ML19206A267
| ML19206A267 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/20/1978 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| NYO-7S-003, NYO-7S-3, NUDOCS 7904180449 | |
| Download: ML19206A267 (17) | |
Text
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's FIRE PROTECTION PROGRA31 EVALUATION Three 3111e Island Nuclear Station Unit No. 2 LOSS OF CABLE ROOSI SUPPLE 3IENT Prepared for GPU SERVICE CORPORATION Prepared by EDS NUCLEAR INC.
31ay,1978 EDS Report No. NYO-7S-003, Revision 1 or-046 7 M tevv9 u_
I
FIRE PROTECT!ON PRCGRA3I EVALUATION Three 3111e Island Nuclear Statica Unit No. 2 LOSS OF CABLE RCOSI SI'PPLE31ENT Prepared for GPU SERVICE CCRPORATION Prepared by EDS NTJCLEAR INC.
31ay,1978 EDS Report No. NYO-7S-003, Revision 1 a2 -04'/
EDS NUCLEAR INC.
REPORT APPROVAL COVER SI1EET Client:
GPU Service Corporation Project:
Three Mile Island Nuclear Station, Unit 2.
Job Number:
3700013 Report
Title:
Loss of Cable Rcom Supplement NYO-78-003 O
Report Number:
g y, The work described in this Report was performed in accordance with the EDS Nuclear Quadly Assurance Program. The signatures below verify the accuracy of this Report and its complianc? with applicable quality assurance requirements.
Prepared By: b Date: f O!8 f/2o/7p Reviewed By: b,w T k'd '-
Date:
u u Y[4' b8 Approved By: U 9f % d Date:
REVISION RECORD Rev.
Prepared Reviewed Approved Approval Revision No.
Date 1
A &C G,7, IR W.7 R 5"[80 [7 ?
311nor Revision to Pages:
1, 6, 7, 11 f.-048
NYO-7 S-003 Revision 0 FIRE PROTECTION PROGRAM EVALUATION Three Mile Island Nuclear Station, Unit No. 2 LOSS OF CADLE ROOM SUPPLEMENT TABLE OF CONTENTS SecMon Page Report Approval Cover Sheet
- 1. 0 Introduction 1
- 2. O Method of Analysis 2
- 3. 0 Results of Andysis 3
4.0 Conclusion 12
- 5. 0 References 13 Safe Shutdown Logic Diagram TMI-2-SSLD-003A -
" Shutdown Outside Cable Room" b2"049
NYO-78-003 Revision 0
- 2. 0 METHOD OF ANALYSIS The following activities were performed during the Shutdown Outside the Cable Room evaluation.
a.
The components and instruments necessary to perform a Shutdown Outside the Cable Room were identified utilizing the existing Safe Shutdown Logic Diagram TMI-2-SSLD-003, " Shutdown outside Con-trol Room", Revision 1.
b.
The Elementary Diagrams and Block Diagrams for those components and instruments were collected and reviewed. (See Section 5.0 -
References. )
c.
The ccmponents and instruments which become unavailable as a re-sult of a Design Basis Fire in the Cable Room were determined. The following assumptions were used:
1.
Local control switches, pushbuttons or contacts routed in series with Control Room and/or Cable Rcom control switches, push-buttons or contacts are incapacitated.
2.
Local control switches, pushbuttons or contacts routed in parallel with Control Room and/or Cable Room control switches, push-buttons or contacts are available.
3.
Fire induced faultings in electric circuits causing components to fail in unexpected positions have not been considered.
4.
Credit has been taken for the manual operation of valves, if neces-sary,.!uring shutdown, d.
The result of this evaluation were documented on SSLD-TMI-2-SSLD-003A, " Shutdown Outside Cable Rocm". (Refer to Paragraph 4. 5 of,
" Technical Procedure for Performance of the Fire Protection Program Analysis", 3700013-2, Revision 0.
The path utilized for shutting down the plant following modifications has been indicated with a heavy line.)
e.
The results of the analysis are also summarized on Table No.1 of this repo rt.
f.
Modificat: ens re@ ired to maintain the capability to safely shutdown were.
identified. L' 050
NYO-78-003 Revision 0
- 3. 0 RESULTS OF ANALYSIS The results of the Loss of Cable Room analysis are documented on Table No.1 of this report and on SSLD T3II-2-SSLD-003A, " Shutdown Outside Cable Room". __ _
W U2-051
NYO-78-003 Revision 0 TABLE NO.1 SHUTDOWN OUTSIDE CABLE ROOM
SUMMARY
IAcal Control
& Indication SSLD System Component Available Note Sheet No.
CVCS MU-P-1 A No L
6, 7 MU-P-1 B No L
6, 7 M U-P-1 C No L
6, 7 MU-P-I A -
No L
6, 7 Main Bearing Lube Oil Pump MU-P-1 B -
No L
6, 7 Main Bearing Lube Oil Pump MU-P-I C -
No L
6, 7 Main Bearing Lube Oil Pump MU-P-1 A -
No L
6, 7 Auxiliary Bearing Lube Oil Pump 71U-P-1B -
No L
6, 7 Auxiliary Bearing Lube Oil Pump MU-P-1 C -
No L
6, 7 Auxiliary Bearing Lube Oil Pump MU-P-1 A -
No L
6, 7 Auxiliary Gear Lube Oil Pump MU-P-1 B -
No L
6, 7 Auxiliary Gear Labe Oil Pump MU-P-I C -
No L
6, 7 Auxiliary Gear Lube Oil Pump MU-V-16A Yes M
6 MU-V-1GB Yes M
6 MU-V-16 C Yes M
6 MU-V-16D Yes M
6 DH-V-5 A Yes P
6, 7 DH-V-5 B Yes P
6, 7 MU-V-376 Yes K
6 MU-V-377 Yes K
6 '
b2-052
NYO-78-C 03 Revision 0 Table No.1 (Continued) beal Control
& Indication SSLD
- Svstem Comoonent Available Note Sheet No.
DH DH-P-1 A No J
4, 8 DH-P-1 B No J
4, 8 DH-V-4A Yes P
4 DH-V-4B Yes P
4 DH-V-1 Ycs P
4, 8 DH -V-171 Yes P
4, 8 DH-V-1'0A Yes P
4, 8 DH-V-100 B Yes P
4, 8 DH-V-3 Yes P
4, 8 DH-V-2 Yes I
4, 8 pianual)
DH-V-12?A Yes I
4, 8 pla1ual)
DH-V-l'J 8 B Yes I
4, 8 pianual)
DH-V ' 02A Yes P
4, 8 DH-V -102B Yes P
4, 8 NS NS-P-I A No L, N 6, 7 NS-P- 1 B No L, N 6, 7 NS-P-1 C No L, N 6, 7 NR NR-P-1 A No J,L,N 4,6,7,8 NR-P-1 B No J,L,N 4,6,7,8 NR-P-1 C No J,L,N 4,6,7,8 NR-P-ID No J. L, N 4, G, 7, 8 CF C F-V-I A Yes H
4, 8 pianual)
C F-V-1 B Yes H
4, 8 pianual)
-5 brJ-053
NYO-78-003 Revision 1 Table No.1 (Continued)
Ircal Control
& Indication SSLD System Comconent Available Note Sheet No.
DC DC-P-1 A No J
4, 8 DC-P-1 B No J
4, 8 EF E F-P-2A No E
3 E F-P-2 D No E
3 E F-V-4A Yes P
3 E F-V-4 B Yes P
3 EF-V-5A Yes P
3 E F-V-5 B Yes P
3 L v-V-33A Yes P
3 E F-V-33B Yes P
3 E F-V-32A Yes P
3 E F-V-32B Yes P
3 E F-V-12A Yes P
3 EF-V-12B Yes P
3 CO-V-87 Yes P
3 31S-V-11 A (EF-P-1)
Yec S
3 3IS-V-11B (E F-P-1)
Yes S
3 1
31S-V-14 (E F-P-1)
Yes S
3 LIS-V-207 (E F-P-1)
Yes S
3 AC (10)
AH-C-50A Yes P
3 AH-C-50 B Yes R
3 l1 SF S F-P-I A No N
6 SF-P-1 B No N
6 DH-V-157 Yes P
6 WDL WDL-V-96A Yes P
6 WDL-V-96 B Yes P
G _
- -054
NYO-78-003 Revision 1 Table No.1 (Continued)
Iocal Control
& Indication SSLD System Comoonent Available Note Sheet No.
CAC (1)
AH-E-11 A No O
6 AH-E-11B No O
6 AH-E-11 C No O
6 AH-E-11D No O
6 AH-E-11E No O
6 RB RB-P-1A Yes P
6 RB-P-1 B Yes P
6 RB-Z-1 A Yes P
G 1
R B-2-1 B Yes T
6 SFAS Channels No G
4, 8 CRDCS CRAs Yes A
1 TCS Turbine Stcp Valves Yes B
1 RCS RC-P-1 A Yes C
1 R C-P-1 B Yes C
1 R C-P-2A Yes C
1 R C-P-2 B Yes C
1 FW FW-P-1 A Yes D
2 FW-P-1 B Yes D
2 Communi-Emergency Page Party System No Q
6 cations Page Party System Maintenance Communication Jack Systems
_7-6 3Z-055
NYO-78-003 Revis:en 0 Table No.1 (Continued) local Parameter Indication SSLD Measured Instrument Available Ncte Sheet No.
T RC-5 A-TE2 Nb F
4, 5, 8 RC-5A-TE4 No F
4,5,8 RC-5B-TE2 No F
4, 5, 8 RC-5B-TE4 No F
4, 5, 8 i
RC-3A-PT4 No F
4,5,8 RC-3B-PT3 No F
4,5,S L
RC-1-LT1 No F
4,5,6 P
T RC-2-TE1 No F
4 RC-2-TE2 No F
4 L,b SP-1 A-LT1 No F
3 SP-1 A-LT4 No F
3 SP-1 A-LTS No F
3 SP-I B-LT' No F
3 SP-1 E-LT4 No F
3 SP-1B-LTS No F
3 P
No F
2, 4 sg
_g_
32'056
NYO ~8-003 Revision 0 Table No.1 (Continued)
NOTES A
If the manual trip button located in the Control Room is unavailable and the reactor is not tripped as a result of the loss of control circuits for the RPS, the operscor may locally open control rod drive breakers.
B If the turbine does not trip due to a reactor trip, it may be manually tripped by interrupting the auto-stop oil pressure that maintains all turbine stop valves in the open position.
C If the manual reactor coolant pump trip switches in the Control' Room are unavailable and the pumps are not tripped as a result of the loss of control circuits, the operator may locally trip the reactor coolant pumps.
D If the manual feedwater pump trip switches in the Control Room are un-available and the pumps are not tripped as a result of the loss of control circuits, the operator may locally trip the feedwater pumps.
E The control circuits for motor driven Emergency Feedwatec Pumps EF-P-2A and EF-P-2B are unavailable and must be restored to achieve a safe shutdown.
F The following indication is unavailable and must be restored to achieve a safe shutdown:
1.
Steam Generator Level 2.
Steam Generator Pressure 3.
Reactor Coolant System Temperature 4.
Pressurizer Pressure 5.
Pressurizer Level 6.
Pressurizer Temperature G
With a fire in the Cable Room, the operator would not be able to bypass the High and Iow Pressure Injection Channels of Safety Injection Actuation A and B.
However, if the Safety Injection Actuation signal occurs and the HPSI and LPSI pumps and valves are not incapacitated by the fire and are actuated, the operator would be capable of securing them.
_9
~
b2-057
NYO-78-003 Revision 0 Table No.1 (Continued)
NOTED Although remote control capability of the Core Flooding Valves CF-V-1A a
r_nd CF-V-1B is incapacitated due to a fire in the Cable Room, local man-ual control is unaffected.
I Although remote control capability of the Decay Heat Removal Valves DH-V-2, DH-V-12SA and DH-V-12SD is incapacitated due to a fire in the Cable Room, local manual control is unaffected.
J The control circuits for Decay Heat Removal Pumps DH-P-1A and DH-P-1B, Decay Heat Closed Cooling Water Pumps DC-P-1A and DC-P-1B, and Nuclear Services River Water Pumps NR-P-1A, NR-P-1B, NR-P-1C and NR-P-1D are unavailable and must be restored to achieve a safe shutdown.
K If the letdown valves cannot be closed prior to evacuating the Control Room, the valves may be closed locally.
L The Charging Pumps 31U-P-1A, 31U-P-1B and 3IU-P-IC become unavailable due to the loss of their associated main and auxiliary bearing lube oil pumps, auxiliary gear lube oil pumps, Nucicar Service,s Closed Cooling Water Pumps NS-P-1A, NS-P-IB and NS-P-1C and Nuclear Services River Water Pumps NR-P-1 A, NR-P. 8, NR-P-1C and NR-P-1D. The control circuits for these pumps are unavailatae and must be restored to achieve a safe shutdown.
31 Although local control of 3Inkeup Valves 3IU-V-16A, AIU-V-16B, 31U-V-16C and 31U-V-16D is available, these valves will not normally be used to achieve a safe shutdown. However, they are available as a backup if required.
N The control circuits for Spent Fuel Cooling Pumps SF-P-1A and SF-P-1B, Nuclear Services Closed Cooling Water Pumps NS-P-1A, NS-P-1B and NS-P-1C, and Nuclear Services River Water Pumps NR-P-I A, NR-P-1B, NR-P-1C and NR-P-1D are unavailable and must be restored to achieve Spent Fuel Heat Removal.
O The control circuits for Reactor Building Air Cooling Fans AH-E-11A, AH-E-11B, AH-E-11C, AH-E-11D and AH-E-11E are unavailable and must be restored to achieve Containment Pressure and Temperature Control. '
a 5%
NYO-78-003 Revision 1 Table No.1 (Continued)
NOTES P
Iocal control of the following components is available and may be utilized in performing a safe shutdown:
DH-V-1 E F-V-4 A CO-V-87 DH-V-3 E F-V-4B DH-V-4A E F-V-5 A AH-C-50A DH-V-4B E F-V-5 B AH-C-50B (see Note R) l1 DH-V-5 A E F-V-12A DH-V-5B E F-V-12B WDL-V-96A DH-V-100A E F-V-32A WDL-V-96 B DH-V-100 B E F-V-32 B DH-V-102A E F-V-33A RB-P-1 A DH-V-102B E F-V-33B RB-P-1 B DH-V-157 RB-Z-1 A DH-V-171 RB-Z-1B (see Note T) 1 Q
Modifications to de comnumication systems shall be made to assure avail-ability in those areas where communications are required for an orderly safe shutdown.
R The B train of the Control Building Area HVAC becomes unavailable due to l
loss of power supply to Fan AH-C-50B and must be restored to achieve a safe shutdown.
S Although the Turbine Driven Emergency Feedwater Pump EF-P-1 will not be used to ' perform the safe shutdown, local control of valves MS-VIIA, 1
MS-V11B, MS-V14 and MS-V207 is available allowing the use of EF-P-1 as a backup as long as steam is available.
T Although the B train of the Reactor Building Normal Cooling Water System becomes unavailable due to loss of power supply to evaporative cooler fans, spray water circulating pumps and RB evaporator blowdown pump, the A train is still available for maintaining the capability to achieve Containment Pres-sure and Temperature Control.
. 52 059 32'05Q
NYO-78-003 Revision 0
4.0 CONCLUSION
The Ioss of Cable Room analysis was performed as described in Paragraph 2.0.
During the evaluation it was determined that plant modifications are required to maintain the capability to safely shutdown assuming the Cable and Control Rooms are unavailable. The design of the plant modifications interded, along with a schedule for implementation, will be provided by GPU.. _ _
32'060
NYO-78-003 Revisk..: 0
- 5. 0 REFER ENCES a.
EDS Report No. NYO-77-002, Revision 1.
b.
EDS Report No. NYO-77-004, Revision 1.
c.
Burns and Roe Elementary Diagrams Burns and Roe Drawinz No./ Sheet No./ Revision No.
3011(1)/
3075(50)/12 3077(SA)/8 3011(2)/
3075(52)/11 3077(33)/3 3075(62)/14 3075(63)/13 3073(10A)/4 3075(65)/12 3078(9)/6 3073(48)/16 3075(69)/12 3078(22)/7 3073(49)/18 3075(87)/14 3073(50)/15 3075(88)/15 3073(55)/15 3075(89)/14 3079(2)/12 3073(68)/16 3075(90)/14 3079(38)/3 3073(69)/17 3075(92)/14 3073(76)/17 3075(139)/13 3075(140)/10 3091/5 3075(142)/10 3074(31)/10 3075(148)/12 3074(32)/10 3075(153)/11 3074(33)/12 3075(163)/7 3074(34)/11 3075(179)/12 3074(41)/14 3075(192)/7 3074(45)/15 3075(193)/14 3074(45A)/5 3075(194)/11 3074(45B)/5 3075(195)/10 3074(4GA)/15 3075(106)/12 3074(46B)'/19 3075(197)/12 3074(46C)/5 3075(199)/8 3075(200)/6 3075(208)/8 3075(20SA)/3 3075(221)/4 3075(238)/4 3075(239)/4 b2-061
NYO-73-003 Revision 0 c'.
Btras and Roe Block Diagrams Burrs and Roe Drawing No. / Sheet No. / Revision No.
3021(43)/10 3023(1)/6 302e(7)/3 3025(1)/9 3021(45)/9 3023(1F)/S 3024(9B)/4 3025(2SB)/3 3021(46)/9 3023(1H)/5 3024(13)/5 3025(2SC)/4 3021(48)/7 3023(IJ)/5 3024(14)/5 3021(59)/7 3023(IN)/6 3024(15)/7 3021(60)/7 3023(1Q)/7 3024(38G)/5 3023(1S)/4 3024(41)/4 3023(1T)/4 3024(42)/4 3022(IB)/4 3023(1U)/S 3024(42C)/4 3022(1C)/4 3023(1W)/6 3024(42D)/3 3022(1E)/S 3023(1X)/5 3024(43)/3 3022(2A)/5 3023(12)/6 3024(43C)/?
3022(2C)/4 3023(1AB)/5 3024(43D)/3 3022(3B)/5 3023(IAC)/3 3024(50)/3 3022(4A)/S 3023(1AH)/4 3024(52)/4 3022(15B)/5 3023(2)/6 3024(52A)/4 3022(15C)/5 3023(2D)/4 3024(89)/4 3022(15D)/5 3023(2G)/5 3024(89A)/4 3022(15E)/6 3023(2H)/5 3024(89B)/5 3023(2J)/5 3024(89C)/4 3023(2N)/5 3024(89D)/6 3023(2T)/S 3024(90A)/4 3023(2X)/4 3024(90B)/3 3023(2Y)/5 3024(90C)/3 3023(2AB)/4 3024(90D)/4 3023(2AC)/3 3023(2AD)/3 3023(3)/5 3023(3A)/8 3023(3B)/5 3023(3C)/8 3023(3D)/7 3023(4)/7 3023(4A)/6 3023(4B)/7 3023(4C)/7 3023(13X)/
3023(14S)/3 3023(14U)/3 3023(15C)/4 3023(16J)/4 b'2^O62-
NYO-73-003 Revision 0 e.
Babcock & Wilcox Schematics 7-09-0311 7-09-1201 7-09-1209 7-09-0312 7-09-1202 7-09-1210 7-09-0313 7-09-1203 7-09-1211 7-09-0317 7-0? 2204 7-09-1212 7-05-1205 7-09-1213 7-09-0817 7-09-1206 7-09-1214 7-09-0818 7-09-1207 7-09-1215 7-09-1208 7-09-1216 7-09-0954 e
e
-1s-7 32'063