|
---|
Category:Drawing
MONTHYEARNMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML22292A1382022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 18, 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 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 ML22292A1082022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 3, Figures 3.2-1 Thru 3C.3-3 ML22292A0772022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 8, Figures ML22292A1182022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 15, 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 ML22292A1102022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 1, Figures 1.2-33 Through End ML22292A1302022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 17, Figures ML22292A1372022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 12, Figures ML22292A1172022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 2, Figures ML22292A1012022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 2, Figures 2H.43 Through 2K-27F ML22292A1092022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 2, Figures 2K.28A Through End ML22292A0632022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 7, Figures ML22292A0922022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 11, 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 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 ML17037C5622017-02-0606 February 2017 Plate 4-9 - Geologic Plan View of Fault Cooling Tower Piping Trench ML17037C6602017-02-0606 February 2017 Figure 5.4-3; Steam Concentration Following a LOCA with CAD Operation 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. ML17037C7252017-02-0606 February 2017 Drawing; Figure 7.15-1, Rod Worth Minimizer Functional Control Diagram ML17037A7102017-02-0606 February 2017 Figure 12.7-1a Radiation Zones - Reactor Building. 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 ML17037A8162017-02-0606 February 2017 Drawing No. 12177-ESK-4CEC25A 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 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 ML17037A7122017-02-0606 February 2017 Figure 12.7-2a, Radiation Zones-Turbine Building, Radwaste Building, and Screenwell. 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. 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 2024-09-20
[Table view] |
Text
0 CSLEL REF Ol ED.A (T 05 NE) 5EE 4 (REC lol-ES-REF W
4'c.
RE.ACTOR VESSEL
>>0 I VESSE ND22
'51 E AND o 0 5 E RBF 5 ~
TABLE E RE 0 Et 02 041 10)-Ee-4 0 1 ol ce 4 (RE>>
RM6 N Vf OSSA <TVP 5 )
(Rf F 10) - 2 6-4 SEE OIE I I T PIC*L Fo 5 Es RE F 10) - E 8 5 OISGE
<1 El N2 J.t 00 '4 54 2 J-5 IS 45 N A 7)L DES 5
3 'I 54 PE Nf '/4' 941 DA
~e-2 EA I g/.
I 5 5MP NG P E NO tSX REF 5EE f8 REF
~E-I X 4 113 Ctl TE 4
e, Vf L5 51 I
-~---- e---
2'I WE 14 C.,
MOTOR 5
~F- t TE
,0,
5EE OT8 7
",, -L ~ --- e;---'-:::el-"':.-
4 OTE
~6 E
A ME
/C ZCTSO E 541
~J-TE.L Et 0 To RI C A .0
/" C 05 0
D NG e STE IG
~
E 8 wacea w4" T E. M 3>>, 0 Ps 8
Ls
-2 A, TE I 0 e--- -': ej-SEE SEE REC 4 G,C,7 I OTE I s /4 OTOR <OOU G COIL5 "...-I- ~ -
DRA 0 DR)'WEU.
C
". ~----e.--,
F5 EOUIP ~51. OO N'I 8
>>0 5 Tf SU P WM IZ
- -';-o....
CNT A STAG 46 I.ING
~
'e-Izt DA r--- SEE 0 r 5 SE C SED J EE RE
~77 Rot ~ 5 't, J.I MO
\023 R IS, ea633 4 PUMP COO 00 8 5H't. J-4 52E REP 9 (flEC 0) ES I MV/I
@46M[
~TE Mf A
SEE 4 TE4 MI""4 RM5 Qvr 0
110
~>>074 6~
I,I ~
~45 SEE aE 9 AEF 3 o.z TP 4 5 IHt'5 REC RC RFF C) 4 404 PER 155 VE L OP'8 5 I REF )3 FS 0 4 E
F0121 l5. FIG. 4.2-2A A7 Fo
P 01 3-- Rs I
REACTOR RECIRCULATION SYSTEM TEMP 44'te o
>>05'ta X / 4 A PIPING AND INSTRUMENTATION DIAGRAM 0 -Ee-4 ~ Y caw 811 NO C2 NINE MILE POINT NUCLEAR STATION UNIT 2 e- 97 A W REC Rc LOOP'1 'AME At OOP "A NIAGARA MOHAWK POWER CORPORATION EC RC LOOP NLE EM 0 L 550 R 'st 5 ECFED,SEE io E 2 laasw R CA< 00 6 PRELIMINARY SAFETY ANALYSIS REPORT Rf. 541, F 2 FRN aT o TA ENT~