ML17139B836
| ML17139B836 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/28/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17139B837 | List: |
| References | |
| NUDOCS 8310120041 | |
| Download: ML17139B836 (23) | |
Text
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JO PENNSYLVANIA POWER Ec LIGHT COMPANY ALLEGHEH ELkC RIC C
0 EIN Vk, H
~ATION, Ullll' SUSQUEHANNA Att kLk At/l LU lk )
RA NG CkHbE J
Amendment Ho.
16 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) havin9 found that:
A.
The applications for amendments filed by the Pennsylvania Power 8 Light Company, dated January 31,
- 1983, and Nay 4, 1983, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended
( the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) 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 in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly,:the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraphs 2.C.(2) and 2.C.(6) of the Facility Operating License Ho. NPF-14 are hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment Ho. 16, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
- PPBL shall operate the facility in accordance with the Technical
'S'pecifications and the Environmental Protection Plan.
83l0i20041 8307128 PDR ADOCK 05000387 P
PDR OFFICE/
SURNAME/
DATEP
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ P ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ PP ~ ~ ~ ~ ~
NRC FORM 318110/801 NRCM 0240 OFFICIAL RECORD COPY
- UA. GPO 1983~00.247 V'
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IP l
W (6)
Fire Protection Pro ram PP&l. shall maintain in effect and fully implement all provisions of the approved Fire Protection Review Report, as amended through Revision 2 dated November 1982.
In addition, PP&L shall maintain the fire protection program set forth in Appendix R to 10 CFR Part 50.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY CON1ISSION
Attachment:
Changes to the Technical Specifications a~E3aX.<g~,e Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance:
September 28, 1983 OFFICE/
SURNAME)
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/83 NRC FORM 318 IIO/BOINRCM 0240 OFFIClAL RECORD COPY
- U.S. GPO 1983~00.247
I
ATTACHMENT TO LICENSE AMENDMENT NO.
Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 3-97 3/4 3-98 3/4 7-3 3/4 7-4 3/4 7-5 3/4 7-6 3/4 8-7 3/4 8-8 3/4 8-19 3/4 8-20 3/4 8-23 3/4 8-24 3/4 8-25 3/4 8-26 3/4 8-27 3/4 8-28 3/4 8-31 3/4 8-32 INSERT 3/4 3-97 3/4 3-98 3/4 7-3 3/4 7-4 3/4 7-5 3/4 7-6 3/4 8-7 3/4 8-8 3/4 8-19 3/4 8-20 3/4 8-23 3/4 8-24 3/4 8-25 3/4 8-26 3/4 8-27 3/4 8-28 3/4 8-31 3/4 8-32
AD m
TABLE 3.3.9-2 FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS FUNCTIONAL UNIT a.
Reactor Vessel Mater Level-High TRIP SETPOINT
< 54.0 inches ALLOMABLE VALUE
< 55 5 inches CD 2
CD Ct.
TABLE 4. 3. 9. 1-1 (Continued)
FEEDWATER/HAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT a.
Reactor Vessel Water Level-High CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED
P L'AN SYSTEMS ULTIMATE HEAT SINK 0
LIMITING CONDITION FOR OPERATION 3.7. 1.3 The spray pond shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and ".
ACTION:
a4 b.
With the groundwater level at any spray pond area observation well greater than or equal to 663'SL, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification
- 6. 9. 2 within the next 10 days outlining the cause of the high groundwater level and the plans for restoring the level to within the limit.
With the spray pond otherwise inoperable:
2.
In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and fn COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
In OPERATIONAL CONDITION 4 or 5, declare the,RHRSW system and the emergency service water system inoperable and take the ACTION required by Specifications 3.7.1.1 and 3.7.1.2.
3..
In Operational Condition ", declare the emergency service water system inoperable and take the ACTION required by Specification
- 3. 7. 1.2.
The provisions of Specification
- 3. 0.3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.1.3 b.
C ~
The spray pond shall be determined OPERABLE by verifying:
The average water temperature, which shall be the arithmetical average of the spray pond water temperature at the surface, mid and bottom
- levels, to be less than or equal to 88 F at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The water level at the overflow weir is greater than or equal to 677'ean Sea Level USGS (MSL), at least once per:
1.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when water level is
< 677'6" MSL, and 2.
14 days when water level is
> 677'6" MSL..
The groundwater level at observation'wells I, 3, 4, 5, 6, and 1113 to be less than 663'SL at least once per 31 days.
"When handling irradiated fuel in the secondary containment.
SUSQUEHANNA - UNIT 1 3/4 7-3 Amendment No.
1
PLANT SYSTEMS 3/4.7. 2 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM LIMITING CONDITION FOR OPERATION
- 3. 7. 2 Two independent control room emergency outsi.de.,ai.r supply~yafem subsystems shall be OPERABLE with each subsystem consisting of:
a.
One makeup fan, and b.
One filter train.
APPLICABILITY: All OPERATIONAL CONDITIONS and ".
ACTION:'.
In OPERATIONAL CONDITION 1, 2 or 3 with one control room emergency outside air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
In OPERATIONAL CONDITION 4, 5 or *:
1.
With one control room emergency outside air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the pressurization mode of operation.
2.
With both control room emergency outside air supply subsystems inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
c.
The provisions of Specification 3.0.3 are not applicable in Operational Condition *.
SURVEILLANCE RE UIREMENTS 4.7.2 Each control room emergency outside air supply subsystem shall be demonstrated OPERABLE:
a..
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters OPERABLE.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber
- housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the subsystem by:
"When irradiated fuel is being handled in the secondary containment.
SUSQUEHANNA - UNIT 1 3/4 7-4 Amendment No. 16
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued l.
Verifying that the subsystem satisfies the in-place testing acceptance criCeria and uses the test procedures of Regulatory Positions C.5.a, C.5.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 5810 cfm
+ 10K.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance wi.th Regulatory Position C. 6. b of Regulatory Guide
- 1. 52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C. 6. a of Regulatory Guide l. 52, Revision 2, March 1978.
3.
Verifying a subsystem flow rate of 5810 cfm + 10K during subsystem operation when tested in accordance with ANSI N510-1975.
C.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Positon C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C. 6. a of Regulatory Guide
- 1. 52, Revision 2, March 1978.
d.
At least once per 18 months by:
l.
Verifying that the pressure drop across the combined prefi lter, upstream and downstream HEPA filters and charcoal adsorber banks is less than 9. 1 inches Water Gauge while operating the subsystem at a flow rate of. 5810 cfm + 10K.
2.
Verifying that on each of the below isolation mode actuation test signals, the subsystem automatically switches to the isolation mode of operation and the isolation dampers close within 8 seconds:
a)
Outside air intake chlorine - high, b)
Outside air intake radiation - high, and c)
Reactor Building isolation.
3.
Verifying that on each of the below pressurization mode actuation test signals, the subsystem automatically switches to the pressurization mode of operation and the control structure is maintained at a positive pressure of 1/8 inch W.G. relative to the outside atmosphere during subsystem operation at a flow rate less than or equal to 58lO cfm:
a)
Reactor Building isolation, and b)
Outside air intake radiation - high.
Verifying that the heaters dissipate 30 + 3.0 Kw when tested in accordance with ANSI N510-1975.
SUSQUEHANNA - UNIT 1 3/4 7"5 Amendment No. 16
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued) e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95K of the OOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 5810 cfm + 10K.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 99.95K of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 5810 cfm + 10K.
SUSQUEHANNA - UNIT 1
'3/4 7"6
TABLE 4. 8. 1.
1. 2-1 DIESEL GENERATOR TEST SCHEDULE Number of Failures in Last 100 Valid Tests*
Test Fre uenc At least once per 31 days At least once per 14 days At least once per 7 days At least once per 3 days Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2 ~ e of Regulatory Guide l. 108, Revision 1, August 1977, where the last 100 tests are determined on a per nuclear unit basis.
For the purposes of this test schedule, only valid tests conducted after the OL issuance date shall be inc'luded in the computation of the "last 100 valid tests."
Entry into this test schedule shall be made at the 31 day test frequency.
SUSQUEHANNA - UNIT 1 3/4 8-7
TABLE 4. 8. 1. 1. 2"2 UNIT 1 AND COMMON DIESEL GENERATOR LOADING TIMERS DEVICE TAG NO.
K116A K116B K125A K125B 62X-20104 62X-20204 62X1-20304 62X1"20404 62X2-20304 62X2-20404 62X3-20304 62X3-20404 62X2-20310 62X2-20410 62AX2-20108 62AX2-20208 62AX2-20303 62AX2-20403 62X-516 62X-526 62X-536 62X"546 62A-20102 62A-20202 62A-20302 62A-20402 SUSQUEHANNA - UNIT 1 SYSTEM CS pp 1A CS pp 1B CS pp 1C CS pp 1D Emerg Switchgear Rm cooler A 8 RHR SN pp H8V fan A
Emerg Switchgear Rm cooler B 8 RHR SN pp H8V fan B
Control Structur e Chil lwater System Control Structure Chillwater System Control Structure Chillwater System Control Structure Chillwater System Control Structure Chi llwater System Control Structure Chillwater System Control Structure Chillwater System Control Structure Chillwater System Emerg SW Emer g SW Emerg SW Emerg SW DG Rm Exh Fan A
DG Rm Exh Fan B
DG Rm Exh Fan C
DG Rm Exh Fan D
RHR Pump 1A RHR Pump 1B RHR Pump 1C RHR Pump 1D 3/4 8-8 LOCATION 1C626 1C627 1C626 1C627 OC877A OC877B OC877A OC877B OC877A OC877B OC877A OC877B OC876A OC876B 1A201 1A202 1A203 lA204 OB516 OB526 OB536 08546 1A201 1A202 1A203 1A204 TIME SETTING 10.5 sec 10.5 sec 10 ~ 5 sec 10.5 sec 60 sec 60 sec 3 min 3 ml n
- 3. 5 min
- 3. 5 min 60 sec 60 sec 3 ml n 3 ml n 40 sec 40 sec 53 sec 57 sec 2 min 2 ml n 2 min 2 min 3 sec 3 sec 3 sec 3 sec Amendment No. 16
ELECTRICAL POWER SYSTEMS DISTRIBUTION -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, the following power distribution system divisions shall be energized:
a.
For A.C. power distribution, Division I or Division II with:
Division I consisting of:
a)
Load group Channel "A", consisting of:
1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A.C. motor control center b)
Load group Channel "C", consisting of:
1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A.C. motor control center c)
Load group 480 volt A. C. motor control centers 1A201 1B210 OB516 1A203 1B230 OB536
- OB517, OB136
- 1B216, 1B236
- 1B217, 1B237 1B219 2.
d)
Load group 208/120 volt A.C. instrument panels
- 1Y216, 1Y236 Division II consisting of:
a)
Load group Channel "B", consisting of:
1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A.C. motor control center b)
Load group Channel "D", consisting of:
1) 4160 volt A.C. switchgear bus 2) 480 volt A.C. load center 3) 480 volt A.C. motor control center c)
Load group 480 volt A.C. motor control centers 1A202 18220 OB526 1A204 1B240 OB546
- OB527, 08146
- 1B226, 1B246
- 18227, 1B247 1B229 d)
Load group 208/120 volt A.C. instrument panels lY226, lY246 SUSQUEHANNA - UNIT 1 3/4 8-19
ELECTRICAL POMER SYSTEMS LIMITING CONDITION FOR OPERATION Continued b.
For D.C.
power distribution, Division I or Division 2, with:
Division I consisting of:
a)
Load group Channel "A", consisting of:
1) 125 volt DC buses 2)
Fuse box b)
Load group Channel "C", consisting of:
1) 125 volt DC buses 2)
Fuse box c)
Load group "I", consisting of:
1) 250 volt DC buses 2)
Fuse box d)
Load group "I", consisting of:
1)
+ 24 volt DC buses 2)
Fuse box 2.
Division II consi sting of:
10612i 1D614 1D611
- 10632, 1D634 1D631
- 10652, 1D254 1D651 10672 10671 a) b)
c) d)
Load group Channel "B", consisting of:
1) 125 volt DC buses 2)
Fuse box Load group Channel "0", consisting of:
1) 125 volt DC buses 2)
Fuse box Load group "II", consisting of:
1) 250 volt DC buses 2)
Fuse box Load group "II", consisting of:
1)
+ 24 volt DC buses 2)
Fuse box
- 10622, 10624 10621
- 10642, 10644 10641
- 1D662, 10264, 10274 I
10661 10682 1D681 APPLICABILITY:
OPERATIONAL CONDITIONS 4, 5 and ".
1 "Mhen handling irradiated fuel in the secondary containment.
SUS(UEHANNA - UNIT 1 3/4 8-20 Amendment No.
16
ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued 2.
By selecting and functionally testing a representative sample of each type of fuse on a rotating basis.
Each representative sample of fuses shall include at least 10'f all fuses of that type.
The functional test shall consist of a non-destructive resistance measurement test which demonstrates that the fuse meets its manufacturer's design criteria.
Fuses found inoperable during these functional testing shall be replaced with OPERABLE fuses prior t'o resuming operation.
For each fuse found inoperable during thesenfunctional
- tests, an additional repgesentative sample of at least 10K of all fuses of that type shal P+e functionally tested until no more failures are found or all fuses of that type have been functionally tested.
b.
At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
SUSQUEHANNA " UNIT 1 3/0 8"23
TABLE 3. 8. 4. 1 -l PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES CIRCUIT BREAKER FRAME LOCATION TYPE" RATING/UL a.
T e
2 Molded Case Circuit Breakers+
1.
1B219022 HFB"M 150/30 TRIP SET POINT
~Am eres 270
RESPONSE
TIME (Mi1 1 i-seconds/
~Cc1 es SYSTEMS OR E UIPMENT POWERED HVB311F031A RRP IIA" DSCH VLV 2.
1B237043 3.
1B236052 4.
1B236023 5.
1B236011 6.
1B236033 7.
1B236021 8.
1B236032 9.
1B236042 10.
1B236043 11.
1B236082 12.
1B23 6102 13.
1B236053 HFB-M 150/30 HFB-M 150/30 HFB-M 150/3 HFB-M 150/30 HFB-M 150/30 HFB"M 150/30 HFB"M 150/30 HFB-M 150/30 HFB"M 150/30 HFB-M 150/30 HFB-M 150/3 HFB-M 150/5 270 215 18 250 220 175 180 150 160 150 45 NA NA NA NA NA NA NA HVB311F023A Recirc:
PP "A" Suction HVE111F009 RHR Pump Suction Shutoff HV12603 Containment Inst.
Compressor Suet.
Iso. Valve 1V413A - Drywel l Area Unit Cooler 1V414A - Drywel1 Area Unit Cooler 1V417A - Drywel 1 Area Unit Cooler 1V412A - Drywel 1 Area Unit Cooler 1V411A - Drywel 1 Area Unit Cooler 1V416A - Drywel 1 Area Unit Cooler 1V415A - Drywel1 Area Unit Cooler HVB211F001 - Reactor Head Vent Valve HVG331F001 - Reac.
Mtr. Clean up inboard isolation 14.
1B237072 HFB"M 150/5 SUSQUEHANNA - UNIT 1 3/4 8-24 25 HVB8211FO16 - Main Stm.
Line Drain Inbd.
Iso.
Amendment No.
16
TABLE 3.8.4.1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 16.
18237073 HFB"M 150/10 60
. TRIP CIRCUIT BREAKER FRAME SET POINT LOCATION TYPE" RATING/UL
~Am eras T
e 2 Molded Case Circuit Breakers (Continued)
+
15.
18219023 HFB"M 150/10 80
RESPONSE
TIME (Mi 1 1 i-seconds/
~Ccles)
NA NA SYSTEMS OR E UIPMENT POWERED HVB311F032A -
RRP "A" Dsch Byps Vlv HVE111F022 - Reac Heater Spray Shutoff Inboard 17.
18237082 18.
18246011 19.
18229022 20.
18246022 21.
18246051 22.
18246061 23.
18229023 24.
18246072 25.
18246081 26.
18246091 27.
18246102 28.
18246103 HFB-M 150/10 HFB"M 150/30 HFB"M 150/30 HFB-M 150/5 HFB"M 150/30 HFB"M 150/30 HFB-M 150/10 HFB-M 150/30 HFB"M 150/30 HFB"M 150/30 HFB-M 150/30 HFB-M 150/30 70 270 270 40 170 170 70 170 170 160 215 170 NA NA NA NA HVE411F002 - HPCI Stm.
Supply Inboard Iso.
HVB311F0238-Reactor Recirc Pump Suction HVB311F0318-Reactor Recirc Pump Disch HVE511F007 - RCIC Inbrd Steam Line 150 lV4178 - Drywel 1 Area Unit Clr Fan 1V4148 - Drywel 1 Area Unit Cl r Fan HV8311F0328 -
RRP "8" Dsch Byps Vlv lV4158 - Drywel 1 Area Unit Clr Fan 1V4168 - Urywel 1 Area Unit Clr.
Fan 1V4118 - Orywel1 Unit Clr.
Fan lV4138 - Drywel 1 Area Unit Clr.
Fan lV4128 - Drywel 1 Area Unit Clr.
Fan SUSQUEHANNA " UNIT 1 3/4 8-25 Amendment No.
16
30.
1B246113 31.
1B246062 32.
1B246 012 33.
1B253063 HFB-M 150/3 HFB-M 150/3 HFB-M 150/3 HFB-M 150/5 20 18 18 NA NA TABLE 3. 8. 4. 1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
RESPONSE
TIME TRIP (Mi1 1 i-CIRCUIT BREAKER FRAME SET POINT
= seconds/
LOCATION TYPE*
RATTNGlUL
~(Am eres
~Ccl es T
e 2 Molded Case Circuit Breakers (Continued)
+
29.
1B246112 HF8 "M 150/3 8
~
NA SYSTEMS OR E UIPMENT POWERED HVB211F002 - Reactor Head Vent Valve HVB211F005 - Reactor Heat Vent Valve HV11346 -
RBCCW Containment Iso. Vlv.
HV11345 "
RBCCW Containment Iso. Vlv.
1P402A - Drywell Floor Draw Sump IIAII P P IIAll 34.
1B253053 35.
1B263043 36.
1B263053 37-1826308l 38.
1B263071 39.
1B253043 40.
1B263072 41.
1B253021 42.
1B263023 HFB-M 1SO/S HFB"M 150/3 HFB-M 150/3 HFB"M 150/3 HFB-M 150/5 HFB-M 150/5 HFB-M 150/5 HFB-M 150/50 HFB-M 150/50 27 10 12 20 20 20 480 480 NA NA NA NA NA HVG331F102 " Line Suction Inside Control Valve HVG331FIOO -
RWCU Loop "lA" Suction HVG331F106 -
RWCU Loop "B" Suction HVG331F101 -
)
Sys Vessel Drain Line Recirc.
1P4023 -
Or Ywe11 Floor Drain Sump IIAll PP 1P403A - Drywell Floor Drain Sump IIBII Pump IIAII lP403B - Drywell Floor Drain Sump II8 II P P HVB211F011A Feedwater Inlet Shutoff Valve HVB211F011B - Feed-water Inlet Shutoff Valve HFB-M - Westinghouse Type HFB, magnetic only
+Each location no. represents two breakers; A and B, in series.
SUSQUEHANNA - UNIT 1 3/4 8-26 Amendment
"'o.
TABLE 3.8.4. 1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES CIRCUIT BREAKER LOCATION b.
T e 3 Molded Case Circuit Breakers l.
1B236103 2.
'B246033 3.
1B226103 4.
1B216 092 TYPFAe KB-TM KB-TM KB"TM KB-TM FRAME RATING/UL 250/150 250/150 250/150 250/150
RESPONSE
TIME (Mi1 1 i-seconds/
~Cc1 ee NA NA NA SYSTEMS OR E UIPMENT POWERED 1E440C - Containment
)
Recomb El'ect. Htr. Ass'y.
1E4400 - Containment Recomb Elect. Htr. Ass'y.
1E440B - Containment Recomb Elect. Htr. Ass'y.
1 E440A - Containment Recomb.
Elect. Htr. Ass'y.
""KB-TM - Westinghouse Type KB, Thermal-magnetic SUSQUEHANNA - UNIT 1 3/4 8-27 Amendment No. 15
ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION 3.8.4.2 The thermal overload protection of each valve shown in Table 3.8.4.2-1 shall be bypassed continuously by an OPERABLE bypass device integral with the motor starter.
APPLICABILITY:. Whenever the motor operated valve is.'required to be OPERABLE.
ACTION:
I I
With thermal overload protection for one or more of the above required valves not bypassed continuously by an OPERABLE integral bypass
- device, take admin-istrative action to continuously bypass the thermal overload within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the affected valve(s) inoperable and apply the appropriate ACTION statement(s) for the affected system(s).
SURVEILLANCE RE UIREMENTS 4.8.4.2. 1 The thermal overload protection for the above required valves shall be verified to be bypassed continuously by an OPERABLE integral bypass device by verifying that the thermal overload protection is bypassed for those thermal overloads which are continuously bypassed and temporarily placed in force only when t'e valve motors are undergoing periodic or maintenance testing:
a.
At least once per 18 months for those thermal overloads which are continuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing.
b.
Following maintenance on the motor starter.
4.8.4.2.2 The thermal overload protection for the above required valves which are continuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing shall be verified to be bypassed following periodic or maintenance testing during which the thermal overload protection was temporarily placed in force.
SUSQUEHANNA - UNIT 1 3/4 8-28
TABLE 3.8.4.2-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALVE NUMBER HY-Ell-lF028B HV-Ell"1F047B HV-Ell-lF016B HY-Ell-1F003B HV-Ell-1F017B HY-E21" 1F031B HV-E21-1F001B HV-Ell-lF103B HY-Ell-lF075B HV-Ell-1F0738 HY-Ell"1F0060 HV-Ell-1F004D HV-Ell-1F024B HY-E21-1F015B HY-E21-1F004B HV-E21-1F005B HV-E32-1F001K HV-E32-1F002K HV-E32-1F003K HV-E32-1F001P HV-E32-1F002P HV-E32-1F003P HV-E32-1F001B HV-E32-1F002B HV-E32-1F003B HV-E32" 1F001F HV-E32-1FOOZF HV-E32-1F003F HV-E32-1F006 HV-E32-1F007 HV-E32" 1F008 HV-E32-1F009 HV-E51-1F045 HV-E51-1F012 HV-E51-1F013 HY-15012 HV-E51-'1F046 HV-E51-1F008 HV-E51-1F031 HV-E51-1F010 SYSTEM(S)
AFFECTED RHR RHR RHR RHR RHR CS CS RHR RHRSW RHRSM RHR RHR RHR CS CS CS MSIV MSIV MSIV MSIV MSIV MSIV MSIV MSIV MSIV MSIV MSIY MSIV MSIV MSIV MSIV MSIV RCIC RCIC
'RCIC RCIC RCIC RCIC RCIC RCIC SUSQUEHANNA - UNIT 1 3/4 8-31 Amendment No.
16
TABLE 3.8.4.2-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD. PROTECTION VALVE NUMBER HV-E51-1F019 HV"E51-1F060 HV-E51" 1F059 HV"E51-1F022 HV-E51" 1F062 HV-E41-1F012 HV-E41" 1F001 HV"E41-1F011 HV-E41" 1F006 HV"E41-1F079 HV-E41-1F059 HV-E41-1F004 HV"E41-1F003 HV-E41" 1F042 HV-E41-1F075 HV-E41"1F008 HV-E41" 1F007 HV-E41-1F066 HV-G33"1F004 HV-B21-1F019 HV-Ell-1F008 HV"Ell-1F023 HV"Ell"1F049 HV"B31-1F032A HV-B31"1F032B HV"B31-1F031A HV-B31-1F031B SYSTEM(S)