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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 1999-08-04
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 ML20137P8441997-02-14014 February 1997 Rev 5 to Authorization of Changes,Test & Experiments (10CFR50.59 & 72.48 Reviews) ML20140G9351997-02-14014 February 1997 Rev 13 to ISTs IT 585, Leakage Reduction & Preventive Maint Program Test of Post-Accident Containment Atmospheric Sampling Sys (Refueling) ML20140G8921997-02-14014 February 1997 Rev 7 to ISTs IT 215, SI Valves (Cold Shutdown) ML20140G9401997-02-0707 February 1997 Rev 21 to TS Tests TS 10A, Containment Airlock Door Seal Testing ML20138K2991997-01-31031 January 1997 Rev 46 to OP 4D,Part 1, Draining RCS to CVCS Hut W/O Entering Reduced Inventory ML20138K2031997-01-31031 January 1997 Rev 6 to IT 380, Purge Valve Air Sys Check Valve (Quarterly) for Unit 1 ML20138K2551997-01-31031 January 1997 Rev 2 to IT 530B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) for Unit 1 ML20138K2411997-01-31031 January 1997 Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1 ML20138K3231997-01-31031 January 1997 Rev 9 to RP 6A, SG Crevice Flush (Vacuum Mode) ML20137P8551997-01-31031 January 1997 Brine Tank Standpipe Mod ML20138K3071997-01-31031 January 1997 Rev 38 to OP 9C, Containment Venting & Purging ML20138K2901997-01-31031 January 1997 Rev 2 to IT 535A, Leakage Reduction & Preventive Maint Program Test of Train a HHSI & RHR Sys (Refueling) Unit 2 ML20138K2641997-01-31031 January 1997 Rev 12 to IT 535, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 2 ML20138K4991997-01-31031 January 1997 Rev 9 to Ort 4, Main Turbine Mechanical Overspeed Trip Device for Unit 2 ML20138K3181997-01-31031 January 1997 Rev 33 to RP 1B, Recovery from Refueling ML20138K3031997-01-31031 January 1997 Rev 1 to OP 4D,Part 5, Draining RCS to CVCS Hut W/O Entering Reduced Inventory & W/O SG Tubes ML20138K2251997-01-31031 January 1997 Rev 7 to IT 385, Purge Valve Air Sys Check Valve (Quarterly) for Unit 2 ML20138K4791997-01-31031 January 1997 Rev 15 to Ort 67, Component Cooling Water to & from Excess Letdown Heat Exchanger-Refueling Shutdown for Unit 1 ML20138K4701997-01-31031 January 1997 Rev 17 to Ort 59, Train Spray Sys CIV Leakage Test for Unit 1 ML20138K5041997-01-31031 January 1997 Rev 7 to Ort 50, PRT to Gas Analyzer Sample Line for Unit 2 ML20138K5161997-01-31031 January 1997 Rev 18 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 2 ML20138K4751997-01-31031 January 1997 Rev 19 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 1 ML20138K5231997-01-31031 January 1997 Rev 7 to Ort 71, Electrical Penetration Leak Test for Unit 2 ML20138K7311997-01-31031 January 1997 Rev 9 to TS 80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175A,B) & EDG Day Tanks (T-31A,B & T-176A,B)(Quarterly) ML20138K7171997-01-31031 January 1997 Rev 6 to TS 37, Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Yrs) for Unit 1 ML20138K3121997-01-31031 January 1997 Rev 43 to RP 1A, Preparation for Refueling 1998-09-30
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t-RDW 3.1 MINOR Revision 1 05-11-84 RADIOACTIVE WASTE DISPOSAL 1.0 SCOPE The release of all plant radioactive effluents shall be subject to the
. applicable regulations specified in 10 CFR 20 and the conditions of the facility license. Shipments of waste for offsite disposal shall be in accordance with applicable NRC and DOT regulations and conditions of the disposal contractor's license.
2.0 REFERENCES
2.1 10 CFR 20, 61, 71 2.2 49 CFR 100 to 199 2.3 Chem-Nuclear Systems, Incorporated, Barnwell, South Carolina Disposal Site License and Criteria
( 2.4 US Ecology, Incorporated, Richland, Washington, Disposal Site License 2.5 US NRC Special Nuclear Materials License No. 16-19204-01, issued to US Ecology 3.0 RESPONSIBILITY 3.1 It is the responsibility of CHP to determine the radioactivity content of plant effluents and solid wastes.
3.2 It is the responsibility of CHP to ensure that all controlled radioactive waste discharges are in compliance with 10 CFR 20, and provisions of the facility license.
I i 3.3 CHP will maintain complete records of radioactive waste releases to i
the environment and shipments offsite for disposal.
3.4 It is the responsibility of the Duty shift Superintendent to review the operational aspects of all controlled releases of radioactive
! effluents and to ensure the proper lineup of tanks, valves and discharge pumps. In the case of an uncontrolled and unmonitored release of radioactivity, the Duty Shift Supervisor has the responsibility of determining if any adjustments are required in i plant operation or equipment. Any uncontrolled or unscheduled release shall be reported to a Duty & Call Superintendent.
i 3.5 It is the responsibility of cognizant supervision to notify CHP of anticipated accumulations of radioactive material that require disposal.
3411120324 841105 PDR ADOCK 05000266 PDR I
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RDW 3.1 Page 2 3.6 It is the responsibility of cognizant supervision to assure that personnel filling packages of solid or solidified wastes obtain a waste permit number for each package.
3.7 It is the responsibility of the Duty Shift Superintendent or his designate, to initiate the preparation of a Waste Permit Form (CHP-16) for each package of solid or solidified radioactive wastes.
e 4.0 SOLID RADIOACTIVE WASTE 4.1 Solid radioactive waste containers, properly designated, are located at convenient points throughout the controlled zone.
Containers for compressible scrap should be lined with a plastic bag to prevent the spread of contamination during the transfer from the container to the baler.
4.2 Containers should be routinely monitored and radiological hazards posted as appropriate.
4.3 When full, containers should be emptied or processed for shipment as
( appropriate.
j 4.4 Large solid radioactive waste articles shall be monitored and then
- wrapped, boxed, or otherwise sealed, if necessary, to confine any l contamination before moving or storing as contaminated waste.
4.5 CHP will assure that solid waste is properly packaged and shipped to 4
a licensed disposal site.
l 4.6 Solid waste will have no free standing liquids in the package. Use nf
- absorbents, solidification agents or dewatering methods will be used as appropriate.
See Attachment 1 for the procedure to order the proper type of l
cement for solidification and absorbent purposes.
5.0 LIQUID RADIOACTIVE WASTE
[
5.1 All normal liquid radioactive wastes are collected by the waste disposal system and processed as required.
5.2 Prior to disposal of any tank of liquid radioactive waste, a sample of the tank shall be analyzed. The specific activity (in pCi/ml)
( shall be determined; isotopic concentrations identified, if necessary, and the required dilution factor calculated.
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RDW 3.1 Page 3 5.3 If the tank is acceptable for disposal, a permit for radioactive waste discharge will be completed by a CHP Supervisor or his designated personnel and forwarded to the Duty Shift Superintendent who will authorize and carry out the disposal. Radioactive liquid waste having concentrations in excess of those specified in Appendix B, Table II, 10 CFR 20, after in plant dilution, will not normally be approved for discharge from the plant. A release rate in excess of that stipulated by the radioactive waste release permit is not i
permitted. Any deviation from the conditions of the release permit shall be noted on the permit.
5.4 Any uncontrolled, or unplanned liquid release shall be recorded and concentrations and total activity output will be determined by CHP.
The Duty Shift Superintendent and the Duty & Call Superintendent will be notified promptly.
6.0 GASEOUS RADIOACTIVE WASTE 6.1 All radioactive gaseous wastes emitted through the plant vent or 4
drumming area vent stack are monitored prior to the point of discharge.
f 6.2 The controlled release of all radioactive gaseous waste shall be in accordance with applicable Federal and State regulations and provisions
- of the facility license.
6.3 Prior to disposal of any tank of gaseous radioactive waste, a sample of the tank shall be analyzed. The specific activity (in pCi/cc) will be determined; isotopic concentrations identified, if necessary, and the required dilution factor calculated.
4 6.4 If the tank is acceptable for disposal, a permit for radioactive 2
waste discharge will be completed by a CHP Supervisor or his
- designated personnel ard forwarded to the Duty Shift Superintendent who will authorize and carry out the disposal.
i 6.5 Any uncontrolled, or unplanned gaseous release shall be recorded and concentrations and total activity output will be determined by CHP.
The Duty Shift Superintendent and the Duty & Call Superintendent will be notified promptir.
7.0 BURIAL SITE CRITERIA l PBNP primarily ships its radioactive vaste to the Chem Nuclear and U.S.
Ecology burial sites at Barnwell, SC and Richland, WA, respectively. The
, facilities are governed by different Agreement State licenses and therefore, their operations may differ from one another in certain areas.
! Prior to processing or shipping radwaste to either site therefore,
'( requires a review of the particular requirements at each facility.
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l RDW 3.1 l Page 4 7.1 Chen Nuclear, Barnwell SC 7.1.1 Chelating Agents Waste sent to the Chem Nuclear burial site may not contain chelating agents with concentrations greater than 8% by weight. Waste with chelating agents within the range of 0.1 to 8.0% by weight must be solidified. The concentration limits apply to the vastes prior to solidification; dilution by solidification media is not allowable. This means that solidification media such as cement may not be added to the waste merely to lower the concentration of the chelating agents.
In addition, as is required by RDW 5.8, Paragraph 5, the concentration of chelating agents over 0.1% by weight must be listed on Form CNS-201, Barnwell Management Facility Radioactive Shipment Record.
7.1.2 Resins and Filters
( Ion exchange resin and filter media containing isotopes with greater than 5 year half-lives having a specific activity of all these isotopes of 1 pci/cm3 or greater must be stabilized by solidification. The waste when solidified may contain no significant free standing water, i.e., 50.5%
by volume. In lieu of solidification however, the waste may be disposed of in a high integrity container.
7.1.3 Incore Detectors Incore detectors containing transuranic materials are not acceptable for disposal at the Chem Nuclear burial site.
7.2 U.S. Ecology, Richland, WA 7.2.1 Chelating Agents There is no limit on the amount of chelating agents that may be contained in a package sent to U.S. Ecology. As is {
required by RDW 5.8, Paragraph 4 however, the concentration 8 of chelating agents over 0.1 percent.by weight must be listed on the U.S. Ecology Radioactive Waste Shipment &
Disposal Manifest. .
o RDW 3.1 i Page 5 7.2.2 Resins and Filters Ion exchange resin and filter media ccntaining isotopes with a total specific activity of 1 pCi/cm3 or greater and half-lives greater than 5 years must be stabilized by solidification. The waste, when solidified may contain no significant free standing water, i.e. 50.5% by volume. In lieu of solidification, the waste may be disposed of in high integrity containers which have been approved by the State of Washington.
7.2.3 Incore Detectors Incore detectors and other equipment contaminated with transuranic nuclides (TRU's) are acceptable for burial at US Ecology provided the concentration of TRU's is less than 10 nanocuries per gram of waste.
7.2.4 Special Nuclear Material No package containing special nuclear material for disposal may contain more than 100 grams of uranium-235, 60 grams of uranium-233, or 60 grams of plutonium. Waste containing a combination of these isotopes must be such that the sum of the ratios does not exceed unity; i.e. ,
Grams Contained U-235 , Grams Contained U-233 , Grams Contained Pu $1.
100 60 60 In addition, the radioactive shipment record used to describe the special nuclear material must be certified by the shipper to show compliance with USNRC Special Nuclear Material License No. 16-19204-01 (US NRC SNM No.
16-19204-01, Paragraph 20.)
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RDW 3.1
.t Page 6 ATTACHMENT 1 ORDERING CEMENT FROM A VENDOR 1.0 GENERAL '
The presence of borates in liquid radwaste streams inhibits the action of many cement compounds. In order to assure acceptably hard waste forms, the proper cement must be used. Solidificaiton tests and plant experience show that cement from Western Lime & Cement, identified as their Type 1.1.0, is acceptable.
2.0 CEMENT ORDERING PROCEDURE 2.1 Fill out a purchase request (form AD-64) and forward it to Ready Stores.
2.1.1 The vendor shall be Western Lime & Cement. Their address is on file in Ready Stores.
2.1.2 Identify the quantity needed.
2.1.3 State whether bulk cement or bags are desired.
2.1.4 Identify the cement as Type 1.1.0.
2.1.5 Enter the words "D0 NOT SUBSTITUTE" on the request.
2.2 A cement distributor may be used, provided exactly the same cement is delivered. !
3.0 CHECK CDENT ON DELIVERY If the cement delivered is not Type 1.1.0 manufactured by Western Lime &
Cement, then return it to the vendor.
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