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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20094J2421995-09-13013 September 1995 Rev 9 to Ja Fitzpatrick Nuclear Power Plant IST Program for Pumps & Valves Second Interval ML20078A5211995-01-18018 January 1995 Rev 2 to Core Operating Limits Rept ML20063L9621993-12-28028 December 1993 Rev 0 to DVP-01.02, Radiological Effluent Controls & Odcm ML20056D0151993-04-0606 April 1993 Rev 7 of Ja FitzPatrick IST Program for Pumps & Valves ML20115J1891992-08-31031 August 1992 Startup Readiness Evaluation (Sure) for James a Fitzpatrick Nuclear Power Plant ML20099J2081992-06-30030 June 1992 Assessment of Fitzpatrick Results Improvement Program ML20101H4711992-06-0808 June 1992 JAF-RPT-MISC-00543, Analog Transmitter Trip Sys Transmitter Response Time Testing Methodology JPN-91-054, Rev 4 to Second Interval Inservice Testing Program for Pumps & Valves1991-09-27027 September 1991 Rev 4 to Second Interval Inservice Testing Program for Pumps & Valves ML20012B0331989-12-20020 December 1989 Rev 7 to Odcm. ML20148A2251988-03-15015 March 1988 Hydrogen Water Chemistry Sys for James a Fitzpatrick Nuclear Power Plant. W/Three Oversize Drawings ML20235S6001987-06-30030 June 1987 Rev 2 to Procedure PDP-3. Direct Reading Dosimeter Calibr ML20235S6141987-05-15015 May 1987 Rev 3 to Procedure PDP-7, Dosimetry Sys Calibr & QC Procedure ML20206N1771987-03-31031 March 1987 Rev 5 to Ja Fitzpatrick Nuclear Power Plant Offsite Dose Calculation Manual. Two Oversize Maps Encl ML20235S6101987-03-0404 March 1987 Rev 4 to Procedure PDP-6, Rem Sys Instructions ML20209J0981987-01-0707 January 1987 Revised Emergency Plan Implementing Procedures,Including Rev 5 to IAP-2, Classification of Emergency Conditions, Rev 11 to EAP-1.1, Offsite Notifications & Rev 7 to EAP-2, Personnel Injury ML20207T6241986-12-31031 December 1986 Rev 4 to Offsite Dose Calculation Manual ML20206L4821986-07-30030 July 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 7 to EAP-17, Emergency Organization Staffing & Rev 7 to SAP-3, Emergency Communications Testing. W/Undated Release Memo ML19302A5181986-05-15015 May 1986 Advanced Technical Training Program for Ja Fitzpatrick Nuclear Power Plant. L-86-024, Installation Procedure ML-86-024, Limitorque Valve Actuator Qualification Insp/Upgrades. Result Summary of Limitorque Control Wire Insps,Per IE Info Notice 86-003,encl1986-03-0606 March 1986 Installation Procedure ML-86-024, Limitorque Valve Actuator Qualification Insp/Upgrades. Result Summary of Limitorque Control Wire Insps,Per IE Info Notice 86-003,encl ML20138A7651986-02-28028 February 1986 Revised Emergency Plan Implementing Procedures,Including Rev 3 to IAP-1, Emergency Plan Implementation Checklist, Rev 4 to IAP-2, Classification of Emergency Conditions & Rev 8 to EAP-1.1, Offsite Notifications ML20136H4721985-11-0101 November 1985 Revised Emergency Plan Implementing Procedures,Including Rev 5 to SAP-3 Re Emergency Communications Testing Rev 5 to EAP-22 Re Operation & Use of Radio Paging Device & Rev 14 to EAP-2 Re Personnel Injury ML20205C9461985-09-0606 September 1985 Rev 3 to Fitzpatrick Emergency Procedure Guidelines ML20129J7201985-06-30030 June 1985 Emergency Plan Implementing Procedures,Vols 2 & 3,including Rev 5 to EAP-4, Dose Estimates from Dose Assessment Calculator & Rev 3 to EAP-6, In-Plant Emergency Survey/Entry ML20212B1031985-06-25025 June 1985 Rev 2 to Offsite Dose Calculation Manual ML20128G9231985-06-19019 June 1985 Rev 0 to Procedure EDP-16, Procedure for Technical Review of Procurement Documents ML20116N6881985-04-30030 April 1985 Long-Term Pipe Support Insp & Evaluation Program Plan ML20205A9481985-04-17017 April 1985 Administrative Procedure AP 1.10, Process Control Program ML20205C9701985-02-0808 February 1985 Rev 5 to Administrative Procedure AP 2.2, Procedure for Emergency Operating Procedures ML20100A9571984-11-30030 November 1984 SPDS Implementation Plan for Ja Fitzpatrick Nuclear Power Plant ML20128G9091984-09-13013 September 1984 Rev 3 to Procedure PSO 28, Operating Experience Feedback ML20128G8981984-08-23023 August 1984 Rev 1 to Procedure EDP-12, Procedure for Establishing QA Category Classifications ML20094F5711984-07-18018 July 1984 Emergency Response Plan Exercise Manual for Ja Fitzpatrick Nuclear Power Plant ML20083N9001984-03-23023 March 1984 Rev 2 to Procedure RTP-34, Contamination Radiation Monitoring - Post-Accident ML20083N8961984-03-23023 March 1984 Rev 1 to Procedure RTP-46, Core Estimation Damage, Post-Accident Sampling Sys ML20087G6771984-02-29029 February 1984 Revised Proposed Disposal Procedures for Radioactively Contaminated Fuel Oil ML20092P6771984-02-0909 February 1984 Procedure 23, Post-Trip Evaluation ML20081B9441983-10-31031 October 1983 Revised Offsite Dose Calculation Manual ML20090H3041983-10-19019 October 1983 Detailed Control Room Design Review Program Plan for Ja Fitzpatrick Nuclear Power Plant ML20085K7581983-10-12012 October 1983 Emergency Response Plan Exercise Manual ML20072D3151983-06-21021 June 1983 Offsite Dose Calculation Manual ML20078J8471983-04-30030 April 1983 Rev 1 to Procedure SAP-1, Emergency Response Plan Exercise Manual ML20069E6861983-03-18018 March 1983 Change 1 to Rev 3 of Inservice Testing Program for Pumps & Valves 1999-10-13
[Table view] |
Text
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I 1 .
ATTACHMENT No. 2 TO JPN-84-17 s
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT Proposed Disposal Procedures for Radioactively Contaminated Fuel Oil
1.0 INTRODUCTION
In accordance with the provisions of 10 CFR 20.302(a), this document describes procedures proposed by the New York Power Authority for the incineration of radioactively contaminated fuel oil at the James A. FitzPatrick Nuclear Power Plant.
2.0 DESCRIPTION
OF LICENSED MATERIAL Seven 55-gallon drums filled with #6 tuel oil have become contaminated with very low levels of Co-60 and Cs-137. The i total activity of these drums is approximately 51 micro Ci. l This contaminated fuel oil was recovered from the Auxiliary l Boiler Room Floor Drain Oil Separator. (Refer to Table 1.) l l
2.1 Other Radioactive Material Involved No other radioactive material will be involved.
2.2 Proposed Manner and Conditions of Disposal The oil will be incinerated in the auxiliary boilers at the Authority's James A. FitzPatrick Nuclear Power Plant. The contaminated oil will be transferred from seven, fifty-five gallon drums to underground auxiliary boiler storage tank 1A where it will be used as fuel for the boilers. The auxiliary boiler storage tank has a capacity of 30,000 gallons which will further dilute the contaminated fuel oil. The average burn rate of fuel oil in an auxiliary boiler is 165 gal /hr (the maximum burn rate is 496.2 gal /hr). The gases are vented through a boiler outlet equipped with a dust collector and a fly-ash collection system.
No special conditions will be imposed on auxiliary. boiler operation.
The release of the particulates will be included in the appropriate seminannual report as a batch release occurring on the day that the drum's contents were added to the fuel oil tank.
8403200096 840315 PDR ADOCK 05000333 P PDP
' Revised 2/84
i l
l Alternate Disposal Costs 1
)
Disposal of fuel oil by this method will save approximately l
$25,000 in burial costs (including absorbant material, preparation and nandling time and transportation fees) and will save approximately 250 cubic feet of space in a commercial waste-disposal site.
Table 2 describes our estimate of the disposal costs associated with burial.
2.3 Analysis and Evaluation Radiological Effects Using the current Technical Specification formula for particulate and halogen airborne releases to the environment, a 51 micro Ci release would result in a maximum of 20.5% of Technical Specifications limits. Based upon actual quarterly releases, this release would result in an average percentage increase of 0.007% percent.
No credit is taken for treatment of releases in the exhaust l
path and the assumption is that the contaminated oil would be burned and the total activity released in approximately three-quarters of an hour.
The instantaneous release rate to the environs of I-131 equivalent halogen and particulates witn half-lives greater than eight days is limited by Environmental Technical Specification Section 2.3.B.2. The portion of the formula limiting ground level releases from FitzPatrick is:
--- + --- + (QvFITZ/8.9E-8) =1 and the estimated duration of the release assuming no dilution and boiler at maximum firing rate is:
(385 gals y496.2 gal /hr) x 3600 sec/hr = 2793 see therefore, assuming no dilution and coiler operating at maximum firing rate, tne maximum instantaneous release is:
- 51E-6 Ci/2.79E+3 sec =
0.205 8.9E-8 or approximately 20.5% for 0.78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />.
When averaged over a calendar quarter in accordance with semiannual radiological effluent reporting requirements, that average is:
SlE-6 Ci/7.78E+6 sec =
7.36E-5%
6.9E-u or approximately 0.007%.
Revised 2/84
FitaPatrick Tecnnical Specifications currently limit
[ , tne dose to persons witnin unrestricted areas to 500 mrem /yr. Tnis limit applies to whole body or any organ
- s doses from airborne halogens and particulates witn
!, half-lives greater than eight days. Tnis limit applies to releases from tne main stack and vents of uuth FitzPatrick and Nine Mile Point' Unit 1. Tne dose L attrioutanle to tne proposed con'taminated oil is calculated as follows:
L S00 mrem /yr. x 7.368-S4 = 3.6.88-2 or-approximately 0.04 I mrem /yr.
A second calculation using tne draft ODCM (Offsite Dose Calculation Manual) metnodology agreed with tne wnole bodyoranyorgandoseof0.Opmremwitnin+25%.
- The following is an estimation of residual radioactive
,. material of tne tank assuming.tnat tne 3dSNgallons is thoroughly mixed with tne contents of a full Fuel Oil Tank 1A.
t Activity of tank = b l ,4JCi (Co-60 + Cs-137) 30,000 gal x 3,785 ml/ gal ,
5 =
4.498-7 ALCi/ml s
If the content of the tank is completely used (ourned)
, assume that oil 1 cm thick will cling to the tank Walls.
Contamination = 4.498-7 4Ci/cc x 2.22E+6 dpm/ A(, Ci x 100 cm
= 9.97E+1 dpm/100 cm2 x Disc smears are approximately 203 efficient; tuerafore measurable smearable activity would be:
Smearable contamination ^= 100 dpm/100 cm 2 x 0.20
~% y s -
= 20 dpm/100 cm 2 Tne plant's unrestricted area smearaole contamination limit is 1,000 dpm/100 cm2, ,
?
Nature of Environment Refer to the James A. FitzPatrick Final Safety Analysis Report (FSAR), Cnapter 2 (Site and. Environment) for pertinent information as to tne nature of tne environment, including topographical'(Section 2.1.1), geological (Section 2.5), meteorological (section 2.2), nydrological (Section 2,4) cnaracteristics;' usage of ground and surface waters in tne general area (Sections 2.1.2, 2.4.lJand 2.4.2 ) and location of otner potentially affected facilities (Section 2.1.'3 ) . ,
s ,
F. j~
s ,
Revised 2/84
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1 J
, 2.4 Ptocedures to Minimize Risk of Unexpected or Hazardous l Exposures !
Prior to transferring the contents of the seven fuel oil drums to Fuel Oil Tank 1A, a sample from each drum l will be taken. These samples will be subjected to i Ge"Li" isotopic analysis. Analysis results uill be !
compared with prior samples to ensure accuracy and consistency.
Other than this analysis, the Authority does not propose using any special procedures related to the incineration of this fuel oil. The analysis presented in Section 2.3 of this document clearly shows that the incineration of this fuel oil represents an insignificant change in the amount of radioactive effluents released and no significant environmental impact can be attributed to the proposed action.
Therefore no special procedures are proposed.
3.0 REFERENCES
- 1. Code of Federal Regulations, Title 10, Part 20.302,
" Method for obtaining approval of proposed disposal proceaures."
- 2. 10 CFR 20.305, " Treatment or disposal by incineration."
- 3. USNRC Office of Inspection and Enforcement Information Notice No. 83-05, " Obtaining Approval for Disposing of Very-Low-Level Radioactive Waste - 10 'R Section 20.302," dated February 24, 1983.
- 4. NRC Policy Statement on Low-level Waste Volume Reduction, Octouer 16, 1981 - 46 FR 51100.
- 5. 10 CFR 61, " Licensing Requirements for Land Disposal of Radioactive Waste," July 24, 1981 - 46 FR 38031.
- 6. James A. FitzPatrick Nuclear Power Plant Environmental Technical Specifications, Section 2.3.B, " Airborne Effluents."
- 7. James A. FitzPatrick Nuclear Power Plant Final Safety Analysis (FSAR), Revision 0 dated July 1982, Chapter 2,
" Site and Environment."
Revised 2/84
. ~ _ . - . _ _ . . . _ _ . _ . . _ . . . _ _ . . _ _ . - . _-- _ _ _ _ - . -. .- ... _ . - _ - __ _
i -
l l . r i l ,
TABLE 1 i r /
w 66 PUEL OIL SAMPLE AND ANALYSIS !
JANUARY 11, 195J l
Waste Oil' ACi/ml Total Activity in mci l Labeled As co-60 Cs-137 Co-60 Cs-137 il 3.37E-5 ND* 7.02 ND
- 3 3.44E-5 HD 7.16 ND 2
(4 -3.77E-5 ND 7.85 ND ;
I5 1.49E-5 ND 3;10 ND i i 66 5.31E-5 ND 11.05 ND
- #7 4.70E-6 ND 0.98 ND 98 6.14E-5 4.40E-6 12.78 0.92 i TOTAL 49.94 0.92 4
l
.i i -,
i 1
i j
1 d
d
'i 4
Revised 2/84
.f'
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e-vr -vr <<n- - , --ce --
i . TABLE 2 COST OF BURIAL DISPOSAL OF SEVEN DRUMS OF HUMBER 6 FUEL OIL j i
5 Solidification 7 drums of 36 oil x 10 solidified drums x $130/ drum = $ 9,100 i Cost drum or 96 011 Burial Cost 70 drums x 7.5 cu. ft. x $18.97/cu ft = 9,960 drum .
Labor Cost 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> x $ 15.60 = 300 nour Transportation = 5,000
. TOTAL $24,360 4
1 Notes for Table 2:
- a. Because of the viscosity of 96 fuel oil, " Speedy Dry" type absorbants cannot be used. Instead, contractors are retained to perform the required solidification. Based upon previous experience, the cost for solidifying #6 oil using concrete, soaps, etc., is approximately
$130 per solidified drum.
- b. Por the purpose of estimation, a 10:1 solidification factor is used.
- c. The current cost of burial is $18.97/ cubic foot.
- d. 20 man-hours would be expended.for preparing the lead for shipment at an average rate of $15.60/hr.
- e. Transportation cost is approximately $5,000.
Revised 2/84.
1
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