes. Dove it through the equipment hatch and into the containment using the containment transport sys'em.
bb. Transport the assembly to a designated location within the containment and upend it using the polar crane. Lift the assembly vertically and move it to a position over the steam generator supports. Lower the assembly into place over the supports. Temporary positioning devices (e.g., jacks) may be installed to facilitate the positioning of'he lower assembly without the use of a polar crane.
cc. Peassemble and/or reinstall the steam generator support system.
dd. Install new moisture separation ecuipment, feedring and other internal components in the upper shell.
prepare mating'urface of upper shell for welding to lower assembly.
, ee. Lift upper steam generator shell into place and align with lower assenbly. Temporary positioning devices may be used to facilitate alignment without the use of the polar crane.
ff. ",leld the upper and lower assemblies together, stress-relieve, and inspect.
gg. Yield the steam generator wrapper to tPe upper internals and inspect.
hh. Install the reactor coolant piping.
ii. Fitup weld and inspect the main st am piping.
Fitup, weld, and. inspect the feedwater piping.
kk. Install miscellaneous piping (e.g., blowdown) instrumentation and controls which were removed.
ll. Construct biological shield wall, repair crane wall and other concrete structures that were chipped,.
mm. Clean affected systems and work areas.
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nn. install insulation.
oo. Remove scaffolding.
pp. Remove cavity cover.
qq. Reload core.
rr. Radiation survey mentioned at 5 2.6.1.1 of NRC Safety valuation Report.
ss. Local decontamination mentioned at 5 2.6.1.1 of NRC Safety Evaluation Report.
tt. Removal of sections of containment internal structures mentioned at 8 2.6.1.1 of NRC Safety Evaluation Report.
uu. Rove steam generator to storage or cutup facility deposit and seal facility..
vv. Monitoring of steam generator in sealed storage facility for about SO years ww. Each of the tasks described in answer to I
interrogatory 2-1. C xx. Disposal or decontamination
~a of temporary shielding.
yy. Yiaiting in low background radiation areas.
zz. Ingress and egress to work location.
2-3 For each of'he tasks listed in question 2-2, describe how each radiation field intensity rate was computed, providing:
- a. Isotopical nature of'he material.
- b. Qzaritity of radioactive material.
- c. Nature of emitted radiation.
- d. Nature of the shielding between the source and the receptor.
e.. Geometry (e.g. distances and dimensions).
Intensif'ication due to high temperatures, volatization, and particulate suspension.
xposure rate (3/hr).
2-4 For each of the tasks listed in cuestion 2-.2, please list:
- a. The number of'imes monitoring measurements were taken for computing field intensity rates.
- b. The dates on which monitoring measurements were taken for computing field intensity rates.
- c. Hach measurement.
. d. The location of'ach measurement device.
I'.as the L'icensee made future projections ofield intensity rates for any of'he tasks listed in question. 2-2 7 2-6 If'he answer to question 2-5 is yes, describe for each projection:
- a. The task.
- b. The projection date.
- c. The projected field intensity rate.
- d. The procedure employed for determinig the rate.
2-7 Descry,4p the procedure k
and provide calculations and data for determining the radiation field intensity rate reductions that will occur due to water being kept in the steam generators, for each item listed in question 2-2 to which this procedure is applicable.
2-8 For each task listed in question 2-', where. applicable, describe the shielding'hat will be used for each worker and provide the calcu1ations and data for determining the reduction in radiation intensity fi.elds due to the shielding.
2-9 For each of the tasks described in cuestion 2-2, state the number of workers performing each task.
2-10 For each worker performing a task, as listed in the answer to ouestion 2-9, state the nu~ber of hours that each worker will be performing each task..
2-11 For each worker described in the answer to auestion 2-10, list the total man-rem exposure for, that worker.
2-12 For each of the tasks described in question 2-2, state the total number of man hours recuired for each task.
22>>
2-13 For each task described in question 2-2, state the total man-rem exposure for that task.
2-14 Provide a detailed. explanation, including calculations and data, f'r determining that the post repair operation occupational dose for inspection and repair of degraded steam generator tubes will be reduced to 100 man-rem per year for the two Turkey Point units combined f'r the life of the plant.
2-15 Provide a detailed explanation, including calculations and data, for the assumption that the replacement steam generator tubes will maintain their integrity during the remaining operating lifetime of the plants.
2-16 Provi'de man-rem doses for the inspection and repair o'f degraded steam generator tubes for the years 1974, 1975, 1976, 1977, and 1978 for each reacto'r.
2-17 Has the Licensee established criteria for restricting workers from any tasks listed in question 2-2, based upon the age or sex of' worker 7 2-18 Zf the answer to 'question 2-17 is yes, describe fully the nature of those restrictions,r including a list of each task to which the restriction will be applied and the age group and/or sex that will be restricted from performing that task.
2-19 Describe attempts that will 'oe'ade to screen out radiation workers who may be more susceptible to radiation induced problems,
2-20 For each of the. tasks listed in cuestion 2-2, describe in, detail the prejob planning and the prejob training that will be provided to perform each task, including the number of hours of training that >v~ ll be provided for each worker performing each task, as listed in the answer to ouestion 2-9.
2-21 Describe the procedure 'and provide calculations and data for determining the reduction in man-rem exposure, for each task listed in question 2-2, due to job training and "'ob planning.
,2-22 Zor each task listed in question 2-2, list the reduction in man-rem exposure due to 'ob training and job planning.
2-23 Describe the procedure for hiring each of the workers described in the answer to cuestion 2-9.
2-24 Has the Licensee contracted with any person, either corporate or individual to hire or to provide workers to perform the tasks listed in question 2-2 7 2-25 If the answer to cuestion 2-24 is yes, attach a copy of'hat contract to the answers of th se interrogatories.
2-26 Describe the procedure the Licensee will'use to obtain the reports of'ach worker's previously accumulated occupational doses.
I 2-27 Describe the procedure that will be used to obtain a certificate. or Form NHC-4 from non-english speaking "workers.
2-28 For each task described in ouestion. 2-2, provide an, explMation, with calculati'ons and data, as to how automated tools and ecuipment are to be used in reducing the occupational exposure recuired for cutting, removal, and welding.
2-29 For each task listed in question 2-2, state the reduction in man-rem exposure due to automated tools and. 'ecuipment being used in cutting, removal and welding.
2-30 Specify what is meant by "Some small sections of containment internal structures..." as mentioned in the NHC Safety Evaluation Heport 5 2.6.1;1.
2-31 Describe procedures if the upper assembly of a steam generator fails to mate satisfactorily with the new lower assembly, due to deformation of one of the assembly halves.
2 ID 2 Provide a Health Physics Manual describing monitoring and protection procedures for workers in radiation fields.
I CONTENTION 3 3-1 State in detail the exact steps mhich will be used in (a) handling (b) processing (c) s toring (d) '.'preventing the discharge of the primary coolant during the course of the proposed repairs.
3-2 State the names, addresses and telephone numbers of each person employed, retained or consulted by the licensee in preparing the plans for handling, processing and storing the primary coolant.
3-3 State the educational background of each of the persons
-listed above.
3-4 Identify the documents utilized by each of those persons in preparing the plans for handling, processing and storing the primary coolant.
3-5 Did any of,the persons named above disagree, to any extent, with the method ultimately decided upon by the licensee for the handling, processing and storing of the primary coolant during the course of the proposed repairs~
3-6 Xf so, please state: (a) the names of each of those persons, and (b) the bases for their differences of opinion with the, submitted plan.
3-7 State in detail the exact steps which mill be used to monitor the release of laundry waste water during the proposed repairs.
3-8 State in detail the exact steps which will be used to measure the amount of radioactive material in the discharged laundry waste water.
3-9 State the names, addresses and telephone numbers of each pexson employed, retained or consulted by the licensee in establishing the methods for monitoring the release of laundry waste water and measuring the radioactivity of the material in that water.
3-10 State the educational background of each person listed above.
3-11 Identify the documents utilized by each of those persons in establishing the methods for monitoring and'easuring.
3-12 Did any of the persons named above disagree, to any eztent, with the method ultimately decided upon by the licensee for the monitoring and measuring discussed above~ If so, please state -their names and the bases'of their differences of opinion+
3-13 State the method by which it was determined that any release of radioactive material during the handling, processing, storing or discharging of the primary coolant, or the discharge of laundry waste water will be as low as reasonably achievable within the meaning of 10 CTR, Parts 20 and 50.
3-14 State the names, addresses arid telephone numbers of each pex'son employed, retained or consulted by the licensee in making those determinations.
3-15 State the educational background of each person listed above.
3-16 Identify the documents utilized by each of those persons in making determinations regarding the level of radio-activity that will be released.
3-17 Did any of the persons named above disagree, to any extent, with the method ultimately decided upon by the licensee for the monitoring and measuring discussed above~
If sc, please state their names and the bases for their differences of opinion.
C 3-18 Specify the volume of primary coolant, in liters present in;
- a. Unit 3..
- b. Unit. 4.
3-19 Provide calculations and data for determinig the amount of primary coolant to be drained, for steam generator repairs, from
- a. Unit 3.
- b. Unit 4.
3-2O For the storage tanks that will be used to store primary coolant during steam generator repairs state:
- a. Tocation of each tank.
- b. Safe. capacity for each tank,
- c. Composition of tank wall of each tank.
- d. Y(all thickness of each tank.
- e. Description of any additional biological shielding for eeich tarQc.
3-2l Provide calculations and data used to determine the radiation. intensity field (R/hr) on. the outside surface of each tank'.storing primary coolant.
3-22 Provide. current FSAR (NRC approved) practices for storing primary coolant.
3-23 Provide current FSAR (NRC appioved) practices for discharging primary coolant.
lf primary coolant is to be discharged, for each filtering and/or decontaminating device, 'pecify:
- a. Name of device.
- b. 1Kanufacturer.
c I",odyl.
- d. Capacity e Zficiency Number of devices used, per unit.
Specify amount of radioactivity, in curies, for all isotopes that will be, present in discharged primary coolant:
- a. Provide half-life of, each isotope listed.
t
- b. Provide calculations and d'ata.
For the primary coolant presently in unit 3, provide:
a An inventory of'll isotopes.
b Amount. of radiation, in curies, for each isotope.
c Falf-life of each isotope.
- d. Date measurement was recorded.
e Time interval between last operation -of unit 3 and date isotopical measurement was taken.
For the primary 'coolant presently in unit,4,- provide:
a An. inventory of all isotopes.
- b. Amount of radioactivity, in curies, for each isotope.
c.- Half-life of each isotope;..
- d. Date measurement was recorded.
- e. Time interval between last operation of unit 4 and date isotogical measurement was taken.
If answer to question 3-9, d, is a date prior to June 1, 1979, provide answers to cuestion- 3-9 for primary coolant as of October 22, 1979.
If answer to question 3-10, d, is a date prior to June 1, 1979, provide answers to ouestion 3-10 for primary coolant as of October 22, 1979.
/~
Provide calculations and data for a projection of radioactive isotopes in primary coolant as 1, 1979, specifying: of'eptember
- a. Inventory of all isotopes
- b. Amount of, radioactivity, in curies, for each isotope.
- c. Identification of each unit for the projection.
For unit 3, since January 1, 1975, for all new fuel rods, specify:
- a. The number of types, of fuel rods having different 4
isotopical makeup
- b. An isotopical inventory for each type of fuel rod.
1
- c. The amount of radioactivity, in curies, for each isotope.
- d. The half-life of each isotope.
- e. The number of fuel rods, of each type, used.:..
I E r
3 For unit 4;. since r January =1, 1975, for all new fuel
" rods, specify: '
a..The number of types, of fuel, rods haying different rr isotopical makeup.
b., An isotopical inventory for each type of f'uel rod..
- c. The amount of'adioactivity, .in" curies, for each I
1'sotope o r
d.. The half-life of'ach isotope.,
- e. "The number. of fuel rods, of each type, used.
3-33 For unit. 3; since January 1, 1975, for all.burned up-fuel rods extracted, specify:
a.'he=number of types, of fuel rods having different iso topic al makeup.-
=
'r b, An isotopical inventory for each type of fuel rod.
- c. The half-life of'ach isotope.
- d. The amount'f radioactivity, in curies, for each isotope.
'e.. The number- ofuel, rods of each type, extracted from unzt 3.
~ ~
3-34 For unit 4; since January 1, 1975, for all burned up fuel rods extracted, specif'y:
a The number of'ypes, of'uel rods having dif'ferent
~
isotopical makeup..
b..An .isotopical invent'ory for each. type. of fuel rod.
~,
- c. The half-.life of'ach isotope.
amount of radioactivity, in curies, for 4
The each
,isotope.
,e'.. The number of fuel rods of each type, extracted
.from unit 4
Contention 6 a Shat specific standards set out in 10 CFR Part 20 .
~
and 10 UFR Part 60 does Licensee contend were considered in the Steam Generator Repair Report; (SGRR) and the Final Safety Analysis Report (FSAR) concerning the integrity of. the steam generator, storage facility ?
- b. Identify, specifically, where such standards stated in question 6-1, a, were considered in .the SGRR and FSAR
- c. Ykhat is the name, title, employer, and educational of'he background person, or persons, who drafted the specific sections, of'he SGRR mentioned. in question 6-1, b 7
.d State all documents, papers, research reports, and testimony relied upon by the draft'sman of'he sections qf the, SGRR mentioned. in ouestion 6-1, b.
- e. Give the name, title, employer, and educational background of the person, or persons, who wrote .and.
researched each item listed in answer to question 6-1, d.
6-2 a Does applicant contend that the SGRR adequately outline the. specifics of the storage facility and
'emonstrate the facility's compliance with 10 CFR Part 20 as it relates to the possibility of radioactive
/ 1 releases into unrestricted areas," as advanced .in Contention 6 7
P
-34
.b. If yes, state the specif'ic sections of'he SGRR that do in fact adeauately cover the questions raised in this contention and snow compliance with -10 CFR Part 2Q.
- c. State. the name, title, employer, and educational.
background of'he person or persons who wrote this section of'he SGRR mentioned in 6-2, b d State. all documents, papers, research reports, and testimony relied upon by the draftsman of'he sections mentioned .in 6-2, b e.. Give the name, title, employer,. and educational background of'he person, or persons, who wrote and J
researched. each i,tern listed in 6-2, d.
- a. Does Iicensee contend that the SGRR adequate+
outlines the specif'ics of'he storage f'acility and demonstrates the f'acility's compliance -with 10 CL'R Part 20 as it relates to the possibility of radioactive releases which are not as is reasonably achievable 7 b State the. specific sections of'he SQRR that do, in fact, adequately cover the oue8tions. raised in contention 6 and show compliance with 10 CFR Part GO.
- c. State the Name, title, employer, and educational background of'he person, or persons, who wrote the sections'of the SGRR mentioned in question 6-3, b.
- d. State all .the documents, papers, research reports and testimony relied upon- by the draftsman of the sections mentioned in cuesCion 6-3, b.
- e. 'State the name, title, employer, and educational background of tha person or persons who wrote and resea.ched each item listed in question 6-3, d 6-4 a<<'ist '.all sactions and titles of reports and papers wherein the: Licensee considered substantial immersion of the steam generator lower assemblies ia sea water, for each grade of grade one through five hurricanes,
.respectively.
- b. State the name, title, employer, and educational hac3cground of the person, or persons,. who wrote and researched each item listed in question 6-4, a.
c State all documents, papers, research reports, and
'testimony relied upon by the draftsman of'he sections mentioned in 6-4, a.
d" State the name, title, employer., and educational background of the person, or persons who wrote and "
researched the items listed in 6-4, c.
6-0 a. est all sections and titles of reports and papers where the Licensee considered movement of the steam generators, while immersed in sea water, during each
-36>>
grade hurricane.
b State the name, title, employer, and educational background of'he person or persons who wrote and researched each item listed in 6-5, a.
c State all documents, papers, research reports, and
~
testimony relied 'upon by the draftsman oi'he- sections.
mentioned in 6-5, a.
d State the name title, employer, and educational
,background. of'he person, or persons who wrote and
/W researched the items. in 6-5, a.
- a. List all sections and titles of'eports and papers where the Licensee considered the impact of'uch .
moving steam generators upon the walls of'he storage structure, or upon another object or objects
- b. State. the name, title, employer, and educational background of the person or persons who wrote and researched each item listed in 6-6, a.
- c. State all documents, papers, research reports, and testimony relied upon by. the draftsman of the sections mentioned in 6-6, a.
- d. State the name, title, employer, and educational background of the person, or persons, who wrote and 1 researched the items listed in 6-6, c.
<<37>>
- a. List all sections and titles of reports and papers where the Licensee considered corrosion of steam generator lower assemblies in the storage facility as a result of moisture, sea water, condensation, or
- salt spray.
- b. State name, title, employer, and educational background of. the person, or persons, who wrote and researched each item listed in 6-6, a.
- c. Stake:hll documents, papers,, research reports, and
'estimony relied upon by the draftsman of the sections mentioned in 6-6, a.
d State the name, title, employer, and educational background'f the person, or, persons, who wrote and researched the items listed in 6-6, c.
- a. List all sections and titles of reports and papers wherein the Licensee considered leakage containing radioactivity .through the earthen floor of the storage facility b State the name, title, employer, =and educational background of the person, or persons, who wrote and researched each item listed in. 6-7, a.
- c. State all documents, papers, research reports, and testimony relied upon by the draftsman of the sections mentioned in 6-7, a.
I Cf
- d. State the name, title, employer, and educational background of the person, or persons, who wrote and researched the items listed in 6-7, c.
6 9 a. State the documents where the Licensee considered a breach of the integrity of the storage facility and the environmental consecuences of such a breach.
b.. State the name, title, employer, and educational background of'he person or persons who wrote and resea>'ched each item listed in 6-8, a
- c. State all documents, papers, research reports, and
. testimony relied upon by the draftsman o the sections mentioned in 6-8; a..
d.. State the name title, employer, and educational background of the person, or persons, who wrote and researched the items listed in 6-8, c.
Provide names and job titles =-of'ersons responsible f'r submitting f'inal design for Licensee!s steam generator storage f'acility.
Provide guidelines f'oIIowed in designing steam generator storage facility Specify distance f'rom ground surface to ground water table at steam generator storage facility site:
a Lt. mean high water.
b ~:mean, Iow water Specify porosity of ground under steam generator storage facility site.
If. immersed in salt water, will sealed steam generator lower assemblies f'loat 7 Produce blueprints f'r the'steam generator storege facility Describe the f'unction of'stop logs" Describe the nature of'top logs specif'ying:
a Their material composition b The dimensions of'ach. stop log.
c The breaking strength of'ach stop log.
- d. The method used to af'ix each stop log in place
- e. The breaking 'strength of'ach fastener holding stop, logs in place.
'I Describe the roof'f the steam generator storage facility specifying:
- a. Xt's composition.
,b. The support geometry.
c Zt's breaking strength at center point.
- d. The methods and materials which will afix it (roof) to the walls.
e . The methods and materials which will afix it (roof) to the.stop logs.
The breaking strength of the fastenings between.
the roof'nd the stop logs.
Specify the distance between the proposed sto age facility site and the closest shoreline point of'outh Biscayne Bay at. mean'high water Describe the process for placing the steam generator
~
lower assemblies in the steam generator storage facility.
a What device will lift the lower assemblies off the transporter 7 b What device will positiofi the lower assemblies in the steam generator storage facility'7
- c. What portions of the steam generator storage facility will remain uncompleted while lower assemblies are. being delivered and positioned 7
- d. )Yhat is the proposed time interval (in days) between the delivery of the first steam generator to the storage fhcility and first complete closing of the facility with all stop logs and roof 'in place 7
- e. Specify the distance between the floor of the storage facility and the inside ceiling of the storage facility Specify the distanc'e betw'een the top of the in portion steam generator and the inside ceiling.
6-2Z. Describe the provisions for the collection inside the steam generator storageof'ondensation facility.
Provide the calculations and data demonstrating the rate that water would flood into tne storage if facil'ity a storm surge measuring 18'bove msl were to occur at the Turkey Point Site.
A 6-28 Describe the means of anchoring steam generators in place, in the storage facility..
6-24 Describe the m'ethods that. will be employed to inhibit corrosion of the. seal welds while the lower assemblies are in the s orage facility.
6-25 Specify the composition of the plates sealing the ends of the lower assemblies.
6-26 Specify the. composition of the lower assembly ends to which the, seal plates wi.'ll be welded.
r 6-27 Provide calculations and data describing %he consecuences affecting the seal weld plates of a postulated drop of a lower assembly off' transporter 6-28 Provide a survey of all isotopes present in the defective steam generators..
a'pecify the amount of each isotope, in curies,
%chas been deposited. in each lower assembly.
b Specify the amount of each isotope, in curies, that, is present in the stzucturaI members of the the. lower assembIy due to neutron radiation.
6.-29 Specify the date .by which the steam generator lower assemblies will be removed from the Turkey Point site, after the long term. storage period.
Spec ify what radio active mat erials will be stored, in addition to the lower assemblies,. in the storage fac 3.13.ty a Specify what radioactive materials wilI be stored in the: storage facility, after the lower assemblies have been removed.
.Specify the data (month and year) the steam generator storage facility will be removed from the turkey point site.
Provide calculations and data demonstrating the number"of'urricanes that are likely to strike the Southeast 1'lorida coast, During the 0ime the steam generator stox'age facility will be storing radioactive materials.
Provi'de calculations and data demonstrating the number of maximum probable hurricanes that are likely to strike the Southeast Florida coast, during the. time- the. steam. generator storage facility will be storing radioactive material.
6 Provide calculations and data demonstrating the integrity. of the earthen foundation to the steam generator storage facility, in the event of a 1
maximum probable hurricane striking the Turkey Point site.
6-36 Specify the three nearest sites of ground water use to the. steam generator storage facility stating:
- a. Locat'ion of each site
- b. Distance of. each site from the storage facility.-
- c. Direction of each site from the storage facility.
- d. Particular use of ground water at each site.
44-CONTENTION 7 7-1 What is a full-flow condensate polishing de-mineralizing system?
7-2 Who manufactures such systems? (including addresses) 7-3 What are the estimated costs of such systems?
7-4 Who installs such systems?
7 5 Plwdse state the places in which such systems are presently in use and describe any operating problems occurring in those places.
7-6 Identify all documents which explain the operation and use of such systems. =
7-7 What are the estimated costs of installation of a full-
=
flow condensate polishing system?
.7-8 Is any data available concerning the repair needs of such a system? If so, please identify that data and summarize 7-9 State the names-, addresses and telephone numbers of all persons who have been consulted, employed or retained by the licensee for the purpose of determining the need and utility of such a system.
7-10 Did any of those persons recommend against the need for and use of such a system'? If so, please state their names and, the reason for their advice.
7-11 Has any estimate been made of the effluent release or environmental degradation caused by a full-flow condensate polishing de-mineralizing system?
7.-Z2 Xf'o, please. state the names, addresses and telephone numbers of the persons making those estimates and those estimates.
7-Z3 Did the Licensee conduct a water analysis of'heir present water chemistry to see if the. demineralizing system was needed 7 7-14 ('lhat chemicals or elements will such a system take out of the water and put back into the water '?
l 7-15 Produce the purchase. agreement for the demineralizer.
and other new water chemistry support equipment.
7-16 Specify location for demineralizer and support equipment for unit no. 3, and;
- a. Unit no. 4 r
7-17 Produce contract for oot"iuxng work force for installing demineralizer.
7-18 Provide specifications for the facility housing the demineral'er. and new support equipment 7'-19 Specify chemical composition of all effluent Xor each recharge cycle, for each unit.
7-20 Specify amounts of each chemical composition as requested in question 7-19.
7-21 Specify volume discharge amount per recharge, per unit.
7-22 Specify number of recharges per unit, per year.
~ lI
7-23 Produce a National Pollutant Discharge Elimination System amendment or permit authorizing demineralizer
'effluent.
7-24 Provide calculations and data demonstrating the effect of demineralizer effluent on the cooling canal biota for the projected life of the plant 7-25 Provide data and calculations demonstrating the effect of demineralizer.effluent on, the biota found within one mile of the junction of the Card Sound Canhf. and Card. Sound 7-26 Provide costs associated with personnel maintaining and operating demineralizer on a yearly basis, per unit.
7-27 Provide analysis of salinity and suspended solids rates of cooling canal water after:
- a. One year's operation of demineralizers for units 3 and 4.
- b. Thirty years operation of demineralizers or units 3 and 4.
7-28 )that is the percolation rate of water containing demineralizer effluent through:
a., The, bottom of the cooling canals-b The sides of the cooling canals.
Contention 9-1. List all procedures for monitoring, surveillance, measurement and testing used by licensee and/or its agents.to determine levels of radioactivity in the'impact environment resulting from airborne or solid waste emissions and liquid waste discharges from the Turkey Point nuclear power plant.
A. Describe in detail all such procedures used.
B. The frequency with which all such procedures are employed.
C. The date of the most recent employment of any procedure listed, to measure concentrations of radioactivity in the environment.
I D. The locations where all monitoring procedures are employed,
-samples taken, and. measurements made.
E. The person or persons or corporate entities who have conducted all such monitoring, measurement,. and testing procedures, including all those who are under contract with. licensee to perform such functions, or who perform such functions under the authority of the State of Florida.
(1) Identify all such persons or corporations by name, address, telephone number and job title.
(2) Provide where applicable the contracts under which all such persons, or corporations conduct monitoring procedures.
F. Provide all reports, surveys, memorandum, letters and any other correspondance which contains the data or test results of all monitoring, -surveillance, measurement and testing done since Turkey Point began nuclear operations.
9-2. List by radioactive isotope and/or nuclide all cumulative residual concentrations of radioactivity which persists in the environment as a result of airborne and solid waste emissions and liquid waste discharges from Turkey Point. For each isotope or nuclide
listed state:
A. The amount of radioactivity measured.
B. Its half-life.
C. Its location in the environment.
D. Attribute its presence to which form of release.
E. Describe its probable effect on the life forms in the environment and on human health and the manner in which it may impact on human health.
9-3. State whether .residual concentrations of radioactivity from
\
airborne, liquid,and
~/. solid waste releases from Turkey Point have been
'.measured on or in:
A. Any vegetable crop grown inSouth Dade county area.
B. Any fruit harvested in the area.
C. Any catch of marine life for human food, or in any organisms which are part of the food chain for marine life used for consumption by humans as food.
D. Any dairy product produced in the area.
E.- In meat from livestock raised in the area.
F. In drinking water supplies, both of well and municipal nature.
In human mother's milk.
H. State whether licensee or its agents have conducted any- such testing.
I. If radioactivity has been found on or in any substance listed in 9-3 A-G, please list:
(l) the radioactive isotope and/or nuclide present.
(2) The substance sampled.
(3) The half-life.
(0) The date sample was taken.
~ t
$9 r~
(5) The person or corporation making the measurement.
(6) The location the sample was obtained.
(7) Provide all reports, surveys, memorandum, letters, or any other correspondence which contains date, teat results, and.
calculations of al'1 such monitoring, surveillance, testing or measurement conducted since Turkey Point began nuclear operations.
Using the procedures in Regulatory Guide 1-109, specify the amount of radioactivity in curies that may be released from each of the following sources:
A. The operating reactor.
B. The reactor buildings.
C; Steam generators in transit.
D. Gaseous emissions.
- Z. Construction dust.
F. Airborne particulates.
G. Cooling canal water.
H. Decontamination liquids.
I. Liquid construction effluent.
Laundry wastes.
K.. Primary coolant.
L. Processed primary coolant.
M. Stored. primary coolant.
N. Fuel movement.
- 0. Spent fuel movement.
P. Spent fuel pits.
Q. Resins.
R. All filters.
S. Plant-wide run L off.
T. Secondary coolant.
U. Storage tanks.
V. Ducts.
N. Radwaste building.
X. Concrete.
Y. Tools.
Z. Clothing.
BB. Protective shields.
CC. Nor/.envelopes.
DD. Clean rooms.
EE. Postulated work accidents.
FF. Postulated spills.
9-5. Describe the procedures that will be taken to insure the residual radioactivity on/in the steam generator lower assemblies will be insoluble.
9-6. State the estimated quanity of residual radioactivity in the lower assemblies. I A. State the type of residual radioactivity in the lower assemblies.'stimated.
B. State the quantity of removable radioactivity in the lower assemblies.
C. State the type of removable radioactivity in the lower assemblies 9-7.'escribe disposal methods for removable radioactivity in the lower. assemblies,.
9-8. Show calculations and data that demonstrate the amount of radio-
t'ctivity'n curies; in. each; lower assembly.
v 9-9., State method. of. derivation of: decontamination estimates given for
'.. Mixed bed demineralizer.
B. Boric acid, recovery process.
9-10. State the total. volume of primary coolant, per reactor to be:
A.. Stored. and reused.
B.. Processed and. discharged.
9-11. State the fate of the drained primary coolant.
9-12. Nhat is the nature of the ground water within one mile of the plant?
9-13. Nhat is the depth of the groundwater below the plant' 9-14. State method of. calculations of radioactivity in primary coolant based. on 1976 sampling.
9-15. Show calculations and data demonstrating how radioactivity in primary coolant would change since 1976.
r 9-16. Ylhat types of airborne radioactivity are HEPA'ilters unable to eliminate' '
9-17. Nill the plant purge system be operating during all phases of the repair using plant, purge filters'f not, why not'?
9-18. Nill mi'sters be used in front of all HEPA filters?
A. -If not, which filters will have misters?
B. If not, which filters will not have misters?
9-19. Nill airborne particulates generated during welding, cutting
,and grinding be totally contained within the work envelope?
9-20. Nill a perfect seal be formed between filter and work envelope'
'9-2i. Nill all lower assemblies be ready for removal from containment before the equipment hatch door is opened and enlarged' A. If not, will cutting operations be permitted while door is open?
9-22. Nhat is the length of time the cut away concrete will be stored at the plant site before being shipped to final disposal.
9-23; Describe nature of storage containers that will be used for cut away concrete.
I Describe handling and disposal of decontamination fluids during repairs.
9-25. Describe handling and. disposal of construction liquid effluent
.during repairs.
9-26. Describe handling and disposal of sludge from lower assemblies during repairs.
9-27. Describe in detail licensee's contingency plan for protecting the environment from radioactive liquid waste contained in the cooling canals, in the event of a major hurricane which floods and overflows the water in the canals' 9-28. Describe in detail licensee's contingency plan for restoring the environment after release of liquid radioactive waste from the cooling canals as postulated in question 9-27.
l I CONTENTION 11 11-1 State the method by which the figure of @00,000 per day per unit for,replacement power costs for reactor outage was determined.
Stat'e the names, addresses and telephone numbers of the persons who were employed, retained or consulted by the licensee to determine that figure.
11;3 Does the licensee still believe that figure to be accurate?
Xf the answer to the above question is "no", state:
believe the accurate figure to be; (b) .the method (a)'hat.you used to arrive at the new figure; (c) the names, addresses and telephone numbers of the persons who determined the new figure.
State: (a) the number of days of estimated outage time; (b) the method of determining that time; (c) the names, addresses and telephone numbers of the persons making that estimate.
11-6 Shat additional land resources will be utilized for the storage of the defective steam generators?
Have you provided any analysis of the economic and environmental costs for the use of the land which will be utilized for the storage of the defective steam generators?
11-8 Xf so, please provide the names, addresses and telephone numbers of the persons responsible for that analysis.
11-9 How long will the building housing the defective steam generators remain on the premises?
11-10 How much will the building cost to construct?
11-11 How much wi" 1 the building cost to dismantle, i.f it is to be dismantled?
11-12 Have. those costs been considex'ed in arriving at the over'all repair costs'?
11<<13 What kind of tubing will be 'used in the condenser x'e-tubing process?
11 Xf titanium is to be used, please state the projected availabili.ty and cost of titanium over the next 30 years?
A 11-15 How much will condenser retubing cost?
11-16 Who provided the estimate of that cost?
11-17 What is the breakdown between cost of matex'ials and of installation fox condenser retubing?
11-18 Please list the names, addresses and telephone numbers of the persons employed, retained or consulted to determine the procedures and the cost'of condenser retubing.
11-19 Who will supply the materials for condenser retubing?
11-20 Please state the prior installations in the United States of condenser retubing and the operating problems which have occuxred .in those priox installations.
11-21, Have any updates of costs been made since the initial estimate for the x'epairs made by the licensee?
I1-22 Xf so~ please state: (a) the names, addresses and telephone numbers. of the persons ma]zing those estimates" and (b) the methods by .which those estimates were made.
~ la lI-23 is
~p Specify whether 8 300,000 a day a purchase price for replacement electricity or a fueI differential.
cost between nuclear fuel and. fossil fuel.
11-24 Specify fuel casts per barrel, as=of November 1, 1979, for:
a Low sulfer oil.
- b. High sulfer oiI Il-25 project fuel costs. per barrel,'or the Fall on 1980, f
- a. Low sulfer oil.
- b. High ox'l-26 sulfer oil.
Produce current contracts, showing oil purchase price.
lI-27, Specify nuclear fuel costs, per fuel cycle, per reactor.
II-28 Produce pre 1979 contract for nuclear fuel with the Westinghouse Corporation.
1I-29 Produce settlement terms of Licensee/',Vestinghouse nuclear fuel sujet 11-30 Specify costs and produce fuel contracts which will be in effect for obtaining nuclear fuel from 1980 to 2000
11-3l If 8 300,000 a day is a fuel differential cost, specify which generating units will supply replac'ement electricity during steam generator. repairs.
11-32 Specify the costs for purchasing 666,000 tuve.
II from the Sou;~heastern Reliability power grid for.:
- a. November 1,, 1979.
b i:al1 1980 (projected).
11-33 Provide a job description, task by task, for the skilled and unskilled labor utilized in the conden er retubing effort.
1I.-34 Provide.'man hours required for all tasks listed in 11-33.
11-35 'pecify amount of titanium required for condenser retubing, in kilograms.
lI-36 a. State specific percentage rate of increase of costs for repairs, fuel, materials, and labor in November 1979, from 1977 estimated. costs of the repair project.
- b. State estimated percentage rate increase for repairs, fuel, mater'ials, and labor from Pall 1979 to Pall 1980.
- c. If 36, a, is different than 11-36, b, state reasons for change and provide calculations.
11-37 Specify all costs for bringing replacement generating electricity plants from cold standby to on-line generation.
Contention 13 13-1 During the repair of the steam generators, describe the monitoring procedures that will'be used including:
- a. Provisions for monitoring workers in multiple radiation fields.
- b. The type of monitoring equipment that will be used.
- c. The use of permanent monitoring systems.
- d. The frequency of measurement for all monitoring equipment and syst,ems.
- e. The areas that will be monitored.
13-2 State the frecuency at which the thermal luminescent dosimeters will be recharged.
13-3. Describe the procedures to be used to measure the accuracy of'he TLDs.
13-4 Describe the procedures that will be used to monitor the daily exposure xates for each wor1-er.
13-5 Describe the procedures that will .be used to maintain a record of the cumulative doses for each worker.
13-6 For handling, processing, and storing primary coolant describe the radiation monitoring procedures, stating;
- a. All locations of the radioactive material.
The location of all monitors in relation to the radioactice material..
- c. Which monitors will be continuously monitoring.
- d. Ylhich monitors will be continuously providing a permanent record of radiation intensity levels.
- e. which monitors will produce an alarm when a specific radiation level is encountered.
- f. The. set point for each instrument named in 13-6, e.,
- g. The name of the person, job title, and telephone number or the. specific location and telephone number where monitoring alarms are guarded.
h The name of the person, job title, and. telephone number who has the responsibility of overseeing this monitoring operation.
13-7 For monitoring the the handling, processing and discharging of primary coolant, state all information requested in question 13-6, a-.h.
13-8 For monitoring the handling, processing, and discharging of laundry waste water, state all information requested in ouestion 18-6, a-h.
13-9 For monitoring releases of radioactivity during the transport of each steam generator lower assembly,-
state all information as requested in question 13-6, a-h.
13-10 For the storage of all steam generator lower. assemblies, state all information as requested in question 13-6,. a-h.
For the handling, storing, processing, and discharging of liquid construction effluent, state all information as requested in question 13-6, a-h.
-60 13'12 For the handling, processing, storing and discharging of decontamination fluids, state all information as requested in question 13-6, a-h.
13-13 For monitoring construction dust during repairs, state.'all information as requested in ouestion 13-6, a-h, 13-14 For monitoring smoke and fumes, state; all information as requested in auestion 13-6, a-h.
13-15 Far monitoring the packaging and transportation of solid waste, state all information as requested in question 13-6, a-h..
13-16 Ear monitoring the storage of solid waste. on site, State all information as reouested in question 13-6, a-h.
13 "17. For monitoring work. envelopes and filter fittings which may leak during construction, state all information as requested in question 13-6, a-h.
13-18 1'ar monitoring radiation that may be released during an accidental fire at the work site, state all information as requested in question 13-6, a-h.
13-19 Describe procedures and eouipment for monitoring ingested radioactivity by all plant personneI.
I
Contention 14 14-1 Specify the experience each member of the fire brigade team has gained, other than in the employment of the licensee, stating:
- a. The amount of firefighting experience.
- b. The location of the firefighting experience.
- c. The mount of firefighting training.
d The location of the firefighting training.
- e. The type of firefighting training.
14-2 a. State the number of individuals presently on the fire brigade team.
- b. How zany of those individuals have received a r
Florida Certificate in Fire Training (200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />).
I4-3 List the fire training procedures implemented at Turkey Point, including:
- a. '<<Yho will conduct, the training of personnel.
- b. Zducational background and cualifications of the trainer.
- c. ',Vhat firefighting procedures are covered.
- d. identify books, documents, and papers used in training by =-Author, title, date of publication, and publisher.
e.. Frequency of training classes.
- f. Total hours of each class;
7
- g. List duties of fire brigade members during:
- 1. Postulated fires.
- 2. Announced fire drills.
- 3. Unannounced fire drills.
- h. Specify freouency of announced fire drills.
- i. Specify freouency of unannounced'ire drills.
Specify if brigade members are trained in first 83.d s
- 1. If so, list areas covered in first, aid training.
- 2. lf so, give educational background and qualifications of trainer.
- 3. lf not, specify regulations or guidelines that permit fire brigade members not to be trained in f3.rst 83.de 14-4 a. List the available exits from the containment building during the repair operation.
- b. Describe t¹ accessability of these exits during the different major repair operations where large workforces will be in the containment.
- c. List approximate times needed to evacuate personnel from containment during repair'perations:
- l. Under normal situations.
- 2. Under emergency situations.
14-5 Will the I/HC regulatios of June 8, 1979 concerning fire safety, brigade size, and training be implemented for the proposed repairs. 7
- a. If so, state name and job title of'erson responsible'or implementing procedures.
- b. Which of the June 8, 1979 regulations will not apply to the repair project.
14-6 >'lill the portable foam. unit be stored inside the containment during the repair effort 7
- a. LYhere will it be located '?
it is P
- b. Describe how transported to a fire location.
- c. How many persons will transportation of the portable foam unit reauire, to move to fire locations.
-d. Will the persons involved in this transportation be fire brigade members 7
- e. If 14-6, d, is yes, describe the duties of the remaining members of the fire brigade team should a major fire exist.
14-7 List all fire extinguishers available during cutting, grinding, and welding operations, including:
- a. Location.
- b. Size.
- c. Type.
d- Range.
- e. Duration of'ischarge..
- f. Weight when fully charged.
g.. Extinguishing agent
- h. Date of last recharge
- i. Travel distance to the containment.
Travel time to the containment.
14-8 Provide information and documentation in answering the. following questions pertaining to the "specially designed envelopes" to .be used when cutting, grinding, and welding. State:
- a. The fire. retardant agents in the material of these envelopes.
- b. The principal material composing these envelopes.
- c. L~<elting temperature of these envelopes
- d. Ignition temperature.
e.. The toxic agents in fumes when ignited..
- f. The potential danger to a worker caught inside an envelope in a flash fire
- g. Procedures for ingress and egress.
- h. Whether a mister will be used on the IPPA filters on these envelopes.
14-9 Describe the dangers of accidental radiation. exposure if a major fire should-encompass a cut steam generator with its internals exposed'tate:
a An inventory of the exposed isotopes.
b- Maximum concentration of radioactivity airborne in containment..
- c. Maximum amount of airborne radioactivity that can pass through a respirator per minute.
14-10 Desex',ibe procedures for venting smoke from envelopes.
14-11 Describe procedures for venting smoke and fumes from containment caused. by:
- a. Cutting welding and grinding ope'rations.
- b. Accidental fire.
14-12 Specify qualifications for fire watch personnel during cutting, welding, and grinding operations.
- a. >Yhat other duties will the fire watch person assume during cutting, welding and grinding operations2
- b. Describe in detail the fire watch procedure.
- c. <gill the fire. watch person'also be a member of the fire brigade team '?
14-13 State the flashpoint of the radiation protective clothing.
- a. Specify the composition of any toxic fumes that 1
may be given off when the radiation protective clothing catches fire.
14-14 State the flashpoint of the breathing apparatus that will be in use during cutting, welding, and grinding operations.
- a. Specify the composition of any toxic fumes that may be given off when the breathing apparatus catches fire.
- b. Specify the composition of any toxic fumes that.
may .b'~ given off when the breathing apparatus melts.
14-15 List the available fire breathing apparatus units available during steam generator repairs. State:
a The type..
b The quantity.
- c. The. capacity.
- d. The'eight.
- e. The size.
- f. The locations where stored.
- g. The travel distance from the various locations to the containment.
- h. The travel time from. the various locations to the containment.
14-16 list all firehose. nozzles available during steam generator repairs. State:
- a. The quantity of. nozzles that can be used inside the containment.
- b. The'uantity of nozzles that cannot be used inside the containment."'.
The locations 'of both. types of nozzles.
- d. The f'low rate f'r each type of'ozzle.
14-17 Kist all firehoses available; during steam generator repairs -State:
a The location of'he hoses.
- b. The quantity of hose at each location.
c- The capacity of'he. hoses.
- d. The pounds of'ressure and f'low rate f'r each hose, with fire water 'pumps operating.
- e. The puunds of'ressure and the f'low rate f'r each hose without the fire water pumps operating.
14-18 Are all hose and nozzle coupling threads interchangable 'P
- a. XX not, state reasons for. not being interchangable.
14-19 Describe the. system of fire. signals in use during steam generator repairs. State:
- a. Locations oi'hones within the containment.
b- I;ocations ofire pull boxes within the containment.
- c. The other methods of reporting f'ires within the containment..
- d. The person or place that receives the f'ire signals.
- e. The procedures that f'o'liow af'ter a f'ire signal has been received.
14-20 Are special suits, for fighting fires containing radioactivity, available at 'Turkey Point '?
- a. List quantities and locations where suits are stored a
- b. Da local fire units assigned to aid Turkey Point, posses. radiation fire fighting suits 7 I; .Zf not, state. reasons f'r negative answer.
14-21 State most recent date the commanders of Fire station. 5 6, 16, and Homestead APB toured Turkey Point.
a What is the frequency of familiarization tours for the commanders of assisting fire stations2 X4-22 State the information and procedures the Licensee has transmitted to the. commanders of the assisting f'ire stations.
I4-23 Do the assisting fire stations have a written plan of'he Licensees fire fighting procedures '?
I4-24 Describe the procedures the Licensee will employ in assisting outside fire personnel once'hey arrive.
- a. What person will coordinate'he fire fighting "effort.
I4-25 State reasons for not, installing a "Standpipe System" within the containments.
14-26 In the letter of'une 6, 1978, from the NRC'to the Licensee it-is s'tated, "All personnel assigned to the fire brigade would have to fulfillalI applicable training requirements ".
- a. State the requirements.
b- How often are they implemented '?
- c. Yfhat portions of the requirements must be fulfilled before an individual can be assigned to the"pire brigade. ~
Respect ully submitted, BRUCE S. ROGOYI JOEL V. LU2ER RICHARD A. MARSHALL) JR.
Counsel for the Intervenor 330? College Avenue Fort Lauderdale, Florida 33314 (305} 587-6660 Richard A hiars 18450 S,Yi. 212th al, Jr.
Street Miami, Florida 33187 (305) 233-8104 Dated at Miami, Florida this+7 th day of October, .1979.
AWr
~ co~
UNITED STATES OF AMERICA NUCLEAR REGULATORY CO~~IMISSION BEFORE THE ATOIJiIC SAFETY AND LlCZNSING BOARD In the matter of ) Docket Nos. 50-250
) 50-251 FLORIDA POVf~R AND LIGHT COMPANY )
(Turkey Point Nuclear Generating ) (Proposed Amendments to Units Nos. 3 an~ 4) )
Facility Operating License to permit Steam Generator Repair}
CERTIFICATE OF SERVICE I FEREBY CERTIFY that copies of "INTERVENOR I~LQK P.
ONCAVAGE'S INTERROGATORIES TO, AND RZQiP~ST FOR THE PRODUCTION OF DOCZfZNTS FROM) LICENSEE FLORIDA POWER AND LIGHT C01'/DP3l
" in the above captioned proceeding have been served on the following by deposit in. the. United States Mail, first class, thisg7~ day of October, .1979.
Elizabeth S Bowers, Esq..
Chairperson Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. Oscar H. Paris Atomic Safety and, Livensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. Zmmeth A. Luebke Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Atomic Safety and Licensing Board PaneI U.S. Nuclear Regulatory Commission Washington, D. C. 20555
I; Atomic Safety and Licensing Appeal Board Panel IJ.S. Nuclear Regulatory Commission Washington, D. C. 20555 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission.
'/ashington,. D. C. 20555 .
Steven C. Goldberg, Esq.
Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D. C. 20555.
Norman A. Coll,. Esq.
STEEL ) HECTOR R DAVIS 1400 Southeast First National Bank Building Miami, Florida 33231 Harold F. Reis, Esq.
Lov<enstein, Nevadan, Reis, Axelrad 8; Toll 1025 Connecticut A'venue, N.W.
)Yashington, D. C. 20036 cd&8 Rxc ard A- Marshall, Jr.
18450 S.Y(. 212th Street Miami, Florida 33187 (305) 233-8104
l .e