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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
ML20151D4191988-07-13013 July 1988
Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution
ML20151D6081988-07-13013 July 1988
Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures
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] |
Text
^
SP Number 29.923.02
. .Subnitted:
Epproved: Revision C Flant Manager Effective Date tt c -""
EMERGENCY PROCEDURE dh' ?"h l
.1.9 PURPOSE The purpose of this procedure is to depressurize and cooldown the RPV to cold shutdown conditions while maintaining RPV water level within : satisfactory range.
'2.9 ENTRY CONDITIONS This procedure is entered from SP 23.923 91 (Level Control) after the RPV water level has been stabilized.
}$ 3 9 . OPERATOR ACTIONS
^
~
CAUTION If a high drysell pressure ECCS initiation signal occurs or exists while de?ressurizing, prevent injection.from those CS and LPCI pumps not required to assure adequate core cooling prior to reaching their maximum injection pressures.
When the high drywell pressure ECCS initiation signal clears, restore CS and i.PCI to AUTOMATIC / STANDBY mode.
CAUTION Do not secure or place an ECCS in MANUAL mode unless, by at le..e two independent
, indications, (1) misoperation in AUTOMATIC mode is confirmed, or (2) adequate core cooling is assured. If an ECCS is placed in MANUAL node, it will not initiate automatically. .Make frequent checks of the initiating or controlling parameter. ' When annual operation is no longer required, restore the system to Automatic / Standby Mode if possible.
r eui 3 R lm ;,<ut;
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.'7f4 8/ 8107230261 810720' PDR ADOCK 05000322-
< A PDR- ,
79 .
L3.1 Maintain RPV water laval betwaan +6" en Fual Zens Indicator end +58.75" with cne or more of tha following systens:
3.1.1 Condensate /Feedwater 1115 to 9 psig 3.1.2 CRD 1115 to 9 psig CAUILON Do not throttle HPCI or RCIC systems below the minimum speed of 2159 RPM.
g '3.1.3 RCIC 1115 to 59 psig
- c. 3.1.4 HPCI 1115 to 199 psig 3.1.5 C.S. 333 to 9 psig 13 .1.6 LPCI 238 to 9 psig CAUTION If signals of high suppression pool water level (26'11") or low condensate storage tank water level (3'4") occur, confirm automatic transfer of /or manually transfer HPCI and RCIC suction from the condensate " tank to the i suppression pool.
i 3.1.7 If any of the following limits are er.ceeded, proceed
. to'.SP 29 923.93 (Containment Control) and perform L it concurrently with this procedure.
L
- s. Drywell pressure above +1.69 psig i :b. Drywell ~ temperature above 135'F r
- c. = Suppression Pool temperature above 99*F L d. Suppression Pool level above 26'8"
- e. Suppression Pool level below 26'9" l^
igg -- 3.2 If RPV water level cannot be determined or maintained above I"r ' TAF, enter SP 29 923 94 (Level Restoration).
1
- 1. TAF = +6" as read on fuel zone' instrumentation:
SP 29 923.92 Rev. C Page 2 g
' . , 3.3 If SRV'c crs cycling, manually cpan ena SRV snd r:duca RPV prssgure to b2tw2cn 790 psig cnd 960 psig to ninimiza SRV cycling (alternate SRV's to equalize suppression pool heating if this step must be repeated using Figure 1 as a guide.)
3.4 Depressurite the RPV and maintain cooldown rate below 19@'F/hr per SP 22 9@5.91, Shutdown to Cold Shutdown concurrently with this procedu"e.
3.4.1 Pressure reduction may be augmented with one or more of the following systems.
CAUTION Cooldown rates greater than 199'F/hr may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive release to the environment.
CAUTION Do'not depressurize the RPV below 199 psig unless motor driven pump sufficient to maintain RPV water level are
~
running and available for injection.
3.4.2 Use one or more of the following systems:
(A) Main Condenser available (1) Main Turbine Bypass Valves (preferred asth'od) per SP 22 905.91, Shutdown to Cold Shutdown
~
(2) RCIC per SP 23.119 91, Reactor Core Isolation Cooling (RCIC) System (3) HPCI per SP 23.292 91, High Pres 9ure Coolant Inja.ction (4) RHR (Steam Condensing Mode) per SP 23.121.91, Residual Heat Removal (RRR)
System l~ (5) Other Steam Driven Equipment (1) Steam Jet Air Ejectors per SP 23.791.91, Condenser Off-Gas Removal L
SP 29.923 92 Rev. C Pags 3 t.
- (2) 'RFPTS par SP 23.199.91, Fetdwater Systes (3) Steam Seal Evaporator per SP 23.124.91, Steam Sealing (4) Main Condense- Deaerating Steam per SP 22.193.91, Condensate (5) RWCU (Recirculation Mode) per SP 23.799 91, Reactor Water ,leanup System (6) Main Steam Line Drains per EP 23.116.91, Main and Auxiliary Steam (7) RWCU (Blowdown Mode) per SP 23.791 91, Reactor Water Cleanup System
~(B) Main Condenser not available (1) RCIC per SP 23.119 91, Reactor Core Isolation Cooling (RCIC) System (2) HPCI per SP 23.292.91, High Pressure ~.
Coolant Injection (3) RHR (Steam Condensing Mode) per SP 23.121 91, Residual Heat Removal (RER)
System (4) RWCU (Recirculation Mode) per SP 23.799 91, Pesctor Water Cleanup System (5) SRV's .
(1) Open relief valves using Figure 1 as a guide to equalize suppression pool heating L
(2) Fewer blowdowns with increased l pressure reductions are desirable to l- minimize SRV cycle stresses.
j-(3) If'the 20atinuous SRV pneumatic supply is or becomes unavailable, l: depressurize with sustained SRV
! opening.
(6) RWCU (Blowdown Mode) per SP 23.799.91, Re. actor Water Cleanup.
SP 25.923.92 Rev. C Page 4
- -- -- p .v-e = e-< - c en - ---e+-r-
- l 3.5 Wh n th2 RHR chutdown cooling interlecko clast, initista the shutdown cooling modi of RRR par SP 23.121 91, Resid:.al Hast u Removal (RHR) System.
t 3.6 If the RHR shutdown cooling mode cannot be established and furt"ser cooldown is required, continue to cooldown with the systems listed in substep 3.4.2(A) or 3.4.2(B) as
, f f+ < applicable.
4" 3.7 If'RPV cooldown is required bst cannot be accomplished, perform the following.
3.8 Initiate Suppression Pool Cooling per SP 23.121 91, Residu.sl Heat Removal (RHR) System.
3.9 ~Close the following valves:
Q (A) RPV Head Vents 1B21 MOV-984 1821 MOV-985 (B) All MSlV's 1B21 A0V-981A IB21 A0V-982A 1821 A0V-981B 1B21 A0V-982B ,
~
1B21 A0V-981C 1821 A0V-982C
-1521 A0V-981D 1B21 A0V-982D _ , _
_(C) MSL Drain Lines 1B21 MOV-938 IB21 MOV-933 1B21 A0V-988 1821 A0V-989 (D) RHR Steam Condensing Valve IE11 MOV-949 3.19 Position SRV'siso that only one SRV is open.
3.11 Maintain RPV water level less than 58.75" until RPV pressure is less than (later) psig by use of HPCI and RCIC.
SP 29.923 92 Rev. C Page 5
P
~
3.12 Wh n PRV w:tsr 1sval exeseds 58.75".
.(A) CLOSE the following HPCI isolation valves:
r
'1E41-MOV-941 1E41 MOV-942 1E41 MOV-947- 1E41 MOV-948 k (B) ~ CLOSE the following RCIC isolation valves:
D .-1E51 MOV-941 1E51 MOV-942 1E51 MOV-947' 1E51 MOV-948 3.13. Start one CS or LPCI pump 'with suction from the suppression ,
pool.
- 3.14 Slowly raise RPV water level while maintaining less than 199'F/hr cooldown rate, to establish a flow path through the 1 open SRV back to the suppression pool.
3.15' Slowly _ increase CS or LPCI flow to' establish a 199'F/hr cooldown rate. [
3.16 IF necessary, increase CS or LPCI flow to the maximum single ~
pump flow for the pressure at which RPV pressure stabilizes. .
3.17 IF RPV pressure.does not stabilize ABOVE (later) psig, start another pump.
3.18 IF RPV ' pressure does not stabilize BELOW (later) psig, open additional SRV's located symetrically about the suppassisn pool.
CAUTION ,
i CONTROL SUPPRESSION POOL TEMPERATURE TO MAINTAIN RPV WATER TEMPERATURE ABOVE 79'F_PER SP 23.121.91, RESIDUAL HEAT REMOVAL (RER) SYSTEM.
! 3.19 'When RPV cooldown is under control and plant conditions are l* stable, proceed to cold shutdown in accordance with SP 22.995.91, Shutdown to Cold Shutdown.
SP 29 923.92 Rev. C Page 6-i
. . . - - . - . , - , - - , - . . - - . . , - - . . . - - , . _ . . - _ ~ . - . . . . - - - . - . . . . . . . _ . -
4.9 REFERENCES
4.1 SP 29 923 91 - Level Control 4.2 SP 29 923.94 - Level Restoration
.4.3 SP 22.995.91 - Shutdown to Cold Shutdown 4.4 SP 23.119.91 - Reactor Core Isolation Cooling (RCIC) System 4.5 SP 23.292 91 - High Pressure Coolant Injection 4.6 SP 23.121 91 - Residual Heat Removal (RHR) System 4.7 SP 23.791 01 - Condenser Off Gas Removal 4.8 SP 23.124.91 - Steam Sealing 4.9 SP 23.193.91 - Condensate 4.19 SP 23.199.91 - Feedwater System "4.11 SP 23.799 91 - Reactor Water Cleanup System 4.12' SP 23.293 91 - Core Spray System 4.13 SP 23.294.01 - Low Pressure Co.olant Injection SP 29.923.92 Rev. C Page 7
< prv yy v .,v --, , - - - , ,w%,-,y,,m,, , -w._._w---,
+v-ga +- < w F--r ,--em g y,c-.y,.9----- 9ser,e, ,9-p-e-yy-- y w-w+,.3--,.-
e U
+RV-093H +RV-093L I
IC61TE022A 1Z93TE132A-1 1 1Z93TE135B 1Z93TE110W-2
+RV-093F 1Z93TE113Z 1Z93TE110Y-3 +RV-0936 1Z93TE113X 1293TE110X-4 1Z93TE113Y 1Z93TE110Z-5 l
'1293TE113W IZ93TE132B-6 J
1Z93TE135A I
+RV-093J 1Z93TE134B 1C61TE022B-1 +RV-093A 1Z93TE1122 1Z93TE133A-2 1Z93TE112X 1Z93TE111W-3 IZ93TE112Y' 1Z93TE111Y-4 -
1Z93TE112W 1Z93TE111X-5
-1Z93TE134A 1Z93TE111Z-6 1Z93TE133B-7 +RV-093B
+RV-093G +RV-093D
+RV-093K +RV-093E FIGURE 1 SP 29 923 92 Rev. C Page 8
. .. --.+
- - . . . . - , . ..--,,m, , , - - - . . . . . . , - , _ , _ _ _ . . , - . . , . - . , . _ . , . , _ - ,
-
