|
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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20141C2841997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Monticello Nuclear Generating Plant ML20137W2621997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Monticello Nuclear Generating Plant ML20136H1671997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Monticello Nuclear Generating Plant ML20134M7071997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Monticello Nuclear Generating Plant ML20133J1401996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for Monticello Nuclear Generating Plant ML20132A8771996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Monticello Nuclear Generating Plant ML20134L2761996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Monticello Nuclear Generating Plant ML20128Q7831996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Monticello Nuclear Generating Plant ML20117M8161996-08-31031 August 1996 Monthly Operating Rept for Aug 1996 for Monticello Nuclear Generating Plant ML20116M2991996-07-31031 July 1996 Monthly Operating Rept for July 1996 for Monticello Nuclear Generating Plant ML20115H5651996-06-30030 June 1996 Monthly Operating Rept for June 1996 for Monticello Nuclear Generating Plant ML20112J1921996-05-31031 May 1996 Monthly Operating Rept for May 1996 for Monticello Nuclear Generating Plant ML20112A3121996-04-30030 April 1996 Monthly Operating Rept for Apr 1996 for Monticello Nuclear Generating Plant ML20107E9831996-03-31031 March 1996 Monthly Operating Rept for Mar 1996 for Monticello Nuclear Generating Plant ML20106H0591996-02-29029 February 1996 Monthly Operating Rept for Feb 1996 for Monticello Nuclear Generating Plant ML20100G5031996-01-31031 January 1996 Monthly Operating Rept for Jan 1996 for Monticello Nuclear Generating Plant ML20096C8061995-12-31031 December 1995 Monthly Operating Rept for Dec 1995 for Monticello Nuclear Plant ML20095G0231995-11-30030 November 1995 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20094L1921995-10-31031 October 1995 Monthly Operating Rept for Oct 1995 for Monticello Nuclear Generating Plant ML20093E6241995-09-30030 September 1995 Monthly Operating Rept for Sept 1995 for Monticello Nuclear Generating Plant ML20092F4121995-08-31031 August 1995 Monthly Operating Rept for Aug 1995 for Monticello Nuclear Generating Plant ML20087H3011995-07-31031 July 1995 Monthly Operating Rept for Jul 1995 for Monticello Nuclear Generating Plant ML20086K1731995-06-30030 June 1995 Monthly Operating Rept for June 1995 for Monticello Nuclear Generating Station 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2061999-10-12012 October 1999 Safety Evaluation Supporting Amend 106 to License DPR-22 ML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With 05000263/LER-1999-007, :on 990610,HPCI Test Return Valve Was Unable to Close Against Max Expected Differential Pressure.Caused by Failure to Accurately Predict Valve Performance.Procedure Revised.With1999-07-0909 July 1999
- on 990610,HPCI Test Return Valve Was Unable to Close Against Max Expected Differential Pressure.Caused by Failure to Accurately Predict Valve Performance.Procedure Revised.With
05000263/LER-1999-006-01, :on 990602,during Quarterly Surveillance Hcpi Was Declared Inoperable.Caused by Drain Pot Alarm.Revised HPCI Surveillance Test Procedure.With1999-07-0202 July 1999
- on 990602,during Quarterly Surveillance Hcpi Was Declared Inoperable.Caused by Drain Pot Alarm.Revised HPCI Surveillance Test Procedure.With
ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With 05000263/LER-1999-005, :on 990508,personnel Inserted Manual Scram When Pressure Transient Closed Air Ejector Suction Isolation Valves & Tripped off-gas Sys.Caused by Recombiner Catalyst Migration.Catalyst Was Removed.With1999-06-0707 June 1999
- on 990508,personnel Inserted Manual Scram When Pressure Transient Closed Air Ejector Suction Isolation Valves & Tripped off-gas Sys.Caused by Recombiner Catalyst Migration.Catalyst Was Removed.With
ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With 05000263/LER-1999-004-01, :on 990422,low Reactor Water Level Scram,Group 2 & 3 Isolations & Subsequent HPCI Became Inoperable.Caused by Feedwater Controller Power Supply Failure.Three Power Supplies Replaced & Connections Cleaned.With1999-05-24024 May 1999
- on 990422,low Reactor Water Level Scram,Group 2 & 3 Isolations & Subsequent HPCI Became Inoperable.Caused by Feedwater Controller Power Supply Failure.Three Power Supplies Replaced & Connections Cleaned.With
05000263/LER-1999-003-01, :on 990412,HPCI & Division 1 ECCS Equipment Were Declared Inoperable Due to Svc Water Pump Failure.Pump Shaft Was Mechanically Freed,Check Valve Was Repaired & Pump Was Successfully Tested.With1999-05-12012 May 1999
- on 990412,HPCI & Division 1 ECCS Equipment Were Declared Inoperable Due to Svc Water Pump Failure.Pump Shaft Was Mechanically Freed,Check Valve Was Repaired & Pump Was Successfully Tested.With
05000263/LER-1999-002-01, :on 990329,event Sequence That Results in Available ECCS Being Reduced to Less than That Assumed in Current Safety Analysis.Caused by Failure of Edg.Plant Operating Procedures Revised.With1999-05-11011 May 1999
- on 990329,event Sequence That Results in Available ECCS Being Reduced to Less than That Assumed in Current Safety Analysis.Caused by Failure of Edg.Plant Operating Procedures Revised.With
ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20205C1651999-03-19019 March 1999 Safety Evaluation Supporting Amend 105 to License DPR-22 ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 05000263/LER-1999-001-02, :on 990215,HPCI High Steam Flow Isolation During Quarterly Surveillance Test Was Noted.Caused by Inadequate Surveillance Procedure.Revised Surveillance Procedure.With1999-03-17017 March 1999
- on 990215,HPCI High Steam Flow Isolation During Quarterly Surveillance Test Was Noted.Caused by Inadequate Surveillance Procedure.Revised Surveillance Procedure.With
ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198M8221998-12-24024 December 1998 Safety Evaluation Supporting Amend 104 to License DPR-22 ML20198M6901998-12-23023 December 1998 Safety Evaluation Supporting Amend 103 to License DPR-22 ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv 05000263/LER-1998-005-01, :on 980921,HPCI Was Removed from Service to Repair Steam Leak in Drain Trap by Pass.Caused by Localized Erosion of Valve Body.Valve Was Declared Inoperable & Was Replaced with Manual Valve1998-10-21021 October 1998
- on 980921,HPCI Was Removed from Service to Repair Steam Leak in Drain Trap by Pass.Caused by Localized Erosion of Valve Body.Valve Was Declared Inoperable & Was Replaced with Manual Valve
05000263/LER-1998-004-02, :on 980909,manual Scram Was Inserted Following Pressure Transient Closed Air Ejector Suction Isolation Valves & Trips Offgas Recombiners,Occurred.Caused by Seat Leakage.Leaking Valve Seat Was Reworked1998-10-0909 October 1998
- on 980909,manual Scram Was Inserted Following Pressure Transient Closed Air Ejector Suction Isolation Valves & Trips Offgas Recombiners,Occurred.Caused by Seat Leakage.Leaking Valve Seat Was Reworked
ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20151T0981998-08-28028 August 1998 Safety Evaluation Supporting Amend 101 to License DPR-22 ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant 05000263/LER-1998-003-01, :on 980417,transgranular Stress Corrosion Cracking Was Identified in Control Rod Drive Lines.Caused by chloride-induced Transgranular stress-corrosion Cracking. Affected Sections of Two Lines Replaced1998-05-14014 May 1998
- on 980417,transgranular Stress Corrosion Cracking Was Identified in Control Rod Drive Lines.Caused by chloride-induced Transgranular stress-corrosion Cracking. Affected Sections of Two Lines Replaced
05000263/LER-1998-002-02, :on 980415,main Steam Isolation Valve Position Setpoint Outside Allowed Range,Was Found.Caused by Previous Testing Technique & Use of Particular Switch Model.Eight New Position Switches W/Less Deadband Installed1998-05-14014 May 1998
- on 980415,main Steam Isolation Valve Position Setpoint Outside Allowed Range,Was Found.Caused by Previous Testing Technique & Use of Particular Switch Model.Eight New Position Switches W/Less Deadband Installed
ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant 05000263/LER-1998-001-02, :on 980323,discovered Containment Isolation Valve Leakage Exceeded TS Limit.Caused by Foreign Matl Found on Valve Seat.Repaired Subject Valves & Developed Process to Ensure Cleanliness of Testing Equipment1998-04-22022 April 1998
- on 980323,discovered Containment Isolation Valve Leakage Exceeded TS Limit.Caused by Foreign Matl Found on Valve Seat.Repaired Subject Valves & Developed Process to Ensure Cleanliness of Testing Equipment
ML20217E9611998-04-20020 April 1998 Safety Evaluation Supporting Amend 100 to License DPR-22 ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant 1999-09-30
[Table view] |
Text
t
.s o'. '
Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401-1927 Telephone (612) 330-5500 i
1, cy 11, 1992 Monticello Technical Specifiestions l
Section-6.7.A.3 VS Huclear Reginatory Commission Attn: Document control Desk Washington, DC 20555 MONTICELLO NUCIIAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Monthly Operating Report January. 1902 Attached is the Monthly Operating Report for January,1992 for the Monticello Nuclear Generating Plant.
/NM0 ' ic![W
' Thomas M Par er Manager Nuclear. Support Service TMP/
C:
Director, Office of.Resua:ce Management Regional Administrator-III, NRC NRR Project Manager, NRC NRC Resident Inspector MPCA Attn: J W Ferman Attachment
[)S 92o21eo323 920:33 p
roa. aooCM osooo m R
PDR
OPERATING DATA REPORT 3.
a*
. DOCKET'NO. 263 DATE-2a 4-92 I
-COMPLETED BY H. H. PaustianI 7
TELEPHONE 612/295-5151-OPERATING-STATUS-
~I
] Notes
-)
- 1. ; Unit :Nameo ::
Monticello
)
)
! 2.J: Reporting period: -
- January
)
-)
.3.iLicensed Thermal Power (MWt):
1670
)
)
- 14. Nameplate Rating (Gross MWe):
569
).
)
4 5,. Design Electrical-_ Rating (Net MWe):=
545.4
-)
)-
-46? Maximum Dependable Capacity (Gross: MWe)
.,_._5 6 4
)
.]
L7._ Maximum Dependable' Capacity.(Net MWe):
536
)
J-
- 8. If Changes Occur-in Capacity Ratings (Items Number 3 Through 7) Since Last Report,:Give Reasons:
l
- 9. Power Level;To Which Restricted, If Any_(Net MWe):
N/A
- 10. Reasons-For Restriction's,- If Any:'
_N/A_
iO THIS MONTH-YR.-TO-DATE
-CUMULATIVE-744 744 180481
.~11.5 Hours In Reporting _ Period 675.1 675.1 144093.5-
- 12.LNuriber Of hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 940.7-
- 14.tHours Generator On-Line 656.8 656.8 14140<' 7 15.-Unit Reserve Shutdown Hours O' 0 0.0
- 0. 0 -
- 16.-, Gross Thermal Energy Generated (MWH)-
_1078193 1078193 216611770
?17.-Gross Electrical Energy = Generated:(MWH) 362863-362863 73252708 2
118. Het Electrical Energy.' Generated (MWH)
-348400--
348400 70050618 19;-Unit-Service Factor:
-88.3%
88 3%
78.3%-
h 88.3%
88.3%
78.3%
- 20. Unit Availabil-ity Factor
~
21.iUnit1 Capacity Factor;(Using MDC Net) 87.4%
87.4%
72.4%
J22.sUnitz; Capacity; Factor-(UsingLDER Net) 85.9%-
85.9S 71.2%
23.iUnit Forced-Outage Rate 9.4%-
9.4%-
3.9%
24.s Shutdowns Scheduled Over Next 32 Months (Type,-Date, and' Duration of Each)
- Refueling; Outage
-1/6/93 - 56 days
'L25.olf Shut Down At End Of Report Period, Estimated Date Of Startup:N/A
^ 26.i Units :In Test f Status (Prior to Commerciak Operation) :- N/A Forecast Achieved-
, INITIAL CRITICALITY
-INITIAL ELECTRICITY COMMERCIAL OPERATTON s
4 y
,.,,2
.g...
_ay.,
,,m.
a.
~ NARRATIVE :
SUMMARY
iOF~. OPERATING EXPERIENCE DOCKET NO.
50-263-J DATE 2-4-92 COMPLETED-BY H. - li. Paustian:.
~'
TELEPHONE.'612/295-5151 MONTIl-JAN i1-1. to
. Power operation.
- 1-2-92.
- 1-2-92 to:
Outiage; to repair Safety Relief Valve Bellows Leak Test 1-6-92 System.
-1~-6-92 toL 1-9-92-_.
Power operationi
+
n J1-9-92 Power reduction'to-70% te backwash Condensate Demineralizer.
.1-9 to-Power operation.
- 1-24 L1-24 Power reduction to-80% due to ice in Intake Structure.
'1-24-92.-
to -
Power. operation.
1-31-92 I
i Note: Power operation defined as essentially 100% of
' rated power except for weekend load drops for 4
specified surveillance testing.
l
..m-.
.~.
a AVERAGE DAILY-UNIT-POWER LEVEL
~,y DOCKET NO.
50-263
.i
' UNIT-Monticello_.,_'
DATE~
'2-'4-92 COMPLETED BY H.-H.'Paustian j
L TELEPHONE 612/295-5151-p i
MONTH OF._ January
-DAY = -AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.
P (MWe-Net)
(MWe-Net)
L 11 542.
17 544.
-2
'313.
18 544.
L L3;
-6.
19 539.
4
- - 6 ~.
20 541.
5 -'
-7.
21 543.
-- 6 --
213.
22 540.
I'
- 7; 522.
23 543.
8?
- 543, 24 518.
o-
- 9:
514.
25 535.
l-
's b
10 ;-
540.
26 530.
11-.
'543.
27 549.
P
- 12'
- 542, 28 537.
13-
- 541, 29 549.
4 14' 543.
30 528.
~
e15 546.
~31 552.
216'-
539.
-INSTRUCTIONS
.On'this' format, list the average daily unit power level in MWe-Net-for each day:in_the~ reporting month.
Compute to the nearr.3t whole megawatt.
L l'
t-l l
~
UNIT SHUTDLNNS AND POVER REDUCTIONS DOCKET NO.
50-263 V
UNIT NAME Monticello DATE 02-0-92 COMFLETED BT 11. H. rauscian REPORT MONTH January-TELEPHONE _,612/295-5151-Duration Reason Method LER' System Cause & Col ective Ty(pe (hours)
(2) of
. No.
Code No.
.Date e-Action to-1)
Shutdown (4)
(5) I Prevent Recurrence
.(3)
{
1 01-02-92 F
87.2 A
'2 92-001 SB FSV I Shutdown required to re ir solenoid valves on Bellows Leak Detection oystem for 2 Safety Relief.
Valves.
2 01-09-92 F.
O H
4 N/A SF FDM
. Power reduction to 70% required to backvash..
Condensate Demineralizer.
3 01-24-92 F'
O H
4 N/A NN N/A Icing problems in Cire. Vater Intake Structure required power reduction to 80%.
t l
1 2
3 4
F: Forced Reason:
Method:
Draft IEEE Standard S: Scheduled A-Equipment Failure (Explain) 1-Manual 805-1984(F805-D5)
B-Maintenance or Test -
2-Mantal Scram C-Refueling 3-Automatic Scram 5
D-Regulator Restriction 4-Other (Explain)
IEEE Standard 803A-1983
.E-Operator Training & License Examination F-Administrative G-Operational Error.(Explain)
H4ther. (Explain)