|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989 Suppl 15 to Startup Rept for Period 890501-0801 ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989 Suppl 14 to Startup Rept for Period 890201-0501 ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988 Suppl 12 to Startup Rept for Period Aug-Nov 1988 SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988 Suppl 11 to Startup Rept for May-Aug 1988 ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution 1994-07-31
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D5931988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 10, Level/ Power Control ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D5621988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 7, Emergency Depressurization ML20151D6971988-06-20020 June 1988 Rev 9 to Procedure 29.023.01, Reactor Pressure Vessel Control Emergency Procedure. W/One Oversize Encl ML20151D6281988-06-10010 June 1988 Rev 1 to Procedure 3.04, Developing Written Tests ML20151D6481988-06-10010 June 1988 Rev 1 to Procedure 5.01, Counseling Trainees & Providing Remedial Training Plan ML20151D6791988-06-10010 June 1988 Rev 2 to Procedure 8.01, Simulator Exam Evaluation ML20151D6581988-06-10010 June 1988 Rev 0 to Procedure 5.02, Formulating Tests from Question & Answer Banks & Administering Tests ML20151D5821988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 9, Reactor Pressure Vessel Flooding ML20151D4981988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 5, Radioactive Release Control ML20151D5691988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 8, Steam Cooling ML20151D6041988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 12, Figure ML20151D5481988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 6, Alternate Level Control ML20151D4471988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 3, Primary Containment Control ML20151D4251988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 2, Reactor Pressure Vessel Control ML20151D5971988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 11, Primary Containment Flooding ML20151D4901988-05-11011 May 1988 Rev 0 to Plant Specific Technical Guideline 4, Secondary Containment Control ML20196A9081988-01-25025 January 1988 Rev 3 to 80A8614, Inservice Insp Program Plan,Core Spray Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing ML20196A9601988-01-25025 January 1988 Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1 ML20196A9911988-01-25025 January 1988 Rev 3 to 80A8621, Inservice Insp Program Plan,Containment Penetration Flued Heads,Shoreham Nuclear Power Plant Unit 1 ML20196A9471988-01-25025 January 1988 Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1 1994-07-31
[Table view] |
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3 F01INF0MATION ONLY PROJECT COVER SHEET
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Document Title -
j PROCESS CONTROL PROGRAM FOR INCONTAINER SOLIDIFICt. TION OF BEAD RESIN - POVDERED RESIN MIX
.$ (Maximum 28 Wet Weight Percent Powdered Resin)
Project Document Number
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, F458-P-003, Rev. O M
for LILCO N
Shoreham Nuclear Power Station
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Hittman Nuclear & Development Corporation 9151 Rumse~ Road
.; Columbia, MaryIand 21045 y
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PROCESS CONTROL PROGRAM FOR INCONTAINER SOLIDIFICATION 0F BEAD RESIN - POWDERED RESIN MIX 1
(MAXIMUM 28 WET WEIGHT PERCENT POWDERED RESIN)
};. ' .
1.0 PURPOSE
-. l
.j To define the analysis to be performed on saeples taken from
.r MITTMAN liners while processing bead resin mixed with powdered 2 resic for solidification, and the parameters of the test solidi- -
]. . ficu lon.
Li
- 1
2.0 REFERENCES
hk F458-P-010. " Operating Procedure for Mobile Incontainer y Solidification of Bend Resin and Powdered Resin Mixtures."
v M 3.0 DISCUSSION
- lI
.,j i The type of waste covered by this document is bead ion exchange p : resin mixed with powdered resin up to a 28 wot weight percent of f powdered resin. In order to ensure that the contents of the jJ f liners to be processed fall within the acceptable range with j! (. respect to the parameters, samples of the liner contents must be gp analyzed prior to solidification. Analysis includes pH, deter-
- 1; gents, a visual determination of oil content an$ an isotopic
.'] analysis.
J
'Ili 4.0 APPARATUS T 4.1 pH meter h
iy 4.2 Disposable beakers l' 4.3 Top loading balance ,
pn 4.4 Electric lab mixer (optional) 41 5.0 CHEMICALSi yy 5.1 50% NaOH solution ,
fn 5.2 Anhydrous Sodium Metasilicate j 5.3 Pprtland Type I cement
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. . . . . ... . . . . . . . . . = = = = . . en- = ee me e.- : e
.d ,e p * *g 8 6 W SSd*d " W T M M M 984@P*W*#8M M N'96 M _ engmurse--- _
99*87 * @ .*'*W gS* M tE88 WE' M i 54 4 e ' & . % e%M +
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F458-P-003 Page 2 of 6
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d$ - 6.0' PREREQUISITES l
&j3 ~ '6.1 Ensure that the contents of the MITTHAN liner have been :
ly .
dewatered prior to sampling. ' !
lit hit 6.2 Ensure that a Waste Solidification Data Sheet, Attachment A,-
)
N' has been initiated for t' e solidification of liner contents !
consisting of spent bead resin mixed with powdered resin.
6.3 Samples are available for analysis for pH, detergents, oil -
and for an isotopic analysis.
3w-f
- $) 7.0 PROCEDURE d
l} NOTE:
Data taken as instructed in this section shall be i recorded on the attached Waste Solidification Data-
[ Sheet, Attachment A.
.e
, 3- 7.1 Chemical Analysis and Pretreatment
.,L' 7.1.1 EXAMINE the sample for evidence of detergents. If large quantities of detergents are present, the J' sample should be treated vnh an anti-foaming agent. The quantity of anti-foaming agent required 1
'73 I-( shall be recorded on Attachment A.
i# 7.1.2 EXAMINE the surface of the sample for any signs of
'b oil. If a measurable quantity of oil exists, y
determine the volume and record it as a percent of
- 9 the total sample volume, otherwise note "none" or y
"less than one percent" (1%) by volume. If the p
c.J quantity of' oil is greater than 11 by volume, the oil shall be reduced to less than 1% by skimming
'( prior to recording.
7.1.3 MEASURE the pH of the sample and record.
.1' NOTE: If necessary, adjust the pH to greater J
than 4 using 50 weight percent sodium hydroxide solution. The quantity of sodium hydroxide added shall be recorded on Attachment A.
7.1.4 PERFORM an isotopic analysis of an appropriate
(
aliquot of the sample.
,p. 7.2 Test solidification 7-' 7.2.1 MEASURE 158.0 gas (* 180 ml) of dewatered waste y
M
.( from the liner into a 1000 ml disposable beaker or similar sized container.
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( 7.2.2 - ADD 55.3 gas of water. :
-J q 7.2.3 MEASURE out the required quantities of c9nt and '
anhydrous sodium metasilicate as shown below.
e a Grams Anhydrous Sodium 1
.d.
Grams Cement Metasilicate d
q 1
179.4 17.9 t i 7.2.4 MIX the cement and additive together and slowly -
- )
, 'l add this mixture to the test sample while it is being stirred. Stirring can be accomplished by an
-electric mixer or by hand.
'j "
7.2.5 After sufficient mixing (2 minutes after all
.i cement and anhydrous sodium metasilicate have been added) so that a homogeneous mixture is obtained, allow the waste to CURE for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
g 7.3 Solidification Acceptability
' The following criteria define an acceptable solidification process and process parameters.-
fI ( 7.3.1 The sample solidifications are considered acceptable 1
1 if there is no visual or drainable free water.
'i 7.3.2
- The sample solidifications are considered acceptable i if upon visual inspection the waste appears that i it would hold its shape if removed from the beaker and it resists penetration.
q 7.4 Solidification Unacceptability 1 l 7.4.1 If a test sample fails to provide acceptable i
1 t
solidification, perform the following steps:
- a. Mix egual volumes of dry cement and water to a
ensure that the problem is not a bad batch of
, cement.
' t j
- b. Add additional caustic solution to raise the pH above S.
i
- c. If the waste is only partially solidified, use lower waste to cement and additive ratios.
Using the recommended quantities of cement i ,
and anhydrous sodium metasilicate, reduce the sample weight by 21.7 gas (* 25 al) and the water weight by 7.5 grams.
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( b. Perform another test solidification using the I revised waste to cement ratios. Continue lowering the waste to cement ratios until the acceptability criteria of 7.3 are meg.
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F458-P-003
'h ' Pase 5 of 6 Iy=.+ .~- ATTACHMENT A 11iI: - ( WAS1T SOLIDIFICATION DATA SHEET FOR READ RESIN - POWDERED RESIN MIX l Liner Sampled: Batch No: e Sample No:
$ Sampled By:
A i g Sample Volume, al:
E (1) -
e; Sample pH: Volume 50% NaOH used to adjust pH
- r. m1I (2) f Quantity of 011 %
(3)
K f Quantity of Anti-Foaming Agent, al d (4) f,i Temperature at solidification:
a (5) p other Major Constituents:
(6) k L1 Quantity of Cement Added Cement. Ratio (1bs/ft.2 y,,ge)2
[ ses (IO)
Quantity of Additive Added Additive Ratio (1bs/ft.8 Weste) 1 gas
% (11) f Volumetric Ratio: Waste to Product:
E q
? (12) e#
Product Acceptable: Sample A _
Yes No 9
p Radionuclides Present: (Isotopes & Concentrations) 4 I
? Test Solidification Done By 2
0 j
Additional batches solidified based on this test solidification:
F Batch Batch Batch Batch Batch Batch No.
4 Vol. Date _ No . _Vol. Date No. Vol. Date 0' 2 5 8 I 3 6 9 a
(s 4 7 10 ,
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To determine the quantity of 50% NaOH or antifoam agent to add to the liner,
'. 5j . . use the following equation: '
.i'
.I al 50% NaOH (or antifoaa) used for 200 al sample a ft.a of waste in liner
.I
, rr 26.72 f*
s = gallons of 50% NaOH to add to liner (or antifoaa)
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} Ratios in this procedure yield a cement ratio of 61.7 lbs/ft.a Il 3 p.f.
- :t The additive used in this procedure is anhydrous sodium metssilicate.
h$
.; d Ratios ir, this procedure yield an additive ratio of 6.2 lbs/tt.*
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