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Category:Drawing
MONTHYEARML22292A1182022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 15, Figures
ML22292A0812022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 Through 4.6-9
ML22292A1022022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 6, Appendix 6D, Figures 6.2.1 Through 6C-1
ML22292A1082022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 3, Figures 3.2-1 Thru 3C.3-3
ML22292A1362022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 13, Figure 13.5-1, at the Controls Main Control Room El. 306'-0
ML22292A0772022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 8, Figures
ML22292A0662022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 9, Figures
ML22292A1272022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 14, Figures
ML22292A0932022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 10, Figures
ML22292A0892022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 5, Figures
ML22292A1372022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 12, Figures
ML22292A1102022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 1, Figures 1.2-33 Through End
ML22292A1172022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Figures
ML22292A1302022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 17, Figures
ML22292A1382022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 18, Figures
ML22292A1092022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Figures 2K.28A Through End
ML22292A1012022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Figures 2H.43 Through 2K-27F
ML22292A0632022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 7, Figures
ML22292A0992022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 9, Figures 9.4-2e Thru End
ML22292A0652022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 1, Figures
ML22292A0922022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 11, Figures
ML18018B3202018-01-18018 January 2018
Undersized Documents - Transformer 2MTX-XM1B - Oil Cooler Piping, Failed Windings, Tank Bulging, Preparation for Removal, HV Tap Changer, and Lv Leads and Bracing
ML18018B1942018-01-18018 January 2018
Undersized Documents, Drawings and Photographs
ML17037C7252017-02-0606 February 2017
Drawing; Figure 7.15-1, Rod Worth Minimizer Functional Control Diagram
ML17037C5622017-02-0606 February 2017
Plate 4-9 - Geologic Plan View of Fault Cooling Tower Piping Trench
ML17037B4552017-02-0606 February 2017
Drawing 12177-EE-1AR-3, 600V One Line Diagram 2EHS*MCC102 Auxiliary Building North - Nine Mile Point Nuclear Station - Unit 2.
ML17037A7102017-02-0606 February 2017
Figure 12.7-1a Radiation Zones - Reactor Building.
ML17037C6602017-02-0606 February 2017
Figure 5.4-3; Steam Concentration Following a LOCA with CAD Operation
ML17037C6592017-02-0606 February 2017
Figure 5.4-2; Hydrogen and Oxygen Concentration in Primary Containment Following a LOCA
ML17037C6582017-02-0606 February 2017
Figure 5.3-2; Stand-by Gas Treatment System
ML17037C5692017-02-0606 February 2017
Plate 5-10A - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-4-8 Through T-4-10
ML17037C5672017-02-0606 February 2017
Plate 5-10 - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-4-1 Through T-4-7
ML17037C5662017-02-0606 February 2017
Plate 5-9A - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-3-9 and T-3-10
ML17037C5652017-02-0606 February 2017
Plate 5-9 - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-3-1 Through T-3-8
ML17037C5642017-02-0606 February 2017
Plate 5-1 - Composite Site Stratigraphic Column
ML17037C5632017-02-0606 February 2017
Plate 4-10 - Cross Section CT-2 West Wall Cooling Tower Piping Trench
ML17037A7122017-02-0606 February 2017
Figure 12.7-2a, Radiation Zones-Turbine Building, Radwaste Building, and Screenwell.
ML17037A8182017-02-0606 February 2017
Drawing No. 12177-ESK-4CEC24
ML17037A6892017-02-0606 February 2017
Figure 12.1-1, General Arrangement Reactor Building - Plans
ML17037A6902017-02-0606 February 2017
Figure 7.9 - 1A, Feedwater Control System.
ML17037A6922017-02-0606 February 2017
Figure 7.6-7, Rod Block Interlocks from Neutron Monitoring System
ML17037A8292017-02-0606 February 2017
Drawing No. 12177-ESK-4CEC14A
ML17037A8382017-02-0606 February 2017
Drawing - (Drawing No. Not Available)
ML17037A7142017-02-0606 February 2017
Drawing No. 12241-GSK-31, Over Excavated Area - Reactor Containment - Locations.
ML17037A4622017-02-0606 February 2017
Drawing 807E154TY, Revision 3, Leak Detection System Elementary Diagram. Sheet 4
ML17037A8272017-02-0606 February 2017
Drawing No. 12177-ESK-4CEC15
ML17037B4562017-02-0606 February 2017
Drawing 12177-EE-1AQ-3, 600V One Line Diagram 2EHS*MCC101 & 2EHS*MCC301 Screenwell Building - Nine Mile Point Nuclear Station - Unit 2.
ML17037A8162017-02-0606 February 2017
Drawing No. 12177-ESK-4CEC25A
ML17037A6942017-02-0606 February 2017
Figure 7.4-10, Power Range Neutron Monitoring System Instrument Electrical Diagram
ML17037A7052017-02-0606 February 2017
Figure 2.7-16, Screenwell Building Plan and Sections
2022-10-05
[Table view] |
Text
S gau PIUS N(, WATCR 5 PPL PRIMARY C ON TA I 4 MENT Fpsi, HO O FQM OUTSIDE. 3 HOTESJ HC OOCUMENTSJ ~HPL ITEH NO F019 INSTRUHENT LINE DESIGN 4 YALVING NUCLEAR BDILER SYS FCD MUST COMPLY WITH INSTRUMEHT PIPING 821/522 fpip FRO CORE 0 PRt55 REACTOR SPECIFICATION REFEREN<E 18. 2.
~ BOYE (GRE Atc 1 5ECDHDARY 2 T CDNTAINll(NT 2. THE HE7HOD OF HOUHTING Lo<AL 3. RESIDUAL HEAT REMOVAL pil Nsi 4 7 INSTRUMENTS IS Tp BE DETERI1INED BV L C E12-1030 15 OTHER5.
4 ~ HIGH PRESSURE CORE
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- 6. EQUIPMENT 8. FUEL POOL <DOLING 8 (5 ( 5 INSTRUMENTS ARE PRE-EA. 5* 8 Ftxto ev svsf<M No. (Efa) ua<Ess CLEANUP 5YS palD Gvf Gvv f pip I 5<<
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- 13. R<t< SYS SHORTEST PRA<TICAL LENGTH.
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- 19. REAC RECIR< Svs PalD 833-1010 QR05 9 RECOMMENDED BUT NOT REQUIRED.
Po IS. NUCLEAR BDILER lp. VALVE SHOULD BE INSTAL'D WITH svs talo 82t/822-101D p- 5'f. Jf. 05 8
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- 2. BETNEEN VALVES Ho FOOB 4 Ho F009 CONSIDERATION SHOULD BE GIVEN TO 18 PIPING PRESSURE PROCESS 5
a EQUIPHENT PARTS IHSTRUMENTATIOH TUBING INSTALLATION SPECIFICATIONS A62-9010 A62 9030
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B,J, sv C CDI Tp 5CRv CE f.R 1>>5 4 RGE SKCC D FIG 7. 3- IOa RESIDUAL HEAT REMOVAL SYSTEM PIPING AND INSTRUMENTATION DIAGRAM NINE MILE POINT NUCLEAR STATION UNIT 2 RK F030 0 KUPPftE55104 5EK Np E 'I Y
1 NIAGARA MOHAWK POWER CORPORATION REF'I J.G POOL 5EE REF 7 PROCESS OECGIC EQU I'HE T 5N 2 H13 AA C 5 H LE 0 PRELIMINARY SAFETY ANALYSIS REPORT Cpd 5 TEN VEF 4 fp ZB R18t SER ICE D
8 0 Wf TER SYSTEM OSV
