ML20136B957
| ML20136B957 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/08/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136B960 | List: |
| References | |
| TAC-59439, NUDOCS 8511200332 | |
| Download: ML20136B957 (17) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION s
wasmuovow, o. c.zeses MISSISSIPPI POWER & LIGHT COMPANY
?
MIDDLE SOUTH ENERGY, INC.
l SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION D0CKET N0. 50-416 l
GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 7 License No. NPF-29 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Grand Gulf Nuclear Station, Unit i
I (the facility) Facility Operating License No. NPF-29 filed by the Mississippi Power and Light Company acting for itself, Middle South Energy Inc., and South Mississippi Electric Power Association (the licensees), dated August 12, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, as t
amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonablei assurance; (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted i
in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and i
paragraph 2.C(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through l
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- l.
- Amendment No. 7 and the Environmental Protection Plan contained in Appendix B are hereby incorporated into this license. Mississippi Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION 41 Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance:
November 8, 1985
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ATTACHMENT TO LICENSE AMENDMENT NO. 7 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed 'pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding over-leaf pages are also provided to maintain document completeness.
Amended Overleaf
,P_ age, Page a
3/4 3-71 3/4 3-72 3/4 4-11 3/4 4-12 3/4 6-30 3/4 6-29 3/4 6-31 3/4 6-38 3/4 6-37 3/4 8-32 3/4 8-31 3/4 8-32a (new page) 3/4 8-47 3/4 8-48
INSTRUMENTATION TABLE 3.3.7.4-1 (Continued)
REMOTE SHUTDOWN SYSTEM CONTROLS MINIMUM CHANNELS OPERABLE I
CONTROL Div 1 Div 2 b
b 12.
RHR Injection Valves 2
2 i
13.
RHR Test Line Valve 1
1 14.
1
1 i
16.
RHR Discharge.to Radwaste Valve 1
1 b
b 17.
2 18.
Diesel Generator HX Inlet Valve 1
1 b
b 19.
Safety / Relief Valves 6
6 20.
RHR to RCIC Head Spray Line Valve 1
NA 21.
RCIC Turbine Flow Controller 1
NA 22.
RCIC Suction Flow Suppression Pool Valve 1
NA 23.
RCIC Injection Shutoff Valve 1
NA 24.
NA 25.
RCIC Recirc. Main Flow Bypass Valve 1
NA 26.
RCIC Test RTN to CST IB Valve 1
NA l
27.
RCIC Test RTN to CST 08 Valve 1
NA..
l 28.
Steam to RCIC Turbine Valve 1
NA 29.
RCIC Turbine Trip & Throttle Valve 1
NA 30.
RCIC Turbine Cooling Water Valve 1
NA 31.
RCIC Turbine Local Control Select Switch 1
NA 32.
RCIC Gland Seal Compressor 1
NA 33.
Shutdown Cooling Isolation Valve Roset Switch 1 1
NOTE:
a.
1 per cooling tower fan b.
1 per valve GRAND GULF-UNIT 1 3/4 3-71 Amendment No.
7_...
l
INSTRUMENTATION TABLE 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENIS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Reactor Vessel Pressure M
R 2.
R 3.
Suppression Pool Water Level M
R 4.
Suppression Pool Water Temperature M
R 5.
RHR System Flow M
R 6.
Standby Service Water System Flow M
R 7.
RCIC Turbine Speed M
R 8.
Condensate Storage Tank Level M
R I
I GRAND GULF-UNIT 1 3/4 3-72
TABLE 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER SYSTEM E21-F005 LPCS E21-F006 E22-F004 HPCS E22-F005 E12-F008 RHR E12-F009 E12-F023 E12-F041 A, 8, C E12-F042 A, 8, C E12-F050 A, 8 E12-F053 A, B E12-F308 E12-F394 l
E51-F063 RCIC E51-F064 E51-F065 E51-F076 l
E51-F013 TABLE 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES PRESSURE MONITORS - ALARM ALARM SETPOINT VALVE NUMBER SYSTEM (psig)
E21-F005 to E21-F006 LPCS 150 E12-F008 to E12-F006A RHR 1183 E12-F008 to E12-F006B RHR 5183 E12-F041A to E12-F042A RHR 150 E12-F0418 to E12-F0428 RHR 150 E12-F041C to E12-F042C RHR 150 GRAND GULF-UNIT 1 3/4 4-11 Amendment No. 7 l
i TA8LE 3.4.3.2-3 REACTOR COOLANT SYSTEM INTERFACE VALVES PRES 5URE INTERLOCK 5 INTERLOCK SETPOINT VALVE NUMBER SYSTEM (psio)
E12-F052 to E51-F064 RCIC 5 465 E12-F041A'to E12-F042A RHR
$ 50 E12-F0418 to E12-F0428 RHR 1 50 E12-F041C'to E12-F042C RHR 1 50 E21-F005 to E21-F006 LPCS 1 50
(
GRAND GULF-UNIT 1 3/4 4-12
(
L
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i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS r
4.6.4.1 Each isolation valve shown in Table 3.6.4-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.
4.6.4.2 Each automatic isolation valve shown in Table 3.6.4-1 shall be demonstrated OPERABLE during COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on an isolation test signal each automatic isolation valve actuates to its isolation position.
4.6.4.3 The isolation time of each power operated or automatic valve shown in Table 3.6.4-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.4.4 (DELETED]
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l GRAND Gulf-UNIT 1 3/4 6-29 l
l 1
-s TABLE 3.6.4-1 CONTAINMENT AND DRYWELLT55LATION VALVES MAXIMUM i
4
-SYSTEM AND 3
PENETRATION ISOLATION TIME VALVE NUMBER NUMBER VALVE GROUP (a)
(Seconds) 1.
Automatic Isolation Valves #
a.
Containment Main Steam Lines B$1-F028A 5(0)*
1 5
Main Steam Lines 821-F022A' 5(I)*
1 5
Main Steam Lines 921-F067A-A 5(0)*
1 9
Main Steam Lines B21-F0288 6(0)*
1 5
Main Steam Lines B21-F0228-6(I)*
1 5
Main Steam Lines B21-F0678-A 6(.0)*
1 9
Main Steam Lines 821-F028C 7(0)*
1 5
Main Steam Lines B21-F022C 7(I)*
1 5
Main Steam Lines' B21-F067C-A 7(0)*
1 9
Main Steam Lines B21-F028D 8(0)*
1 5
s Main Steam Lines B21-F022D 8(I)*
1 5
Main Steam Lines B21-F067D-A 8(0)*
1 9
RHR Reactor E12-F008-A 14(0) 3 40 Shutdown Cooling Suction 4
RHR Reactor E12-F009-B 14(I).
3 40 Shutdown Cooling -
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Suction Steam Supply to E51-F063-B 17(I) 4 20 RHR and RCIC Turbi_ne Steam Supply to E51-F064-A 17(0) 4 20 RHR and RCIC Turbine Steam Supply to E51-F076-B 17(I) 4 20 RHR and RCIC Turbine RHR to liead Spray E12-F023-A 18(0) 3 94g RHR to Head Spray E12-F394-B 18(I) 3 35 l _ __
(a) See Specification 3.3.2, Table 3.3.2-1, for isolation signal (s) that operates each valve group.
s (b). Deleted (c)
Hydrostatically tested with water to 1.10 P Hydrostatically tested by pressurizing syst$m, 12.65 psig.
(d) to 1.10 P Hydrostatically tested during system functional tests.,, 12.65 psig.
(e)
(f) Deleted (g) Normally closed or locked closed manual valves may be opened on an 1:
intermittent basis under administrative control.
- The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDIT0NS 2 or 3 provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reaching a reactor, steam
- pressure of 600 psig and prior to entry into OPERATIONAL CONDITION L
- The "-A, -B, -C, -(A), -(B), -(C)" des!gnators on the valve numbers indicate associated electrical divisions.
- Initial closure time.
Final closure time to be determined during ASME Sec-tion XI testing.
Any required change to this closure time shall be submitted to the Commission within 90 days of the second closure time test completion.
GRAND GULF-UNIT 1 3/4 6-30 Amendment No. 7 l
TABLE 3.6.4-1 (Continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES MAXIMUM l
SYSTEM AND PENETRATION ISOLATION TIME VALVE NUMBER NUMBER VALVE GROUP (a)
(Seconds)
)
Containment (Continued)
Main Steam Line B21-F019-A 19(0) 1 20 Drains Main Steam Line B21-F016-B 19(I) 20 Drains RHR Heat Exchanger E12-F028A-A 20(I) 5 90 "A" to CTMT_ 2 SPR Sparger INL -
RHR Heat Exchanger
- E12-F037A-A 20(I) 3 74 "A" to CTMT Pool l
RHR Heat Exchanger E12-F0288-B 21(I) 5 90 "B" to CTMT SPR Sparger INL RHR Heat Exchanger E12.-F0378-B 21(I) 3 74 "B" to CTMT Pool -
l RHR "A" Test Line E12-F024A-A 23(0)(d) 5 90 to Supp. Pool RHR "A" Test Line E12-F011A-A 23(0)(d) 5 36 to Supp. Pool RHR "C" Test Line E12-F021-B 24(0)(d) 5 144 to Supp. Pool HPCS Test Line E22-F023-C 27(0)(d) 6B 75 RCIC Pump Suction E51-F031-A 28(0)(d) 4 56 RCIC Turbine E51-F077-A 29(0)(c) 9 26 Exhaust LPCS Test Line E21-F012-A 32(0)(d) 5 144 Cont. Purge and M41-F011-(A) 34(0) 7 4
Vent Air Supply Cont. Purge and M41-F012-(B) 34(I) 7 4
Vent Air Supply Cont. Purge and M41-F034-(B) 35(I) 7 4
Vent Air Exh.
Cont. Purge and M41-F035-(A) 35(0) 7 4
Vent Air Exh.
Plant Service P44-F070-B 36(I) 6A 33 Water Return Plant Service P44-F069-A 36(0) 6A 33 Water Return Plant Service P44-F053-A 37(0) 6A 33 Water Supply Chilled Water P71-F150-(A) 38(0) 6A 12 Supply GRAND GULF-UNIT 1 3/4 6-31 Amendment No. -- 7 l
TABLE 3.6.4-1 (Continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUMBER Containment (Continued) 2 Analyzer E61-F596A-(A) 108A(0)
Ctat. H Sample Ctat. H2 Analyzer E61-F596B-(B) 108A(I)
Sample Ctat. H2 Analyzer E61-F598A-(A) 107B(0)
Sample Ret.
2 Analyzer E61-F5988-(B) 107B(I)
Ctat. H Sample Ret.
E61-F595A-(A) 107D(0)
Drywell H2 Analyzer Sample E61-F5958-(B) 107D(I)
Drywell H2 Analyzer Sample Ana-E61-F597A-(A) 107E(0)
Drywell H2 lyzer Sample Ret.
Ana-E61-F5978-(B) 107E(I)
Drywell H2 lyzer Sample Ret.
Drywell Fiss.
D23-F592-A
,109A(0)
Prod. Monitor Sample Drywell Fiss.
023-F591-B 109A(I) 1, Prod. Monitor Sample Drywell Fiss.
D23-F594-A 109B(0)
Prod. Mon.
Sapi. Ret.
Drywell Fiss.
023-F593-B 109B(I) 1 Prod. Mon.
Sep1. Ret.
Ctat. Press. Inst. M71-F594-B 109D(0)
(Post Acc. Sep1.)
Ctat. Press. Inst. M71-F595-A 109D(I)
(Post Acc. Sep1.)
Suppr. Pool Level E30-F593A-A 113(0)(c)
Inst.
Suppr. Pool Level E30-F592A-A 114(0)
Inst.
Suppr. Pool Level E30-F594A-A 115(0)(C)
Inst.
Suppi. Pool Level E30-F591A-A 116(0)
Inst.
Suppr. Pool Level E30-F5938-B-117(0)(c)
Inst.
Suppr. Pool Level E30-F592B-B 118(0)
Inst.
Suppr. Pool Level E30-F594B-B 119(0)(c)
Inst.
.(
Suppr. Pool Level E30-F5918-B 120(0)
Inst.
GRAND GULF-UNIT 1 3/4 6-37
r TABLE 3.6.4-1 (Continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUMBER b.
Drywell Cont. Cooling P42-F114-B 329(0)
Water Inlet Cont. Cooling P42-F116-A 330(I)
Water Outlet Cont. Cooling P42-F117-B 330(0)
Water Outlet 3.
Other Isolation Valves (9)#
a.
Containment Fuel Transfer F11-E015 4(I)
Tube Feedwater Inlet B21-F010A 9(I)
Feedwater Inlet B21-F032A 9(0)
Feedwater Inlet B21-F010B 10(I)
Feedwater Inlet B21-F0328 10(0) 11(0)((d)
RHR "A" Suction E12-F017A 12(0) d)
RHR "B" Suction E12-F017B RHR "C" Suction E12-F017C 13(0)(d)
RHR Shutdown E12-F308 14(I)
Cooling Suction RHR Heat Ex. "A" E12-F044A 20(I)
I to LPCI RHR Heat Ex. "A" E12-F025A 20(I) to LPCI RHR Heat Ex. "A" E12-F107A 20(I) to LPCI RHR Heat Ex. "B" E12-F025B 21(I) to LPCI RHR Heat Ex. "B" E12-F044B 21(I) to LPCI RHR Heat Ex. "B" E12-F107B 21(I) to LPCI RHR Heat Ex. "C" E12-F234 22(0) to LPCI RHR Pump "C" to E12-F041C-B 22(I)
LPCI RHR Pump "A" Test E12-F259 23(0)(*)
Line to Suppr.
Pool RHR Pump "A" Test E12-F261 23(0)(')
Line to Suppr.
Pool GRAND GULF-UNIT 1 3/4 6-38 Amendment No. 7 I
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TABLE 3.8.4.1-1 (Continu:d)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DtVICES c.
480 VAC Circuit Breakers (Continued)
Molded Case, Type NZM' TRIP
RESPONSE
BREAKER SETPOINT TIME SYSTEM / COMPONENT NUMBER (Amperes)
(Seconds)
AFFECTED 52-1542-10 320 0.100 DRYWELL COOLER FAN COIL UNIT (N1M518006A-A) 52-1542-14 5
0.100 M0V - DRYWELL COOLER INLET (N1P44F055-A) 52-1542-15 5
0.100 HOV - DRYWELL COOLER INLET (N1P44F057-A) 52-1542-16 5
0.100 MOV - DRYWELL COOLER INLET (N1P44F059-A) 52-1542-17 5
0.100 M0V - DRYWELL COOLER INLET (N1P44F061-A) 52-1542-18 5
0.100 MOV - DRYWELL COOLER INLET (N1P44F063-A) 52-1542-19 5
0.100 MOV - DRYWELL COOLER INLET (N1P44F065-A) 52-1542-21 800 0.100 SLCS OPERATING HEATER (N1C41D002) 52-1542-22 24 0.100 DRWL PURGE COMP AUX OIL PUMP (Q1E61C001A-A) 52-1542-23 500 0.100 REFUELING PLATFORM ASSY (Q1F15E003-A)
(
52-1542-26 175 0.100 DRYWELL RECIRC FAN (N1M51C001-A)
GRAND GULF-UNIT 1 3/4 8-31
F I
TABLE 3.8.4.1-1 (Continued)
PRIMARY CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES c.
480 VAC Circuit Breakers (Contir:ued)
Molded Case, Type NZM TRIP
RESPONSE
BREAKER SETPOINT TIME SYSTEM / COMPONENT NUMBER (Amperes)
(Seconds)
AFFECTED 52-1542-29 1200 0.100 STBY LIQ CONTROL SYS MIXING HEATER (Q1C41D003) 52-1611-10 12.5 0.100 MOV - DRYWELL COLL TK OUTLET ISOLATION (Q1G41F044-B) 52-1611-15 12.5 0.100 MOV - PSW CTMT STM TNL CLR ISOL (Q1P44F070-B) 52-1611-16 50 0.100 MOV-RHR RX HD
" ~ ~ ~
SPR INBD ISOL (Q1E12F394-B) 52-1611-25 12.5 0.100 MOV - DRYWELL CLG WTR ISOL (Q1P42F117-B) 52-1611-31 12.5 0.100 M0V - DRYWELL CLG WTR INL ISOL (Q1P42F114-B) 52-1611-32 32 0.100 MOV - CTMT CLG WTR ISOLATION (Q1P42F068-B) 52-1611-42 12.5 0.100 M0V PSW STEAM TUNNEL CLR ISOL (Q1P44F074-B) 52-1611-43 12.5 0.100 MOV PSW STEAM TUNNEL CLR ISOL (Q1P44F077-B) 52-1611-44 38 0.100 MOV - SERVICE AIR DRYWELL ISOLATION (Q1PS2F195-B)
GRAND GULF-UNIT 1 3/4 8-32 Amendment No. 7 l
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TABLE 3.8.4.1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES c.
480 VAC Circuit Breakers (Continued)
Molded Case, Type NZM TRIP
RESPONSE
BREAKER SETPOINT TIME SYSTEM / COMPONENT NUMBER (Amperes)
(Seconds)
AFFECTED 52-2621-03 7
0.100 M0V - DRWL HYDR INST LINE ISO (Q1E61F595B-B) 52-1621-04 7
0.100 M0V - DRWL HYDR INST LINE ISO (Q1E61F5978-B) i l
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GRAND GULF-UNIT 1 3/4 8-32a AmendmentNo..l.._l
TABLE 3.8.4.2-1 y.
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION
[
BYPASS DEVICE (CON-TINUOUS) (ACCIDENT SYSTEM (S)
VALVE NUMBER CONDITIONS) (NO)
AFFECTED Q1E51F010 Continuous RCIC System
.Q1E51F013 Continuous RCIC System Q1E51F019 Continuous RCIC System
-Q1E51F022 Continuous RCIC System Q1E51F031 Continuous RCIC System Q1E51F045 Continuous RCIC System Q1E51F046 Continuous RCIC System
.Q1E51F059 Continuous RCIC System Q1E51F068 Continuous RCIC System RCIC Trip and Throttle Continuous RCIC System Valve on Turbine Q1E51C002 Q1B21F065A No Reactor Coolant System Q1B21F065B No Reactor Coolant System Q1B21F098A No Reactor Coolant System Q1821F0988 No Reactor Coolant System Q1B21F098C No Reactor Coolant System Q1821F0980 No Reactor Coolant System Q1821F019-Continuous Reactor Coolant System
~
Q1821F067A Continuous Reactor Coolant System
.Q1821F0678 Continuous Reactor Coolant System Q1821F067C Continuous Reactor Coolant System Q1821F067D Conti Nous Reactor Coolant System Q1821F016 Continuous Reactor Coolant System Q1B21F147A Continuous MSL Drain Post LOCA Leak-age Control Q1B21F147B Continuous MSL Drain Post LOCA Leak-age Control Q1B33F019 Continuous Recirculation System Q1833F020 Continuous Recirculation System Q1833F125 Continuous Recirculation System Q1B33F126 Continuous Recirculation System Q1833F127 Continuous Recirculation System Q1B33F128 Continuous Recirculation System l
Q1D23F591 Drywell Monitoring System I-Q1D23F592 Drywell Monitoring System Q1023F593 Drywell Monitoring System Q1D23F594 Drywell Monitoring System Q1E12F040 Continuous RHR System Q1E12F023 Continuous RHR System Q1E12F006A Continuous RHR System Q1E12F052A Continuous RHR System Q1E12F008 Continuous RHR System Q1E12F394 Continuous RHR System,.__, _.
l GRAND GULF-UNIT 1 3/4 8-47 Amendment No. d _
.]
TABLE 3.8.4.2-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICE (CON-TINU0US) (ACCIDENT SYSTEM (S)
VALVE NUMBER CONDITIONS) (NO)
AFFECTED Q1E12F014A Continuous RHR System Q1E12F026A
' Continuous RHR System Q1E12F082A No RHR System Q1E12F082B No RHR System Q1E12F290A Continuous RHR System Q1E12F047A Continuous RHR System Q1E12F027A tcntinuous RHR System Q1E12F073A Continuous RHR System Q1E12F346 Continuous RHR System Q1E12F024A Continuous RHR System Q1E12F087A Continuous RHR System Q1E12F048A Continuous RHR System Q1E12F042A Continuous RHR System Q1E12F004A Continuous RHR System Q1E12F003A Continuous RHR System Q1E12F011A Continuous RHR System Q1E12F053A Contiouous RHR System Q1E12F037A Conti'nuous RHR System Q1E12F028A Continuous RHR System Q1E12F064A Continuous RHR System Q1E12F2908 Continuous RHR System
(
Q1E12F004C Continuous RHR System Q1E12F021 Continuous RHR System Q1E12F064C Continuous RHR System Q1E12F042C Continuous RHR System Q1E12F048B Continuous RHR System Q1E12F049 Continuous RHR System Q1E12F0378 Continuous RHR System Q1E12F0538 Continuous RHR System Q1E12F0748 Continuous RHR System Q1E12F0428 Continuous RHR System Q1E12F064B Continuous RHR System Q1E12F096 Continuous RHR System Q1E12F094 Continuous RHR System Q1E12F006B Continuous RHR System Q1E12F011B Continuous RHR System Q1E12F052B Continuous RHR System Q1E12F0478 Continuous RHR System Q1E12F0278 Continuous RHR System Q1E12F004B Continuous RHR System Q1E12F0878 Continuous RHR System Q1E12F0038 Continuous RHR System Q1E12F026B Continuous RHR System Q1E12F0248 Continuous RHR System Q1E12F028B Continuous RHR System Q1E12F009 Continuous RHR System f
Q1E12F073B Continuous RHR System GRAND GULF-UNIT 1 3/4 8-48