ML20023B354
| ML20023B354 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/28/1983 |
| From: | Bournia A Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8304060029 | |
| Download: ML20023B354 (4) | |
Text
-L DISTRIBUTION:
{'NRCPDR' Document Contro hlAR 2 8 1983
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~~
L PDR NSIC PRC Docket No. 50-374 LB#2 Rdg.
EHyl ton ABournia CWoodhead OELD APPLICANT: Comonwealth Edison Company WHLovelace adison, R.I.
FACILITY la Salle County Station, Unit 2
SUBJECT:
SUMMARY
OF CASELOAD FORECAST PANEL MEETING AND SITE VISIT In a letter dated February 1,1983, the applicant projected a fuel load date for La Salle County Station, Unit 2 of August 30, 1983 instead of the scheduled April 1983 date. On March 21-23, 1983, the Caseload Forecast Panel visited the site to try to determine its fuel load date projection. The meeting agenda (Enclosure 1) and the list of attendees (Enclosure 2) are attached.
The applicant indicated that Unit 2 was approximately 971 complete and that the initial construction should be completed by early May 1983. The pacing item for which fuel load date was being impact was the completion of the pre-opemtional testing required to be completed prior to fuel load. However, the applicant stated that out of 71 pre-operational testing required 12 tests i
have been completed to date giving them confidence that the fuel load date of
{
l August 31, 1983 can be attained. We requested that the applicant give us the pre-operational testing schedule which was utilized to obtain this fuel load i
date. The applicant indicated that with the experience gained on Unit 1 knowing the testing to be done, knowing the system available for testing, and the man-power available, they were very confident that the fuel load date of August 31, 1983 could be met.
After reviewing the data presented (see Enclosure 3) to the Caseload Forecast Panel and touring the facility, we agreed with the applicant that the pacing item would be the pre-operational testing. However, we indicated that there were two potential problems that could impact the schedule:
(1) repairing and fixing anomalies discovered during these pre-operathnal testing, and (2) timely responses with information required for the staff to complete its review for the license.
The panel also specified that we did not have the confidence that the applicant asserted with respect to its fuel load date. Our projection indicates that the earliest fuel load date was more like late December 1983. Our method used to arrive at the fuel load date was as follows:
(1) Since the staff has been doing these forecast assessments, data indicate that the last 10% completion from 90% to 100% of pre-operational testing have taken from 3 to 5 months to complete.
l La Salle Unit 1 took 5 months. For our projection, we assumed 4 months, l
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OFFICIAL RECORD COPY usom mi--sma NRC FORM 318 (10-80) NACM 024o
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- (2) A chart of percentage completion of pre-operational testing per month indicate that Unit '2 has been completing approximately 8%
testing per month in the last three months.
If we took a longer span, this is more like 6%.
For our projection, we assumed 7.7%
per month, the actual number.
Taking this slope of 7.7% testing completion per month to 90% completion of pre-operational testing and adding 4 months to complete the last 10%, the resulted completion date is late December 1983 or early January 1984 There-fore, the Caseload Forecast Panel projects that the earliest fuel load date to be late December 1983. We indicated to the applicant that this date would be our recommendation to our management.
OJ@Lul wnd W A. Bournia, Project Manager Licensing Branch No. 2 Division of Licensing cc w/ enclosures:
See next page n,
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m, y OFFIClAL RECORD COPY usam mi-sam nnc ronu ais00-803 nacu o:4a
La Salle Mr. Dennis A. Farrar Director of Nuclear Licensing Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 cc:
Philip P. Steptoe, Esquire Suite 4200 One First National Plaza Chicago, Illinois 60603 Dean Hansell, Esquire Assistant Attorr.ey General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 William G. Guldemond, Resident Inspector LaSalle NPS, U.S.N.R.C.
P. O. Box 224 Marseilles, Illinois 61364 C
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t4 ENCLOSURE 2 CASELOAD FORECAST PANEL REVIEW ATTENDEES LA SALLE COUNTY STATION, UNIT 2 March 21,1983 Name Organization C. W. Schroeder CECO - Licensing D. L. Farrar Ceco - Licensing D. L. Shamblin CECO - Construction Supt.
G. R. Crane Ceco - Engineering B. R. Shelton Ceco - Project Eng. Mgr.
W. H. Lovelace NRC A. Bournia NRC R. D. Bishop Ceco - Assist. Supt.
R. H. Holyoak CECO - Project Manager A. L. Madison NRC - Resident Inspector G. J. Diederich Ceco - Superintendent March 22,1983 R. D. Bishop CECO - Assist supt.
W. R. Huntington Ceco - Technical Staff W. Vahle CECO - Construction W. H. Lovelace NRC A. Bournia NRC March 23,1983 C. W. Schroeder Ceco - Licensing R.'D. Bishop Ceco - Assist. Supt.
i W. R. Huntington CECO - Technical Staff i
D. L. Shamblin CECO - Construction Supt.
B. R. Shel ton Ceco - Project Eng. Mgr.
E. E. Spitzner CECO - Startup Coordinator R. H. Holyak Ceco - Project Manager A. L. Madison NRC - Resident Inspector W. G. Guldemond NRC - Sr. Resident Inspector i
A. Bournia NRC W. H. Lovelace NRC
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ENCLOSURE 3 l
NRC CASE LOAD FORECAST AGENDA March 21, 1983 I ntro du c tio n........................
C. W. Schroeder Organization, Overview - Project Schedule Questions #1, #6, #11..................
R. H. Holyoak Design, Engineering, Licensing Requirements,10CFR-50.55 QJestions #2, #9, #10......,............
- 8. R. Shelton Procurement, Craft Work Force, Piping Status, Construction Overview Qu estio ns #3, #4, # 5, #7.................
D. L. Shamblin Preoperational Procedure and Testing Status Qu e s t i o n # 8.......................
R. D. Bishop Conc 1'usion.........................
R. H. Holyoak i
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ST ATION STARTUP SUPERINTENDENT PROJECT l
P R O J E~C T PROJECT CONSTRUCTION OPER ATION AL AN ALYSIS S
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Procedure Approval 80%
by PED 56%
87%
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System Turnover f or Preop Testing Preop Testing 20%
52%
Possible Preop Testing i
16%
48%
Complete.
7%
21%
Preop Results Approved by PED 2%
5%
Systems Released f or Operation 4
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Unit 2 Design & Engineering Status t
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e Structural e
Mechanical All Design Issued
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Hangers Q
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Field Problem Resolution On The Above
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e Paperwork Closeout Comprise The Total Current Design Effort n
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e Al1 N-5 Forms Should Be Signed 4/30 11 of 47 Signed By Engineering i
L, 5 of 47 Signed By ANI i
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License Conditions On U#1 Applicable-to U#2 Administrative Items 18 Generic or U#1 only 17 (no U#2 impact)
Complete on U#2 8
Expect Completion by 8
U#2 Fuel Load In-Progress on 10 U#2 - longer term Awaiting NRC Action 6
l Total 67 BRS 3-18-83
Administrative Items 2.C.(1)
Full Power Level License 2.C.(2)
Technical Specifications 2.C.(3)
Conduct of Testing 2.C.(6)
Deferred Preop Deficiency Resolution 2.C.(9)
Pump and Valve ISI 2.C.(13)
Control Blade Surveillance 2.C.(25)(a)
Fire Protection Program 2.C.(27)(a)(b)(c) Security Program 2.C.(28)
Initial Test Program Rules 2.C.(30)(b)
General Electric Review of Procedures 2.C.(34)
One Loop Operation 2.D.
10CFR73 and 10CFR50.44 Exemptions 2.E.
Environmental Matters 2.F.
Reporting to the NRC 2.G.
Financial 2.H.
40 year License BRS 3-18-83 4
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m Generic or Unit 1 Only (no Unit 2 impact) 2.C.(4)*
Offgas Roof Damage 2.C.(12)(a)*
Fuel Lift Submittal 2.C.(16)*
Containment LTP 2.C.(18)*
Regulatory Guide 1.97 2.C. (19)
- I&C Concerns, 90-Day Report 2.C. (24)
Cable Test 2.C.(25)(b)*
Fire Barrier DG Corridor 2.C. (25) (e)
Record Storage
- 2. C. (26)
- Rad / Chem Techs on Backshif t 2.C. ( 29)
- Teledyne Review 2.C.(30)*
SCRE 2.C.(30)(c)*
Onsite Safety Group 2.C.(30)(e)
Loss of AC Power 2.C.(30)(h)*
Post Accident Instrumentation 2.C.(30)(o)*
Emergency Facilities 2.C.(30)(p)*
Emergency Preparedness 2.C. (33)*
HVAC Review BRS 3-18-83
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L Complete For U#2 1
2.C.(10)(a)
SQRT 2.C.(10)(b)
Drain Valves Replaced 2.C.(23)
Electric Penetration Fault Protection
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2.C.(30)(j)
-RCIC Logic for Auto Restart 2.C.(30)(k)
RCIC Break Detection 2.C.(30)(m)
Auto Restart LPCS & HPCS 2.C.(30)(n)
Auto Switchover RCIC Suction 2.C.(32)
Vacuum Breaker Mods Installed l
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Snubber List for Tech Spec 2.C.(7)
Tendon Surveillance Data for Tech Spec.
2.C.(14)(a).
Scram Discharge Volume 2.C.(17).
ECCS A P Interlock 2.C.(25)(c).
Fire Protection Mods 2.C.(30)(d)
U#2 Control Room Like U#1 2.C.(30)(f)
HRSS 2.C.(31)
Valve Bolting Checks l
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In-Progress U#2 2.C.(5)(b)
Snubber Reduction Program 2.C.(ll)
EQ 2.C.(15)
Low CRD Pump Pressure Scram 2.C.(20)_
Degraded Grid Voltage Protection 2.C.(21)(a)
DG Turbocharger Installation
~2.C.(21)(c)
DG Control Modifications 2.C.(22)
DC Power System Monitoring 2.C.(25)(d)
Fire Door Tests 2.C.(30)(1)(b)
Install ADS Logic Modification 2.C.(30)(g)
Qualified SRV Position Indication J
BRS 3-18-83
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Awaiting NRC Action 2.C.(8)
Masonry Walls 2.C.(12)(b)
Fuel Lift Review 2.C.(14)(b)
Scram Discharge Procedures 2.C.(21)(b)
DG Prelube Pump 2.C.(30)(1)(a)&(b)
ADS Logic Modifications t
2.C.(30)(1)
Inadequate Core Cooling Report 4
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LaSalle Unit 2 Operating License Readiness Review e
LaSalle Unit 1 Operating License' Issued April 17, 1982 e
Original License Conditions (for Unit 1) 67 e
Conditions Fulfilled on Unit 2 Prior to OL 33 e Unit 1 or Common Items 17 e Unit 2 Completed Items 8
e Unit 2 Expect to Complete 8
e Conditions Remaining for Unit 2 34 e Routine Administrative 18 e In Progress, Longer Term 10 e Awaiting NRC Action 6
o Conclusion Licensing Readiness of Unit 2 is Apparent BRS 3-18-83
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50.55(e) Items Control Telecon Written Number Date Issues Report 81-01 1-27-81 Motor Terminal Block Voltage 2-20-81 81-02*
2-27-81 HFA Relay Cracking 3-25-81 81-06 8-18-81 SRV Solenoids 9-17-81 81-07 9-22-81 Excess Flow Check Valve 10-22-81 81-09 10-7-81 Incorrect ASCO valve 11-7-81 82-0l*
1-9-82 DG Air Start Motors 2-8-82 82-02*
1-27-82 GE HPCS Switchgear 2-26-82 82-03 2-9-82 Snubber Inclose Proximity to Restraints 3-11-82 82-07 8-1-82' Z4ck Welder Quals to RDW by CWS 8-31-82 82-08 8-17-82 Bunker, Ramo Installed Butt Splices 3-1-83 on Cable 82-10*
10-19-82 ECCS Pumps - Overtorqued Bolts 11-18-82 82-11*
12-23-82 Elcen Rigid Strut Pins 1-21-83 83-01 2-15-83 Riley Temp. Indicating Switches 3-16-83 83-02 2-16-83 Static-0-Ring Pressure Switches 3-16-83 I
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CASELOAD FORECAST PANEL SITE VISIT March 21-22, 1983 Procurement Activities Current Status (1) All initial required valves, pipe, instruments, cable, major car.ponents, etc. have been purchased and delivered.
(2) Continuing to procure new/ replacement parts for revised and/or damaged valves, pipe, instruments, cable and equipment.
Steps Being Taken~To Complete (1) Full-time on-site and off-site expeditors.
(2) Contact / purchase with other utilities which have cancelled plants.
Overall Assessment
!!ct mpact is expected on fuel load date.
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CASELOAD FORECAST PANEL SITE VISIT March 21-22,'1983 Craft Work Force Current Status (1) Craft availability is N0 problem. Construction is in a large layoff phase.
(Refer to contractor force report and graph).
(2) All craft contracts expire between May 1,1983 and September 1,1983.
fj0, problems are expected due to economic position craft unions find themselves. Surrounding area negotiations have resulted in wage freezes.
' Contingency Steps (1) Invoke national agreements.
(2) Sign retroactive agreements.
(3)Separategates.
i Overall Assessment-fj0, impact is expected on fuel load date.
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CASELOAD FORECAST PANEL SITE VISIT March'21-22, 1983' Contractor Force Report
~
Contractor 3/8/82 10/4/32 11/22/82 12/6/82 2/7/83 3/7/83 A&M 24 16 17 11 11 9
H.P.F.
354 254 306 279 223 211 MIDWAY 37 6
12 13 26 29 MCC0 663 599 599 533 387 320 RCI 59 40 43 33 30 10 TECH-SIL 6
5 6
6 6
7 TRANSCO 11 9
8 17 22 10 WALSH 333 251 240 235 207 205 ZACK.
56 34 21 22 6
6 J.L.M.(Others) 23 0
0 2
3 3
TOTAL CRAFT 1566 1214 1252 1156 921 810 l
OVERHEAD /Q.C.
252
~214 224
~218 209 179 l
TOTAL 1818 1428 1476 1374 1130 989 l
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CASELOAD FORECAST PANEL SITE VISIT
-March 21-22, 1983' Piping Support Status Current Status (1) Design work is~ complete. Sargent & Lundy (A/E) continues to support /
resolve field erection problems.
(Field Problem chart).
(2) All required material has been delivered. Stock material exists on-site for any last-minute changes.
(3) Installation work is 98% complete. (As of March 7,1983).
Monthly FWL Type ~ Support Required Installed
' Remaining Prod.
Date Complete large Bore 8800 8760 40 80 4/1/83 99 Small Bore 8240 7710 530 550 4/20/83 95 4
l Overa11' Assessment
(
All hanger work required for closing out sub-systems to support a N-5 completion and N-3 signoff will be done April 30, 1983, i
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i LA SALLE UNIT 2 FIELD PROBLEM BACKLOG 1000 900 800 700 Total Backlog 600 1
i' 500 i
400
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For 300 installation
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OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR l
1981 rlc 1982 rl:
1983 Ej Previous Backlog:
47 Current Backlog: 49 Problems Resolved: (116)
For installation:
4 Problems Received: 118
CASELOAD FORECAST PANEL SITE VISIT March 21-22, 1983 Belk Quantities i
Current Status (As of March 7, 1983 (1) Concrete - completed (One(1) construction opening will be closed 4/15/83).
(2) Structural Steel - Two(2) floor levels in Drywell must be completed.
Expected completion - May 1, 1983.
(3) Painting / Coating (a) Auxiliary Building - 85%
(b) Turbine Building
- 30%
(c) Reactor Building
- 30%
Thirty (30) painters working at steady rate. Work will be completed by fuel load.
(4) Process Pipe - completed.
(5) Yard Pipe - completed.
(6) Large Bore Piping Supports - Refer to Piping Support Status.
(7) Small Bore Piping Supports - Refer to Piping Support Status.
(8) Cable Tray - completed, 56,768 feet required / installed.
(9) El Conduit To_t,a1, Conduit Required 257,970 Ft.
Required 278,803 Ft.
Installed 255,830 Ft.
Installed 276,663 Ft, Remaining 2,140 Ft.
Remaining 2,140 Ft.
Installation Rate 1,600 Ft./Mo.
Installation Rate 1,600 Ft./Mo.
% Complete 99.2%
% Complete 99.2%
Expected Completion April, 1983 Expected Completion April, 1983 (10) EI Cable Required 17,638 Ea.
Installed 17,214 Ea.
Remaining 424 Ea.
Installation Rate 300 Ea./Mo.
% Complete 97.6%
Expected Completion April, 1983
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(11) EL Terminations Required 34,758 Cable Ends Installed 33,166 Cable Ends Remaining 1,592 Cable Ends Installation Race 800 Cable Ends /Mo.
% Complete 95.2%
Expected Completion May, 1983 NOTE: For conversion to conductors multiply by 5.30.
(12) Plant Lighting Required 3,673 Fixtures Installed 3,381 Fixtures Remaining 292 Fixtures 1
Installation Rate 150 Fixtures /Mo.
% Complete 92%
Expected Completion May, 1983 (13) Instrumentation (Mechanical)
Required 1,396 Ea.
Installed 1,395 Ea.
Remaining 31 Ea.
Installation Rate 20 Ea./Mo.
% Complete 98% Complete Expected Completion April, 1983 Overall Assessment Construction Completion - May, 1983
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f March 18, 1983 PRE-0P STATUS (a) TOTAL NUMBER OF PROCEDURES REQUIRED FOR FUEL LOAD.
71 (b)
NUMBER OF DRAFT PROCEDURES NOT STARTED.
NONE (c)
NUMBER OF DRAFT PROCEDURES BEING WRITTEN.
1 (d)
NUMBER OF PROCEDURES APPROVED.
70 (e)
NUMBER OF PROCEDURES IN REVIEW.
NONE (f)
TOTAL NUMBER OF PREOP AND ACCEPTANCE TESTS REQUIRED FOR FUEL 71 LOAD IDENTIFYING EACH.
(g)
NUMBER OF PREOP AND ACCEPTANCE TESTS COMPLETED IDENTIFYING EACH 12.
(h)
NUMBER OF PREOP AND ACCEPTANCE TESTS CURRENTLY IN PROGRESS 34 IDENTIFYING EACH AND STATUS.
(i)
NU:iBER OF SYSTEMS AND/0R SUBSYSTEMS TURNED OVER TO START-UP 59-lDENTIFYING EACH.
R. D. Bishop t
SYSTEMS NOT TURNED OVER
' SYSTEM PROJECTED TURNOVER 1.
PT-CM-201, CONTAINMENT MONITORING APRIL 1, 1983
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PR-LD-201, LEAK DETECTION
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PT-MS-201C, MSRV AND ADS MAY 15, 1983 5
PT-NR-2010, LOCAL POWER RANGE MONITORING APRIL 15, 1983 6.
PT-NR-202, TRAVERSlNG INCORE PROBES HAY 15, 1983 l7 PT-PC-201, INTEGRATED LEAK RATE TEST -
APRIL 1, 1983 8.
PT-PV-201, REACTOR VESSEL INTERNALS VIBRATION APRIL 1,1983
,9 SD-EH-201 A,~~- ELECTRO-HYDRAULI C CONTROL JUNE 1, 1983 10.
SD-EH-201B, TURBINE SUPERVISORY JUNE 1,1983 11.
SD-FW-201, FEEDWATER APRIL 1, 198'3' 12.
SD-FW-202,.
FEEDWATER CONTROL APRll 1, 1983
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'12CS-ISAE T.'.E L E 14.2-3 PRF.DPERATIONA.L TESTS TEST NUMBER TEST TITLE TABLE NUMBER PT-AP101 A-C Distribution 14.2-4 Systems PT-AP102 D-C Distribution 14.2-5 Systems PT-AP103 Emergency Power 14.2-6 Redundancy PT-CM101 Containment 14.2-7 Monitoring PT-CM102 Postaccident Primary 14.2-8 Containment Monitoring System PT-D0101 Diesel Oil Sys' tem 14.2-9
'PT-FC101 Fuel Pool Cooling 14.2-10 PT-HC101' ~ ~~
Reactor Building Crane 14.2.
PT-IN101 Drywell Pneumatic System 14.2-12 PT-PC101 Primary Containment 14.2-13 Integrated Structural / Leak Rate Test PT-PC102 Drywell Floor 14.2-14 PT-SI101 Seismic Instrumentation 14.2-15 PT-SI102 Vibration Monitoring -
14.2-16 l
PT-VC101 Control Room HVAC System 14.2-17 PT-VD 101 Diesel-Generator Room 14.2-18 Ventilation System t
l PT-VE101 Auxifiary Electrical 14.2-19 Equipment Room HVAC System.
PT-VG101 Standby Gas Treatment 14.2-20 I
System i
l PT-VJ101 Machine Shop HVAC System 14.2-21 t
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TAELE 14.2-3 (Cont' d) i PT-VL101 Laboratory HVAC System 14.2-22 PT-VO101 Off-Gas Building 14.2-23 i
HVAC System PT-VP101 Primary Containment 14.2-24 Vent and Purge System PT-VP102 Post-LOCA Hydrogen 14.2-25 Control System PT-VP103 Primary Containment -
14.2-26 HVAC System PT-VP104 Primary Containment 14.2-27 Chilled Water System PT-VR101 Reactor Building HVAC System 14.2-28 PT-VW101 Radwaste Area HVAC System, 14.2-29 PT-VX101 Switchgear Heat Removal System 14.2-30 f
PT-VY101 CSCS Equipmer.t 14.2-31 Cooling Water System PT-VY102 CSCS Equipment 14.2-32 Ventilation System PT-AR101 Area Radia' tion' 14.2-33 Monitoring Equipment PT-DG101 Diesel-Generators and 14.2-34 Auxiliaries PT-FR101 Fuel Handling and vessel 14.2-35 Servicing Equipment PT-EP101 High-Pressure Core Spray 14.2-36 Systhm PT-LD101 Leak Detection System 14.2-37 l
PT-LP101 Low-Pressure Core Spray Sys, tem 14.2-38
' PT-MS101 Main Steam ADS, MSIV, MSRV, 14.2-39 and MSIV-LCS l
i PT-NB101 Nuclear Boiler System 14.2-40 j
PT-NR101 Neutron Monitoring System 14.2-41 1'4.2-28
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PT-PC103 Primary containment Isolation 14.2-44 l
System PT-PV101 Ccnfirmatory Vibration Flow 14.2-45 Testa and Inspection and Reactor Vessel Flow Induced Vibration Test
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PT-PR101 Process Radiation 14.2-46 Mcnitoring System PT-RD101 Rod Drive Control System 14.2-47 PT-RD102 Centrol Rod Dr:-ve 14.2-48 Bydraulic Sys.pm PT-RH101 ResidualHeatRemovalSyst[em 14.2-49 i
PT-RIl 01 Reacter Core Isolation 14.2-50 s
Cooling System PT-RP101 Reacter Protection System 14.i-5,1 PT-RP102 Remote Shutdcwn System 14.2-52 PT-RR101 Reactor Recirculaticn 1'4.2-53 Flcw Control System
.FT-SC101 Standby Liquid Centrol 14.2-54
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SD-AC101 Aci'd and Caustic System 14.2-56 S D-AS 101 Auxiliary Steam System 14.2-57 SD-CD101 Condensate and Condensate
, 14.2-58 Booster System S D-CD10 2 Condenser and Auxil~iary Equipment System 14.2-59 SD-CG 101 Cycled Condensate Gland Water System 14.2-60 SD-CL101 Service Water Hypochlorite System 14.2-61 CondensatePolishingSyskem..
14.2-62 SD-CP101 SD-CQ101.__
Commmications System 14.2-63
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.ry Equipment System 14.1-64 L
-gi SD-CY101 Cycled condensate System 14.2-65 SD-ES 01 Extraction Steam System 14.2-66 SD-FC101 Fuel Pool Filter /
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SD-FP101 Fire Protection System
,SD-HD101 Heater Drain System 14.2-69
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14.2-71
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Service 'and Instrument Air l
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4 Station Heat Recovery System 14.2-73 SD-SE101 i
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14.2-135
1.JC S-I S.Us A3;E 14.2-55
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S D-VS 101 Service Building HVAC System 14.2-76 SD-VT101 Turbine Building HVAC System 14.2-77 5
S D-WE101 Liquid Radwaste System 14.2-78 S D-WL101 Lake Makeup and Blowdown System 14.2-79 5'
SD-WM101 Makeup Demineralizer System 14.2-80
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Water System 14.2-81 SD-WS101 Service Water System 14.2-82 SD-Wr101 Turbine Building Closed Cooling i
Water System 14.2-83 SD-WW101 Domestic and Well Water System
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Solid Radwaste System 14.2-85
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SD-CX101 Process Computer System 14.2-86 SD-CX102 Rod Worth Minimizer System 14.2-87 S D-EH101 Turbine Electrohydraulic Control Systedt 14.2-88 SD-EW101 Reactor Feedwater System.
14.2-89 S D-FW10 2 Feedwater Control System 14.2 SD-GC101 Stator cooling Water Gystem 14.2-91 SD-GS101 Turbine Steam Sealing System 14.2-92 S D-HY 101 Hydrogen Cooling System 14.2-93 SD-MP.101 Main Generator System 14.2-94 FD-MP102 Main Excitater System 14.2-95 SD-RT101 Reactor Water Cleanup System 14.2-96 SD-TG 101 Turbine Lift Pump System 14.2-97 SD-To101 Turbine Lube oil System 14.2-98 14.2-136
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