ML20151K390
| ML20151K390 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/22/1988 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| EA-88-051, EA-88-51, NUDOCS 8808030174 | |
| Download: ML20151K390 (30) | |
See also: IR 05000395/1988013
Text
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JUL 2 21988
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Docket No. 50-395
License-No. NPF-12
EA 88-51
South Carolina Electric and Gas Company
ATTN: Mr. D. A. Nauman, Vice President
Nuclear Operations
P. O. Box 88
Jenkinsville, SC 29065
Gentlemen:
SUBJECT: ENFORCEMENT CONFERENCE SUMMARY
(NRC INSPECTION REPORT N0. 50-395/88-13)
This letter refers to the Enforcement Conference held at our request on
June 24, 1988.
This conference concerned activities authorized for your
V. C. Summer facility.
The issues discussed related to the inoperability of
the service water system and an inadequate post trip review.
A list of
attendee:, a sunmary and a copy of your handout are enclosed.
We are
continuing our rev;aw of these issues to determine the appropriate enforcement
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action.
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2,
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Title 10, Code of Federal Regulations, a copy of this letter and its enclosures
will be placed in the NRC Public Document Room.
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Should you have any questions concerning this letter, please contact us.
Sincerely,
J. Nelson Grace
Regional Administrator
Enclosures:
1.
Enforcement Conference Summary
2.
List of Attendees
3.
Handout (s)
cc w/encis:
(See page 2)
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8808030174 880722
DR
ADOCK 05000395
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South Carolina Electric
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and Gas Company
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cc w/encis:
0. S. Bradham, Director, Nuclear
Operations
J. L. Skolds, Deputy Director,
Operations and Maintenance
J. B.~Knotts, Jr.
Bishop, Cock, Purcell & Reynolds
W. A. Williams, Jr. , Technical
Assistant, Nuclear Operations -
Saritee Cooper
A. R. Koon, Jr., Manager
Nuclear Licensing
R. E. Rainear, Executive Vice President,
South Carolina Public Service Authority
bec w/encis:
J. Lieberman, DOE
G. R. Jenkins, EICS
DRS, Technical Assistant
J. J. Hayes, Project Manager, NRR
Document Control Desk
State of South Carolina
NRC Resident Inspector
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JUL 2 21988
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ENCLOSURE 1
MEETING SUMMARY
On June 24, 1988, rep,resentatives of South Carolina Electric and Gas Company
(SCE&G) attended an Enforcement Conference at the request of the NRC in the NRC
Region II Office in Atlanta, Georgia.
The meeting was held to discuss NRC
concerns pertaining to a May 12, 1988 event where entry into Modes 2 and I were
made with both trains of the Reactor Building Cooling Units (RBCU) of the
Service Water (SW) System inoperable.
The post trip review failed to detect
that RBCUs were inoperable due to low SW flow.
The NRC Region II Deputy Regional Administrator opened the meeting by reviewing
the NRC concerns pertaining to the switching of operational Modes while both
trains of RBCUs were inoperable and the failure of the post trip review to
identify the discrepancy.
The Vice President of SCE&G gave an opening statement.
He then turned the
presentation over to his staff.
SCE&G representatives provided a presentation
discussing those topics indicated in the attached handout which was distributed
to meeting attendees by SCE&G.
Highlights of this presentation are provided
below:
The licensee provided the sequence of events, the reasons for the restart,
priority given to annunciators, post trip review, and post event actions.
A
system description was provided for the service water system technical specifi-
cation affected, performance history and future plans.
The licensee described
the reason why they failed to detect the low flow to the RBCUs in that they
reviewed the computer post trip review data, verified that SW pumps and SW
Booster pumps started and the pumps reached the required flow.
However, the
review did not go far enough to show that the flow started decreasing below the
minimum level after 120 seconds from the time the pumps started.
One of the
future plan actions to be incorporated is a graphical presentation of the post
trip data.
This will provide a more visible means to identify any parameter
below the required values.
The licensee stated that they took prompt correc-
tive action of declaring both trains inoperable after their independent review
determined SW flow to the RBCUs was below that required.
They claimed that
they did not violate the action statemente of the Technical Specifications.
They stated that at the time of Mode changes they were not aware of the low
flows, that they did an adequate post trip review and all systems were func-
tioning properly.
Nevertheless, corrective actions have been initiated to
prevent recurrence.
The NRC is presently considering enforcement action on this issue.
This
meeting served to enhance tne NRC's understanding of the event and corrective
actions taken to assure proper flow through the RBCUs.
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JUL 2 2 Iggg
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ENCLOSURE 2
LIST OF ATTENDEES
South Carolina Electric & Gas Company:
D. Nauman, Vice President, Nuclear Operations
0. Bradham, Director, fiuclear Plant Operations
J. Skolds, General Manager, Station Operations
G. Soult, Manager, Operations
G. Taylor, Associate Manager, Shift Engineering
J. Burke, Control Room Supervisor
R. Clary, Manager, Design Engineering
A. Koon, Manager, Nuclear Licensing
NRC Representatives:
M. Ernst, Deputy Regional Administrator
C. Hehl, Deputy Director, Division of Reactor Projects (DRP)
E. Merschoff, Deputy Director, Division of Reactor Safety
R. Goodard, Regional Counsel
G. Jenkins, Director, EICS
H. Dance, Chief, Projects Section 18, (DRP)
B. Uryc, Enforcement Specialist, Enforcement and Investigation
Coordination Staff (EICS)
L. Modenos, Project Engineer, Projects Section 18, DRP
R. Bernhard, Reactor Engineer, TPS, DRS
E. Reeves, Senior Project Manager, NRR
J. Hayes, Jr. , Project Manager, NRR
F. Jape, Chief, TPS, DRS
R. Prevatte, Senior Resident Inspector, Summer, DRP
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EHCLOSURE 3
LICENSEE 14EETlHG 80TES
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ENCLOSURE 3
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NRC ENFORCEMENT CONFERENCE
JUNE 24,1988
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ATLANTA, GEORGIA
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S C E & G ATTENDEES
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ENFORCEMENT CONFERENCE
June 24,1988
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Dan Nauman
- Vice President, Nuclear Operations
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Ollie Bradham - Director, Nuclear Plant Operations
Jack Skolds
- General Manager, Station Operations
Gene Soult
- Manager, Operations
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Gary Taylor
- Associate Manager, Shift Engineering
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Johnny Burke
- Control Room Supervi.sor
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Ron Clary
- Manager, Design Engineering
Al Koon
- Manager, Nuclear Licensing
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ENFORCEMENT CONFERENCE AGENDA
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June 24,1988
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Introduction
Dan Nauman
Vice President,
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Nuclear Operations
11.
Sequence of Events
initiating Event to Restart
Gene Soult
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Manager, Operations
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Gene Soult
Manager, Operations
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Post Trip Review
Gary Taylor
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Associate Manager,
Shift Engineering
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Post Event Actions
Gene Soult
Manager, Operations
lil.
Service Water System
Jack Skolds
General Manager,
Station Operations
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Description
Technical Specifications
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Performance History
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Future Plans
IV.
Summary / Conclusions
Ollie Bradham
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Director,
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Nuclear Plant Operations
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Gene Soult
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Sequence of Events
i nitiating Event to Restart
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CLOSURE OF "A" MSIV EVENT
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PART ONE
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A. PLANT WAS OPERATING AT 100% POWER - ON LINE 191 OF
THE PREVIOUS 192 DAYS.
B.
PERFORMING PARTIAL STROKE TESTING OF MAIN STEAM
ISOLATION VALVES WHEN " A" MSIV CLOSED.
C.
IMPLEMENTED EMERGENCY OPERATING PROCEDURE FOR
SAFETY INJECTION / REACTOR TRIP.
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D. IMPLEMENTED EMERGENCY PLAN PROCEDURES.
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CLOSURE OF " A" MSIV EVENT (CON'T.)
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OPERATOR RESPONSE TO ANNUNCIATORS
A. PRIORITY SCHEME
B. TRAINING ON ANNUNCIATORS:
1.
NORMAL PLANT CONDITIONS
2.
UPSET CONDITIONS
C. EMERGENCY OPERAflNG METHODOLOGY,
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POST TRIP REVIEW -
GARY TAYLOR
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Post Trip Review
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POST TRIP REVIEW
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PRELIMINARY REVIEW BY THE SHIFT ENGINEER
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- INDEPENDENT EVALUATION OF THE RX TRIP & Si
- DETERMINATION OF THE ULTIMATE CAUSE OF THE EVENT
- EVALUATION OF PLANT RESPONSE TO THE TRANSIENT
- VERIFICATION OF SAFETY EQUIPMENT
- COMPARISON TO THE TRANSIENT OF MARCH 17,198S
- DETERMINATION OF RELEASES TO THE ENVIRONMENT
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DOCUMENTS REVIEWED PRIOR TO START-UP
- OFF NORMAL OCCURRENCE REPORT *
- EOP 1.1, POST TRIP REPORT *
- PLANT COMPUTER SEQUENCE OF EVENTS *
- PLANT COMPUTER ALARM MESSAGES *
- PLANT COMPUTER POST TRIP REVIEW *
- TECHNICAL SUPPORT COMPUTER DISCRETE CHANGES LOG *
- TECHNICAL SUPPORT COMPUTER POST TRIP REVIEW
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[* DOCUMENTS REVIEWED PER SCE&G RESPONSE TO GENERIC LETTE
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RESOURCES EMPLOYED IN THE RESTART REVIEW
- ASSOCIATE l\\/1ANAGER, SHIFT ENGINEERING
- OPERATIONS ENGINEER
- ADMINISTRATIVE SHIFT ENGINEER
- ASSOCIATE MANGER, OPERATIONS
- MANAGER, OPERATIONS
- DUTY SHIFT SUPERVISOR
- DUTY SHIFT ENGINEER
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REVIEW OF SERVICE WATER TO THE RBCU'S
- VERIFICATION OF SW PUMP AND SW BOOSTER PUMP START
- VERIFICATION OF 4000 GPM TO THE RBCU'S
- PLANT COMPUTER ALARMS NOT PRESENT ON B TRAIN
- LACK OF HISTORICAL DATA FOR COMPARISON
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(DF6r)
- s sen start DATra 05/12/ B8
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5ECOND PRF-TRIP DATA *
18' %1:16
66.1
66.5
0.0
0.0
307.6
89.2
0.0
96.5
1008.6
967.1
8535.5
8976.6
80.8
81.0
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66.1
66.5
0.0
0.0
2P4.4
89.2
0.0
96.5
1002.9
964.4
8352.4
8882.2
80.8
81.0
84 :51:36
66.1
66.6
0.0
0.0
161.1
89.2
0.0
96.5
1005.7
962.4
8246.7
8874.1
80.8
80.9
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66.1
66.6
0.0
0.0
140.8
89.2
0.0
96.5
996.6
968.9
8457.1
8704.3
80.8
80.9
'48%3:56
66.1
66.6
0.0
0.0
J33.8
89.3
0.0
96.5
994.4
967.5
8315.1
8773.0
80.8
80.9
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- 52:06
66.1
66.6
0.0
0.0
402.2
89.3
0.0
96.5
999.9
967.5
8465.2
9048.7
80.8
80.9
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66,1
66.6
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0.0
418.9
89.3
0.0
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992.3
964.2
8565.6
,8569.7
80.8
80.9
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66.1
66.6
0.0
0.0
140.8
89.3
0.0
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908.5
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8482.7
8606.2
80.4
80.9
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lECOND POST-TRIP DATA *
las%2:3n
66,1
66.6
0.0
0.0
372.6
89.3
0.0
96.5
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999.6
971.3
8470.4
8790.1
80.8
80.9
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66.1
66.6
1420.9
1079.7
1632.8
89.3
1574.7
96.5
965.5
941.1
9855.3
8361.4
80.8
80.9
!*:52:56
66.1
66.6
2094.2
1736.9
1959.4
89.2
1880.3
96.5
956.7
936.3
9650.7
7828.4
80.7
80.9
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66.1
66.6
5000.05 46n7.5
3310.1
89.2
1363.6
96.5
802.1
861.1
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80.7
80.9
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66.1
66.6
4300.4
3989.7
3955.1
89.2
3677.7
96.5
908.8
901.2
7303.0
7449.1
80.7
80.9
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66.1
66.6
4422.3 4082.7
4107.8
89:2 4077,a
94:1_
908.8
879.9
7170.1
7559.7
80.7
80.9
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66.1
66.6
4408.1
4119.0
4182.9
87,8
4002.3
92.5
906.7
887.4
7442.4
7866.8
80.7
00.9
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66.1
66.6
4420.1
4122.1
4120.4
87.2
4055.9
90.1
910.3
890.0
7432.2
7630.0
80.7
80.9
!4:53:56
66.1
66.6
4392.9
40*9.3
4099.5
86.7
4064.1
89.4
908.9
886.3
7393.2
7653.4
80.5
80.9
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66.1
66.6
4170.1 4057.0
3874.4
87.J
4069.2
89.4
921.6
892.0
7499.6
7807.5
80.5
80.9
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66.1
66.6
4006.8
4127.5
3663.7
G6.7
4065.3
89.4
923,6
890.8
7462.2
7635.8
80.5
80.9
14:54 26
46.1
66.6
3929.0 3958.4
3666.0
83.3
3844.6
89.4
91986
083.3
7559.2
7666.6
80.5
80.9
!48%4:36
64.1
66.6
3925.9
3184.9
3672.6
80.0
3124.6
86.6
91 Sol
896.0
7584.6
7860.1
80.5
88.9
!*:54:46
66.0
66.6
3919.4 2575.8
3687.1
77.1
2514.4
R3.3
918e6
912.4
7573.0
7708.7
80.5
88.8
l0 :54:56
66.0
66.6
39J8.7 2288.5
3695.2
74.8
2264.3
80.9
921e4
927.9
7523.4
7965.7
80.4
80.8
!0:55 06
66.0
46.6
3902.9 2146.7
3675.7
73.3 2073.7
77.9
922 8
932.6
7442.4 - 8204.0
80.4
88.8
I:55:16
66.0
66.6
3939.2 2091.0
3654.9
72.0
2026.8
76.3
918.92
928.4
7551.8
8499.0
80.4
80.8
O
0:55:26
66.0
66.6
3950.1 2647.8
3676.1
71.4
1975.7
75.1
919.0
931.8
7568.0
8184.0
80.4
80.8
,0:55:36
66.0
66.6
3920.8
1971.1
3666.2
70.8
1968.4
73.7
923.4
936.9
1482.4
8266.9
88.4
80.8
'0:55:46
66.1
66.6
3937.7
1933.6
3701.0
70,2
2905.7
73.2
916,9
934.8
7652.2
8124.7
80.4
80.8
0:45 56
66.1
66.6
3923.1
1961.8
3640.9
69.8
1935.5
72.6
925.5
931.6
7515.1
8363.3
88.4
80.8
0:56:06
66.1
66.6
3902.9
1961.8
3705.1
69.8
1914.5
72.6
922.8
935.5
7455.4
4145.9
80.4
80.8
Pa%6: 16
66.1
86.6
3922.7
1977.6
3637.1
69.8
1958.1
72.0
924.4
933.9
7412.7
8344.5
80.4
80.8
p 96:24
66.1
66.6
3942.3
1916.1
3636.9
69.0
1937.1
,73.0
918.4
932.5
7521.7
8491.6
80.4
80.8
P56:33
66.1
66.6
3912.6
1955.5
3725.6
69.8
1926.0
72.0
919.2
930.6
7513.8
8285.1
80.4
80.8
0:56:46
66.1
66.5
39:3.4
1942.2
3670.9
69.4
1969.9
51.5
924.5
934.1
7561.3
8332.0
80.4
80.7
355:53
66.1
66.5
3901.3
1986.4
3640.3
69.2
1908.5
71.5
928.4
937.5'
7510.0
8495.3
80.3
80.7
397:06
66.1
66.5
3897.8
1910.1
3618.2
69.2
1877.9
'71.5
920.4
933,9
741n,7
80g7.2
80.3
80.7
357:16
66.1
66.5
3902.3
1908.1
3645.3
69.2
1884.0
71.5
919.2
932.3
7570.9
8271.1
80.3
80.7
D:57:26
66.1
66.5
3901.3
18*2.1
3644.5
69.2
1909.3
71.5
922.9
935.6
7525.5
8218.9
80.3
80.7
' Ora stAPT DATra 05/12/88
- 1 M NUTE PnST= TRIP DATA *
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ISEG POST TRIP REVIEW
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- INDEPENDENT EVALUATION OF THE RX TRIP & SI
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POST TRIP ENHANCEMENTS
- STRUCTURED POST TRIP REVIEW
a. GRAPHICAL PRESENTATION OF POST TRIP DATA
b. PLANT RESPONSE CHECKLIST
c. REVIEW GUIDE WHICH WILL INCLUDE NORMAL
OPERATING BANDS , INSTRUMENT SETPOINTS,
CONTROL AND PROTECTION FUNCTIONS AND
TECHNICAL SPECIFICATIONS
- PLANT & TSC COMPUTER REPLACEMENT IN PROGRESS
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POST EVENT ACTIONS - GENE SOULT
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EXAMPLE OF THE NEW GRAPHICAL FORMAT
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MAY 12,1988
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POST EVENT ACTIONS
PART 11
l.
OPERATIONS MANAGEMENT NOTIFIED OF POSSIBLE LOW SW
FLOW TO RBCU..
A. DECLARED BOTH TRAINS INOPERABLE BASED ON POST TRIP
DATA.
B.
INITIATED TESTING OF SW TO RBCU'S.
C.
DECLARED " A" TRAIN SW TO RBC f5 OPERABLE.
,
D. CHECKED FUNCTIONAL SYSTEM COMPONENTS.
E.
INITIATED CHEMICAL FLUSH "6" TRAIN RBCU'S.
F.
DECLARED "B" TRAIN SW TO RBCU'S OPERABLE.
G. CHEMICAL FLUSH OF " A" TRAIN.
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POST-EVENT ACTIONS (CON'T)
11.
INCREASE FREQUENCY FROM 18 MONTH SURVEILLANCE OF FLOW
TO MONTHLY FLOW VERIFICATIONS.
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A. TESTED " A" SWBP SAT ON 6/21/88.
Ill.
OBSERVED REDUCED FLOW OF SW TO "B" TRAIN RBCU'S
A. INSPECTED SW PUMP BAYS FOR CLAM INFESTATION.
B.
PERFORMED a P CHECKS OF VARIOUS "B" TRAIN HEAT
EXCHANGERS.
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IV.
SIMULATED BLACKOUT TESTING FOR WORST CASE TRANSIENT ON
SYSTEM
V.
SERVICE WATER SYSTEM - JACK SKOLDS
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Jack Skolds
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Service Water System
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SERVICE WATER / REACTOR BUILDING
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COOLING UNITS
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' System Description
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Technical Specifications
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Problems Encountered
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Future Plans
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PLANT SYSTEMS
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3f,4_.7.4
SERV!CE WATER SYSTEM
L_IMITING CONDITION FOR OPERATION
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3.7.4
At least.two independent service water loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one service water loop OPERABLE, restore at least two loops to
OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I
SURVEILLANCE REQUIREMENTS 4.7.4
At least two service water loops shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (ma'nual,
a.
power operated or automat 1c) servicing safety related equipment that
is not locked, sealed, or otherwise secured in position, is in its
correct position.
SUMMER - UHli 1
3/4 7-12
Amendment No. 21
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CONTAINMENT SYSTEMS
REACTOR BUILDING COOLING SYSTEM
LIMITING CONDITIONS FOR OPERATION
3.6.2.3
Two independent groups of reactor building cooling units shall be
OPERABLE with at least one of twc cooling units OPERABLE in slow speed in each
group.
.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one group of the above required reactor building cooling units
a.
inoperable and both reactor building spray systems OPERABLE, restore
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the inoperable group of cooling units to OPERABLE status within
l
7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in
COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l
b.
With two groups of the above required reactor building cuoling units
inoperable, and both reactor building spray systems OPERABLE, restore
at least one group of cooling units to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore both above required
groups of cooling units to OPERABLE status within 7 days of Initial
loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in
COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With one group of the above required reactor building cooling units
c.
inoperable and one reactor building spray system inoperable, restore
the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be
in at least HOT STANDBY within the next 6 hcurs and in COLD SHUT 00WN
within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore the inoperable group of
containment cooling units to OPERABLE status within 7 days of initial
loss or be in at least HOT STAN0BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in
COLO SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVE*LLANCE REQUIREMENTS
4.6.2.3
Each group of reactor building cooling units shall be demonstrated
OPERABLE:
a.
At least once per 31 days by:
1.
Starting each cooling unit group from the control room, and
verifying that each cooling unit group operates for at least
15 minutes in the slow speed mode.
b.
At least once per 18 months by:
1.
Verifying that each f an group starts automatically on a safety
injection test signal.
2.
Verifying a cooling water flow rate of greater than or equal to
g
4,000 gpm to each cooling unit group.
N
SUMMER - UNIT 1
3/4 6-14
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SERVICE WATER SYSTEM HISTORY
3/87
Identified High Ap on B Train RBCU.
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Inspected RBCU 28 Cooler (Worst Ap) with
Fiberscope. Clean and very few clams. (2 of 22
tubes)
Inspected CCW HX. Very few clams.
4/87
Reviewed design data of coolers and pumps.
Reviewed Section XI test data.
Ran Flow Balance Test. Met flow rate for 95 F.
Ap's were very close to design requirements.
S/87
Ran integrated safeguards test. Satisfactory.
Provided guidance to Operations.
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FUTURE PLANS
Modification to RBCU Valves, to increase flow
marg'in
- 2000 gpm requirement
- Technical Specification change approved
Possible Strainer / Bypass Loop
More Sophisticated Testing
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"C" SW Pump
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- More instrumentation
Emergency Feedwater Crossconnect
- Visualinspection Refuel 4
- Possible Flush / Filter (Later)
Determine Cause of Flow Degradation
e
- Presently do not believe cause to be clams
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Ollie Bradham
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Summary / Conclusions
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NRC ENFORCEMENT CONFERENCE
' JUNE 24,1988
SUMMARY
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WE DID NOT VIOLATE SPECIFICATION
3.0.4.
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MANAGEMENT FOCUS ON SAFETY
VERSUS ECONOMICS
CHECKS AND BALANCES WORKED
DEDICATED TO RESOLVING PROBLEM
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