ML20073K671
| ML20073K671 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/13/1983 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073K674 | List: |
| References | |
| TAC-49980, TAC-49981, NUDOCS 8304200404 | |
| Download: ML20073K671 (82) | |
Text
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DUKE POWER COMPAllY L
DOCKET NO. 50-369 I
MCGUIRE NUCLEAR STATION, UNIT 1 A'1EtiDMENT TO FACILITY OPERATING LICENSE 5
i Amendment No. 20 Licens? !!o. NPF-9 1
1.
The Nuclear Regulatory Connission (the Commission) has found that:
A.
The application for anondment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License Ho. flPF-9 fil2d by the Duke Power Conpany (licensee) dated March 24, 1983, complies with i
the standards and requirements of the Atoraic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, as amended, the provisions of the Act, and the rem lations of the Com-mission; C.
There is reasonable assurance: (1) that the activities authorized by this amendent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comaission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this 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 attachments to this license amendnent and paragraph 2.C.(2) of Facility Operating License No. !!PF-9 is hereby amended to read as follows:
8304200404 030413 PDR ADOCK 05000 P
3.;
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, are hereby incorporated into this license. The licensee 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 COMMISSIO!!
Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes i
Date of Issuance: April 13, 1983
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l DUKE POWER COMPANY DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated March 24, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amerded, the provisions of the Act, and the regulations of the Com-mission; C.
There is reasonable 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 in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amndment is in accordance with 10 CFR Part 51 of the Conmission'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 attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
r-b 2-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.1, are hereby incorporated into this license. The licensee 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 C0f4 MISSION Elinor G. Adensam. Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: April 13, 1983 i
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ATTACHMENT TO LICENSE AMENDMENT NO.20 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-359 AND-TO LICENSE AMENDME'NT NO. l' FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following -pages of _ the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain
- a vertical line indicating the_ area of change. The corresponding overleaf pages are also' provided to maintain. document completeness.
Amended Overleaf Page Page I.
II-1-2 1-1 1 1-5 3/4 3-42 3/4 3-41 3/4 46 3/4 3-45 3/4 3-58 3/4 3-57 3/4 3-67 3/4 68 3/4 3-74 3/4 3-73 3/4 4-2
-3/4 4-1 3/4 4-3 3/4 4-4
-3/4 4-25 3/4 4-26 3/4 4-28~
3/4 4-27 3/4 5-8 3/4 5-7 3/4 6-2 3/4 6-1 3/4 6-3 3/4 6-4 3/4 6-10 3/4 6-9 3/4 7-21 3/4 7-22 3/4-7-26 3/4 7-25 3/4 7-27 3/4 7-28 3/4 _7-33 3/4 7-34 3/4 8-20 3/4 8-19 3/4 8-21 3/4 8-22
-3/4 8-24 3/4 8-23
'3/4 8-?7.
3/4 8-28 3/4 8-29 3/4 8-30
4
.i' ATTACHMENT TO LICENSE AMENDMENT N0. 20 AND NO.~1 (CON'T) i Amended-Overleaf Page.
-Page
.'3/4.8-34'
-3/4 8 3/4 8-38 3/4 8-37 3/4 8 3/4--8-46 3/4: 8-49 3/4 8-50 3/4 8-56.
3/4 '8-55 3/4 8-57 3/4 - 58 ~:
3/4 8-59 3/4-8 - 3/4 8-66:
3/4.8-65 3/4 ~8-67
' 3/4-;8-68 3/4 8. 3/4 -.8-72 3/4-12-3 3/4 12-4
- 3/4.
12-7...
3/4 12. 3/4 12-13 3/4 12-14 l
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INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 ACTI0N........................................................
1-1
- 1. 2 ACTUATION LOGIC TEST............
1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST...............................
1-1 1.4' AXIAL FLUX DIFFERENCE.........................................
1-1 1.5 -CHANNEL CALIBRATION...........................................
1-1 1.6 CHANNEL CHECK.................................................
1-1 1.7 CONTAINMENT INTEGRITY.........................................
1-2 1.8 CONTROLLED LEAKAGE............................................
1-2 1.9 CORE ALTERATION...............................................
1-2 1.10 DOSE EQUIVALENT I-131.........................................
1-2 1.11 E-AVERAGE DISINTEGRATION ENERGY...............................
1-2 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME......................
1-3 1.13 FREQUENCY N0TATION............................................
1-3 1.14 IDENTIFIED LEAKAGE............................................
1-3 1.15 MASTER RELAY TEST.............................................
1-3 1.16 MEMBER (S) 0F THE PUBLIC.......................................
1-3 1.17 0FFSITE DOSE CALCULATION MANUAL...............................
1-4 1.18 OPERABLE - OPERABILITY........................................
1-4 1.19 OPERATIONAL MODE - M0DE.......................................
1-4 1.20 PHYSICS. TESTS.................................................
1-4 1.21 PRESSURE BOUNDARY LEAKAGE.....................................
1-4 i
l 1.22 PROCESS CONTROL PROGRAM......................................
1-4 Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 I
Amendment No. 20 (Unit 1) i i
INDEX DEFINITIONS-
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- SECTION PAGE
- 1. 2 3 P U R G E - P U R G I N G................................................
1-5 1.24. QUADRANT POWER TILTLRATI0......................................
1-5
.?
' I ?5 RATED THERMAL P0WER............................................
1-5 1.26 REACTOR BUILDING INTEGRITY.....................................
1-5
- 1.27 REACTOR TRIP SYSTEM RESPONSE TIME..............................
1-5 1.28 REPORTABLE-0CCURRENCE..........................................
1-5 1.29 SHUTDOWN MARGIN................................................
1-6 1.30 SITE B0VNDARY..................................................
1-6 1.31 SLAVE RELAY TEST...............................................
1-6 1.32 SOLIDIFICATION.................................................
1-6 1.33SOURCECHECK..T................................................
1-6
~
l 1.34 STAGGERED TEST BASIS...........................................
'l-6 1.35 THERMAL P0WER..................................................
1-6 1.36 TRIP ACTUATING DEVICE OPERATIONAL TEST.........................
1-7 1.37 UNIDENTIFIED LEAKAGE...........................................
1-7 1.38 UNRESTRICTED AREA..............................................
1-7 1.39 VENTILATION EXHAUST TREATMENT SYSTEM...........................
1-7 1.40 VENTING........................................................
1-7 1.41 WASTE GAS HOLDUP SYSTEM........................................
1-7
-TABLE 1.1, FREQUENCY N0TATION....................................... 8 TABLE 1.2, OPERATIONAL M0 DES........................................
1-9 II McGUIRE - UNITS 1 and 2
1.0 DEFINITIONS-t The defined terms of this section appear i.n capitalized type and a're applicable throughout these Technical Specifications.
ACTION 1.1' ACTION shall be that.part of a Technical Specification which prescribes remedial measures required under designated conditions.
ACTUATION LOGIC TEST 1.2' An ACTUATION LOGIC TEST shall be the application of various simulated input combinations in conjunction with each possible interlock logic state and verification of the required' logic output. -The ACTUATION LOGIC TEST shall include a continuity checks -as a minimum, of output devices.
ANALOG CHANNEL OPERATIONAL-TEST 1.3 : An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify 0PERABILITY of' alarm, interlock and/or trip functions.
The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy..
AXIAL FLUX DIFFERENCE i
1.4 AXIAL FLUX DIFFERENCE _shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.
CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it ' responds with the required range and accuracy to known values of input.-
The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or. total channel steps such that the entire channel is calibrated.
CHANNEL CHECK
- 1.6 A CHANNEL CHECK shall be the' qualitative assessment of channel behavior during operation by observation.
This. determination shall include, where possible, comparison of the channel indication and/or status with other -
indications and/or status derived from independent instrument channels measuring the same paramete,r.
McGUlRE - UNITS I and 2 1-1
DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT' INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system,~or 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-2 of-Specification 3.6.3.
b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with~ the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and e.
The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0 rings) is OPERABLE.
CONTROLLED LEAKAGE
- 1. 8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor. pressure vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of.1-131, I-132, I,133, I-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the sample) of the sum of the average beta and gamma energies per' disintegration (MeV/d) for the radionuclides in the sample.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 1-2 Amendment No. 20 (Unit 1) v
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DEFINITI0'NS:
y PURGE - PURGING'
'1. 23 : PURGE or PURGING shall be the-. controlled process of discharging air or
- gas from'a confinement to maintain temperature, pressure, humidity, concentra.
- tion ~ or-other ' operating condition, in such a' manner that replacement air or -
gas is required-to purify. the, confinement.
LQUADRANT' POWER TILT RATIO 1.24 : QUADRANT POWER TILT ~ RATIO shall be the ratio of the maximum upper excore detector calibrated output to the _ average of the upper excore detector cali-brated outputs, or the._ ratio of the maximum lower excore detector calibrated:
output to the average of the lower excore detector calibrated outputs, (whichever is. greater. ' With one excore detector-inoperable, the ' remaining three detectors shall be used for computing the average.
-RATED T'HERMAL' POWER 1.25 RATED THERMAL POWER shall be a total': core heat transfer rate to the reactor coolant of 3411 MWt.
REACTOR BUILDING-INTEGRITY 1.'26'REACTORBUILD5NGINTEGRITYshallexistwhen:
a.
'Each door:in each access opening is closed except when the access-opening is being used for normal transit entry and exit, then at
'least one door shall be. closed, b.
The Annulus Ventilation System is in compliance with the requirements of _ Specification 3.6.1.8, and
- c.
The' sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.
REACTOR TRIP SYSTEM RESPONSE TIME 1.27 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at'the channel. sensor until loss of stationary gripper coil voltage.
REPORTABLE OCCURRENCE 1.28 - A REPORTABLE' OCCURRENCE shall be any of those conditions specified in Speci fications 6. 9.1.10 'and 6. 9.1.11.
McGUIRE - UNITS I and 2 1-5
DEFINITIONS SHUTDOWN MARGIN 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which
.the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are
. fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE BOUNDARY 1.30 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SLAVE RELAY TEST 1.31 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay.
The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.
SOLIDIFICATION 1.32 SOLIDIFICATION shall be the immobilization of wet radioactive wastes such as evaporator bottoms, spent resins, sludges, and reverse osmosis concentrates as a result of a process of thoroughly mixing the waste type _with a SOLIDIFICATION agent (s) to form a free standing monolith with chemical and physical characteristics specified in the PROCESS CONTROL PROGRAM (PCP).
SOURCE CHECK 1.33 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS 1.34 A STAGGERED TEST BASIS shall consist of:
l a.
A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train, or other designated l
component at the beginning of each subinterval.
1 THERMAL POWER 1.35 THERMAL POWER shall be the total core heat transfer rate to the reactor coolant.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 1-6 Amendment No. 20 (Unit 1) m m
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TABLE 3.3-6 5
g; RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS c:
MINIMUM CHANNELS CHANNELS APPLICABLE ALARM / TRIP g
MONITOR TO TRIP / ALARM OPERABLE MODES SETP0 INT ACTION
[
1.
Containment Atmosphere 1
1 1,2,3,4 26 g
Gaseous Radioactivity-i High (Low Range-EMF-39) s,
~4 2.
Spent Fuel Pool 1
1
< 1.7 x 10 30 Radioactivity-High pCi/ml (EMF-42) 3.
Criticali ty-1 1
-< 15 mR/hr 28 Radiation Level R)
(Unit 1-1 EMF-17 and Unit 2-2 EMF-4) a w
I, 4.
Gaseous Radioactivity-
-N.A.
1 1,2,3,4 N.A.
29 RCS Leakage: Detection (Low Range - EMF-39) 5.
Particulate N.A.
1 1,2,3,4 N.A.
29 Radioactivity-RCS Leakage Detection (Low Range - EMF-38)
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~%
MINIMUM 8
CHANNELS CHANNELS APPLICABLE ALARM / TRIP g
MONITOR TO TRIP / ALARM.
OPERABLE' MODES SETPOINT ACTION 5
6.
Control Room Air 1.per station 2 per
'All
< 3.4 x 10 27
~4 4
Intake Radioactivity-station pCi/ml.
s g
High.
o.
(EMF-43a and 43b) ro l
TABLE NOTATION 1
With fuel in the fuel storage. areas or fuel building.
5 With irradiated fuel-in the fuel storage areas or fuel building.
q Must satisfy the requirements of Specification 3.11.2.1.
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y ACTION STATEMENTS ACTION 26.- 'With less than the Minimum Channels OPERABLE requirement, operation may continue
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provided the containment purge valves are ma,intained closed.
ACTION 27 - With the number of operable channels one less than.the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate the Control Room Ventilation System outside air intake which contains-the' inoperable instrumentation.
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ES ACTION.28 -.With less than.the Minimum Channels OPERABLE requirement, operation may continue for j
E 5.
up to 30 days provided an appropriate portable continuous monitor with the same Alarm ES Setpoint is provided in the fuel pool area'.
Restore the inoperable monitors to
[5 OPERABLE status within 30 days or suspend all operations involving fuel movement in 4
,o g the fuel building.
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ACTION 29.-
Mu'st satisfy the ACTION requirement for Specification 3.4.6.1.
nn EE ACTION 30 - With less than the minimum channels.0PERABLE requirement, operation may continue provided the Fuel Handling Ventilation Exhaust System requirements of Specifica-J g
tion 3/4.9.11 are met.
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INSTRUMENTATION MOVABLE INCORE DETECTORS-LIMITING CONDITION FOR OPERATION 3.3.3.2 The-Movable'Incore Detectio'n System shall be_0PERABLE with:
~
a.
'At;least 75% of the detector thimbles, b.
- A minimum of two detector thimbles per core.qusdrant, and
. c.-
' Sufficient' movable detectors, drive,'and readout-equipment ~-to map-these thimbles.
APPLICABILITY: When the Movable Incore Detection System is used for:
a.
Recalibration of the-Excore. Neutron Flux Detection System, b.
Monitoring the QUADRANT POWER TILT RATIO,_or H' I (Z) and F c.
Measurement of F Q
xy ACTION:
With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions.. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
, SURVEILLANCE REQUIREMENTS 4.3.3.2 = The Movable Incore Detection System shall be demonstrated OPERABLE-at least once,per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by normalizing each detector output when required for:
~
'a.'
Recalibration of the Excore Neutron Flux Detection System, _ or b.
Monitoring the QUADRANT POWER TILT RATIO, or H' I (Z), and Fxy*
c.
Measurement of F Q
McGUIRE - UNITS 1 and 2 3/4 3-45 a
INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3' The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.
APPLICABILITY:
At all times.
. ACTION:
a.
With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlininc the cause of the malfunction and the plans for restoring the instru-ment (s) to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-4.
4.3.3.3.2 Each of the above accessible seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the seismic event.
Data shall be retrieved from accessible actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.
Data retrieved from the triaxial time-history accelerograph shall include a post-event CHANNEL CALIBRATION obtained by actuation of the internal test and calibrate function immediately prior to removing data.
CHANNEL CALIBRATION shall be performed immediately after insertion of the new recording media in the triaxial time-history accelo-graph recorder.
A Special Report shall be prepared and submitted *.o the Commission' pursuant to Specification 6.9.2, with a copy to Director, Office of Nuclear Reactor Regulation, Attention:
Chief, Structural and Geotechnical Engineering Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 10 days describing the magnitude, frequency spectrum, and resultant effect
~
upon facility features important to safety.
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Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 3-46 Amendment No. 20 (Unit 1)
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TABLE 4.3-7
??g ACCIDENT MONITORING. INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
CHANNEL
-CHANNEL'
- INSTRUMENT
_ CHECK CALIBRATION g
1.
Containment Pressure M'
R a
1' 2.
Reactor Coolant Temperature - T and TCOLD (Wide Range)
M R
H0T g
3.
Reactor Coolant Pressure - Wide Range M
R
-; k 3
a
_9 4.
Pressurizer Water Level M'
R. ~
5.
Steam L'ine Pressure
~ M
\\ R
~
?
6.
Steam Generator Water Level - Narrow Range M~
R.
7.
Refueling Water Storage Tank Water Level
' M
'R 8.
Auxiliary Feedwater Flow Rate
'M R'
Y l
g 9.
Reactor Coolant System Subcooling Margin Monitor M
R 10.
PORV Position Indicator.
M R
11.
PORV Block Valve Position Indicator-M R
12.
Safety Valve Position Indicator
.M R
13.
Containment Water Level (Wide Range)
M lR-14.
In Core Thermocouples M
R 15.
Unit Vent - High Range Noble Gas Monitor M
R (High-High Range - EMF-36) 16.
Steam Relief - High Range Monitor M
R g.
(Unit'1 - EMF.-24, 25, 26, 27)
~
(Unit 2 - EMF-10,11,12,13)
[.
17.
ContainmentAtmosphere-HighRangeMonitors/N i
fw M
R-
.n (EMF-51a or 51b) 1-
"/'
j__i
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' INSTRUMENTATION
. FIRE DETECTION INSTRUMENTATION LIMITING CONDITION-FOR OPERATION
'3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
ACTION:
a.
With any, but not more than one-half the total in any fire zone, W-Function A fire detection instruments shown in Table 3.3-11 inoperable, restore'the inoperable instrument (s) to OPERABLE status within 14 days or within the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at-least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air, temperature at least once per hour at the locations given in Specification 4.6.1.5.1 or l
4.6.1.5.2.
b.
With more than'one-half of the Function A fire detection instruments in any fire zone _ shown in Table 3.3-11 inoperable, or with any Function B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or a re adjacent fire detection instruments shown inl Table 3.3-11 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the.
inoperable instrument (s) at least once per. hour, unless the instrument (s) is located inside the containment, then inspect that c
containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the contain-ment air. temperature at least once per hour at the locations given in Specification 4.6.1.5.1 or 4.6.1.5.2.
Y c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of.the above re' quired fire detection instruments which are g
[
accessible during' plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.
Fire detectors which are not.' accessible during plant operation shall be demonstrated OPERABLE by the performance of a TRIP ' ACTUATING DEVICE OPERATIONAL TEST during l
each COLD SHUTDOWN exEpiing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
4 e,
Each of thi above required fixeo temperature / rate of rise detection instruments l.
. shall bd dem'onstrated OPERABLE as follows:
[
h' j~-4 Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4-3-58 Amendment No. 20 (Unit 1)
.s b.
l f
+
,?
~
r TABLE 3.3-12 4
y 9,
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 5
g MINIMUM CHANNELS INSTRUMENT EERABLE-ACTION 4
ezq 1.
Radioactivity Monitors Providing Alarm m
And Automatic Termination of Release
~
a.
Waste Liquid Effluent Line (EMF-49) il per station 31
,aa b.
Containment Ventilation Unit Condensate Line (EMF-44) 1 33 4
N 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of-Release Conventional Wastewater Treatment Line (EMF-31) 1-32
- l 4
4 3.
Continuous Composite Samplers And Sampler Flow Monitor a.
Containment Ventilation Unit Condensate Line 1 per station 33 -
w b.
Conventional Wastewater Treatment Line 1 per station 33 i
w4 4.
Flow Rate Measurement Devices j
a.
Waste Liquid Effluent Line 1 per station 34-b.
Discharge Canal Minimum Flow Interlock
- 1 per station 34 c.
Containment Ventilation Unit Condensate Line 1
34-
~
d.
Conventional Wastewater Treatment Line 1 per station 34 l
E2-l k h
- Minimum flow is assured by an interlo'ck terminating waste liquid releases if minimum dilution flow is not-gg available.
,e OZ t
.O SS.
r+ r+
HM vu
?
1
TABLE 3.3-12 (Continued)
ACTION STATEMENTS ACTION 31 -
With the number of channels OPERABLE less than required by the
-l Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
At least two technically qualified members of the facility staff independently verify the discharge line valving:
1)
The manual portion of the computer input for the release rate calculations performed on the computer, or 2)
The entire release rate calculations if such calcula-tions are performed manually.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 32 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity for up to 30 days at a lower limit of detection of at least 10 7, microcurie /ml:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, and b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-Curie / gram DOSE EQUIVALENT I-131.
ACTION 33 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radioactivity at a lower limit of detection of at least 10 7 microcurie /ml.
ACTION 34 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump performance curves generated in place may be used to estimate flow.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 3-68 Amendment No. 20 (Unit 1)
m.
TABLE 3.3-13 (Continuedl
?g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION m
MINIMUf1 CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION E::
5.
Containment Purge System m
Noble Gas Activity Monitor - Providing j
g Alarm and Automatic Termination of Releasc 1
38-(Low Range.- EMF-39) o-N 6.
Auxili'ar.y Building Ventilation System Noble Gas Activity Monitor (EM?-41 or 1
37 EMF-36) 7.
Fuel Storage Area Ventilation System R
Noble Gas Activity Monitor (EMF-42 or EMF-36) 1 37 8.
Contaminated Parts Warehouse Ventilation-System a.
Noble Gas Activity Monitor (EliF-53) 1 per station 37 b.
Flow Rate Monitor 1 per station 36 c.
Sampler Minimum Flow Device 1 per station 36 9.
Raawaste Facility Ventilation System a.
Noble Gas Activity Monitor (EMF-52) 1 per station 37 b.
Flow Rate Monitor 1 per station 36 c.
Sampler Minimum Flow Rate 1 per station 36
TABLE 3.3-13 (Continued)
TABLE NOTATION
- At all times.
During WASTE GAS HOLDUP SYSTEM operation.
- During gaseous effluent releases.
ACTION STATEMENTS ACTION 33 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:
a.
At least two independent samples of the tank's contents are analyzed, and b.
At least two technically qualified members of the facility staff independently verify the discharge valve 1{neup:
1)
The manual portion of the computer input for the release rate calculations performed en the computer, or 2)
The entire release rate calculations if such calcula-tions are performed manually.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 36 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 37 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ano these samples are analyzed for gross radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 38 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING or VENTING of radioactive effluents via this pathway.
ACTION 39 -
With the number of channels OPERABLE one les>.han required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days.
With two channels inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 40 -
With the number of channels OPERABLE loss than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may cone.inue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
ACTION 41 -
With the number of channels OPERABLE one less than reqJired by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 3-74 Amendment No. 20 (Unit 1)
l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1' REACTOR COOLANT LOOPS'AND COOLANT CIRCULATION STARTUP AND POWER-0PERATION.
LIMITING CONDITION FOR'0PERATION 3.4.1.1 All react 6r coolant loops shall be'in operation.
- APPLICABILITY:
MODES 1 and 2.*
ACTION:
With less than the above required reactor coolant loops in operation, be in, at least HOT STANDBY within 1< hour.
SURVEILLANCE REQUIREMENT 4.4.1.1 The above required reactor. coolant loops shall be verified in operation and circulating reactor coolant at least once'per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i 1-A 53ee Special Test Exception'3.10.4.
McGUIRE -' UNITS 1 and 2 3/4 4-1 ymr g
g.
.m l-y-9
REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 At least two of the reactor coolant loops listed below shall be OPERABLE and at least one of these reactor coolant loops shall be in operation:*
a.
Reactor Coolant Loop A and its associated steam generator and reactor coolant pump, b.
Reactor Coolant Loop B and its associated steam generator and reactor coolant pump, c.
Reactor Coolant Loop C and its associated steam generator and reactor coolant pump, and d.
Reactor Cooiant Loop D and its associated steam generator and reactor coolant pump.
APPLICABILITY:
MODE 3 ACTION:
a.
With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 />.
b.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required reactor coolant loop to operation.
SURVEILLANCE REQUIREMENTS l
4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying cerrect breaker alignments and indicated power availability.
4.4.1.2.2 The required steam generators shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 12% at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I 4.4.1.2.3 At least one reactor coolant loop shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
l (1) no operations are permitted that would cause dilution of the Reactor l
Cuolant System boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature, Amendment No. 1 (Unit 2) i McGUIRE - UNITS 1 and 2 3/4 4-2 Amendment No. 20 (Unit 1) l l
REACTOR COOLANT SYSTEM HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3' At least two of the reactor coolant 1and/or residual heat removal
- (RHR) loops listed below shall be OPERA 8LE'and at least one-of-these.
l-reactor coolant and/or RHR loops shall be'in operation:**
n
. a.
Reactor Coolant Loop A and its associated. steam generator and, reactor coolant pump,*
b.
Reactor Coolant _ Loop B and its associated steam generator and reactor coolant pamp,*
c.
' Reactor Coolant Loop C and its associated steam generator and reactor coolant pump,*
d.
' Reactor Coolant loop D and.its associated steam generator and reactor coolant pump;"
e.
RHR Loop.A, and
' f.
RHR Loop B.
APPLICABILITY:
MODE 4.
ACTION:
a.
With less than the ~above required reactor coolant and/or.RHR. loops OPERABLE,.immediately. initiate corrective action to return the required loops to OPERABLE status as soon as possible; if the remaining OPERABLE loop is an RHR loop, be in COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With no reactor coolant or RHR loop ~ in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to l
return the required coolant loop to operation.
4 L
- A reactor coolant pump shall not be started with one or more of the Reactor L
Coolant System cold: leg temperatures less than or equal to 300*F unless:
L
.(1) the pressurizer water volume is less than 1600 cubic feet, or (2) the secondary water-temperature of each steam generator is less than 50 F above each of the Reactor Coolant System cold leg temperatures.
- All' reactor coolant pumps and RHR pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
(1) no operations are permitted that would cause dilution of the L,.
Reactor Coolant System boron concentration, and (2) core outlet temperature i
is maintained at least 10*F below saturation temperature.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 4-3 Amendment No. 20 (Unit 1)
L t
_ SURVEILLANCE REQOIREMENTS'
~
4.4.1.3.1 The required reactor co)lant~ pump (s), if not in operation, shall be determined OPERABLE once.per 7 days by verifying correct breaker alignments
- and' indicated power availability.
~
~ 4.4.1.3.2.The required steam generator (s) snall be determined OPERABLE by verifying ' secondary side. water. level to be greater than or equal to 12%.at-lea'st once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
' 4.4.1.3.3 At least~ one reactor coolant or RHRLloop;shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t 4
McGUIRE - UNITS 1 and 2 3/4 4-4 1
' REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the reactor coolant shall be limited to:
a.
Less than or equal to 1.0 microcurie per gram DOSE EQUIVALENT I-131, and b.
Less than or equal to 100/E microCuries per gram of gross specific activity.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
ACTION:
MODES 1, 2 and 3*:
a.
With the specific activity of the reactor coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 but within the Allow-able Limit (below and to the left of the lina) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that the cumulative operating time under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12-month period; b.
With the total cumulative operating time at a reactor coolant specific activity greater than 1.0 microcurie per gram DOSE EQUIV-ALENT I-131 exceeding 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6 month period, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days indicating 1.he number of hours above this limit; c.
With the specific activity of the reactor coolant greater than 1.0 microcerie rer gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one cor.tinuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; avg d.
With_the gross specific activity of the reactor coolant greater than 100/E microcuries per gram, be in at least HOT STANDBY with T less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and avg e.
The provisions of Specification 3.0.4 are not applicable.
- With T greater than or equal to 500 F.
avg Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 4-25 Amendment No. 20 (Unit 1)
[$
ACTION:
(Continued)
MODES 1, 2, 3, 4, and 5:
With the specific activity of the reactor coolant greater than -
1.0 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram of gross specific activity, perform the mmpling and analysis requirements of Item 4.a) of Table 4.4-4 until t.e specific activity of the reactor coolant is restored to within its limits.
In lieu of any other report required by Specification 6.9.1, for this ACTION statement within 30 days, prepare and submit'a Special Report to the Commis-sion pursuant to Specification 6.9.2 with a copy to the Director, Nuclear Reactor Regulation, Attention:
Chief, Core Performance Branch, and Chief, Accident Evaluation Branch, U.S. Nuclear Regulatory Commission, Washington, D.C., 20555. This report shall contain the results of the specific activity analyses together with the.following information:
1.
Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; 2.
Results of the last isotopic analysis for radiciodines performed prior to eEqeeding the li~mit, while limit was exceeded, and one analyris after the radioiodine activity was reduced to less than the limit, including for each isotopic analysis, the date and time of samplirig and the radiciodine concentrations; 3.
Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first s' ole in which the limit was exceeded; 4.
History of degassing operations, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; and 5.
The time duration when the specific activity of the reactor coolant exceeded 1.0 microcurie per gram DOSE EQUIVALENT I-131.
SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the reactor coolant shall be detercined to be i
within the limits by performance of the sampling and analysis program of Table 4.4 4.
McGUIRE - UNITS 1 and 2 3/4 4-26 I:
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t i
e 20 30 40 50 GO 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE tiQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY > 1.0 pCi/ GRAM DOSE EQUIVALENT I-B 1 McG" IRE - UNITS 1 and 2 3/4 4-27
i TABLE 4.4-4 m
REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE g
AND ANALYSIS PROGRAM m
8 TYPE OF MEASUREMENT SAMPLE-AND ANALYSIS MODES IN WHICH SAMPLE g-AND ANALYSIS i REQUENCY AND ANALYSIS REQUIRED Z
m 1.
Gross Specific Activity At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 1,2,3,4 H
Determination **
2.
Isotopic Analysis for DOSE EQUIVA-1 per 14 days 1
N LENT I-131 Concentration 1
3.
Radiochemical for E Determination ***
1 per 6 months
- 1
~#'
4.
Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, l,'2,3,4,5 Including I-131, I-133, and I-135 whenever the specific activity exceeds 1.0
,g pCi/ gram DOSE c
EQUIVALENT I-131
[
or 100/E pCi/ gram of co gross radioactivity, and b) One sample between 2 1,2,3 i
and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER
[p within a 1-hour period.
I E. @
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=
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22
- 5. S.
ee
EMERGENCY CORE-COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2)
' A visual inspection of the' containment sump :and verifying that the subsystem suction. inlets are not restricted by-debris and that the sump components (trash racks, screens, etc.) show no evidence of structural-distress or abnormal corrosion, e.
At least 'once per 18 months, during shutdown, by:
1)
Verifying that each automatic valve in the flow path actuates to its correct position on Safety Injection actuation and automatic switchover to Containment Sump Recirculation test
_ signals, and 2)
~ Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:
a)
Centrifugal charging pump, b)-
Safety Injection pump, and c)
RHR pump.
r
f.
By verifying that each of the following pumps develops the indicated
('
differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:
1)
Centrifugal charging pump 2 2380 psid, 2)
Safety Injection pump 1 1430 psid, and 3)
RHR pump 1 160 psid.
g.
By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
1)
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and
[
I McGUIRE - UNITS I and 2 3/4 5-7
?
EMERGENCY CORE COOLING SYSTEMS
. SURVEILLANCE REQUIREMENTS.(Continued) 2)-
At least once per 18 months.
Boron Injection Safety Injection Throttle Valves Throttle Valves Valve Number Valve Number-NI-480 NI-488 NI-481 NI-489
-NI-482 NI-490 NI-483:
NI-491 f
h.
By performing a flow balance test, during shutdown, following
. completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
1)
For centrifugal charging pump lines, with a-single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 345 gpm, and b)
The total pump flow rate is less than or equal to 565 gpm.
2)
For Safety Injection pump lines, with a single. pump running:
a)
The sum of the injection line flow rates, excluding.the-highest flow rate,.is greater'than or' equal to 462 gpm, and b)
The total pump flow rate is less than or. equal to 660 gpm.
3)
For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3975 gpm.
4 Amendment No. 1 (Unit 2)
McGUIRE_- UNITS 1 and 2-3/4 5-8 Amendment No. 20.(Unit 1)
3/4.6 CONTAINMENT SYSTEMS L :-
3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION
~3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or be in at least HOT STANDBY within.the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTD0bH within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
(
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
5 a.
At least once per 31 days by verifying that all penetrations
- not' capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3; b.
By verifying that each containment air lock is in compliance with Specification 3.6.1.3; and After each closing of each penetration subject to Type B testing, c.
except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with. gas at P,these seals is
,14.8 psig, and verifying that when the measured leakage rate for added to the leakage rates determined pursuant to Specifica-tion 4.6.1.2d. for all other Type 8 and C penetrations, the combined leakage rate is less than 0.60 L,.
Except valvesi, blind flangbs, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUT 07nH except that such verification need not be performed more often than once per 92 days.
McGUIRE - UNITS 1 and 2 3/4 6-1
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE' 4
LIMITING CONDITION FOR OPERATION
'3.6.1.2. Containment leakage rates shall be limited to:
a.
- An 'overall integrated leakage ' rate of:
1)
Less than~~or equal to L, 0.20% by weight of the containment air.per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-at P,,,14.8 psig, or
- 2)
Less than or equal to L,LO.14% by weight of the containment
~
air.per24 hours >atarkducedpressureofP,74.psig.
t b.
A combined leakage rate.of less than 0.60 L for all penetrations' andvalvessubjecttoTypeBandC. tests,w$enpressurizedtoP,,
and.
Acombinedbypassleakagerateof.lessthan0.07L)forall c.
penetrations identified in Table 3.6-1 as secondar containment-bypass leakage paths when pressurized to P,.
APPLICABILITY:
MODES 1,= 2, 3, and 4.
ACTION:
With.(a) the measured overall integrated containment leakage rate exceeding '
0.75 L or 0.75-L as applicable, or (b) the measured combined leakage.
l ratefrallpenekr,ationsandvalvessubjecttoType'sBandCtestsexceeding 0.60 L, or (c) the combined bypass leakage rate exceeding 0.07 L,
restor $theoverallintegratedleakageratetolessthan0.75L 8rlessthan
-or equal-to 0.75 L, as applicable, and the combined leakage rafe for all penetrationsandvkives,subjecttoTypeBandCteststolessthan0.60L,,
-and the combined bypass leakage rate to less than 0.07 L prior to l
l increasing'theReactorCoolantSystemtemperatureabovef00*F.
SURVEILLANCE REQUIREMENTS lI-4.6.1.2 The containment leakage rates shall be demonstrated at the followiig test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI l'
N45.4-1972 or the mass plot method:
i L
l l
l Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-2 Amendment No. 20 (Unit 1)
(
,4
CONTAINMENT SYSTEMS
~
SURVEILLANCE REQUIREMENTS'(Continued) a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 t 10 month intervals during shutdown-at either P,14.8 psig, or at P, 7.4 psig, during each 10 year service $eriod.
Thethirdtektofeachsetshallbeconducted during the shutdown for the 10 year plant inservice inspection; b.
If any periodic Type A test fails to meet either 0.75 L or 0.75 L thetestscheduleforsubsequentTypeAtestsshallbefeviewedanb, approved by the Commission.
If two consecutive Type A tests fail to meet either 0.75 L or 0.75 L, a Type A test shall be performed at leastevery18monthsuntiltboconsecutiveTypeAtestsmeeteither 0.75 L or 0.75 L at which time the above test schedule may be t
resume 8; c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1)
Confirms the accuracy of the Type A test by veri ying th t the difference between supplemental and Type A test t ta is W hin 0.25 L,, or 0.25 L i t
2)
Has a duration sufficient to establish accurately the chang in leakage rate between the Type A test and the supplemental test; and 3)
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25% of the total measured leakage at P,,
14.8 psig, or P ' 7*4 PSI '
t 9
d.
Type B and C tests shall be conducted with gas at P, 14.8 psig, at intervalsnogrederthan24monthsexceptfortest$ involving:
1)
Air locks, 2)
Dual ply bellows assemblies on containment penetrations between the containment building and the annulus, and 3)
Purge supply and exhaust isolation valves with resilient material seals.
e.
Purge supply and exhanst isolation valves with resilient material seals shall be tested.nd demonstrated OPERABLE by the requirement, of Specification 4.6.1.9.3 or 4.6.1.9.4, as applicable; f.
The combined bypass leakage rate shall be determined to be less than 0.07 L by applicable Type B and C tests at least once per 24 months a
except for penetrations which are not individually testable; penetra-tions not individually testable shall be determined to have no detect-able leakage when tested with soap bubbles while the containment is pressurized to P,, 14.8 psig, or P, 7.4 psig, during each Type A test; g
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-3 Amendment No. 20 (Unit 1)
COMTAINMENT SYSTEMS
(.
- SURVEILLANCE REQUIREMENTS (Continued) g.
Air locks shall be tested and demonstrated OPERABLE per Specification 4.6.1.~3; h.
The space between each dual ply bellows-assembly on containment
. penetrations between the containment building and the annulus shall be vented to the annulus during Type A tests.
Following completion of each Type A test, thel space between each dual ply bellows assembly shall be subjecteo.to a-low pressure' test at 3-S psig to verify no detectable leakage or the dual ply bellows assembly shall be subjected to'a. leak test with the pressure on the containment side of the dual ply bellows assembly at P, 14.8 psig, or P '
7.4: psig, to verify the leakage to be wit $1n the limits of t Specification 4.6.1.2f.;
i.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced Integrated Leakage Measurement System; and j.
The provisions of Specification 4.0.2 are not applicable.
J t
s McGUIRE - UNITS 1 and 2 3/4 6-4
TABLE 3.6-1(Continued)
. x SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS E
PENETRATION TEST 1
NUMBER SERVICE RELEASE LOCATION TYPE M280
' Sample from Accumulator
. Auxiliary Building Type.C M342 Auxiliary Seal Injection AuxjliaryBuilding Type C
=
Line from Annulus to E
Reactor Coolant Pumps N
M394
.. Ice from Rotary Valve Auxiliary Building Type C Assembly to Ice Condenser Cyclone Receiver M255 ILRT Pressure Impulse Line Auxiiiary Building Type C R.
4 5
a 1
4
CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air-lock shall be OPERABLE with:
a.
Both doors closed except when the air lock is being used for normal
- transit entry and exits through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of less than 0.05 L, at P,,14.8 psig.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
a.
With one containment air lock door inoperable:
1.
Maintain at least the OPERABLE air lock door closed and either restore the inoperable' air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed, 2.
Operation may then continue until performance of the next required overall air lock leakage' test provided that' the OPERABLE air lock door is verified to be locked closed at least once per 31 days, 3.'
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in C9LD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and 4.
The provisions of Specification 3.0.4 are not applicable, b.
With the containment air lock inoperable, except as' the result'of an inoperable air lock door, maintain.at least ene air lock door closed; restore the inoperable air lock to OPERABLE status within 24' hours or be in at least HOT STANDBY within the n(xt 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l-l I
i l
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-10 Amendment No. 20 (Unit 1) r
a
. PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
Functional Tests'(Continued) at 1sast one-half _ the size of the_ initial sample'shall be tested until the total-number tested is equal to the initial sample size multiplied by,the factor,1 + C/2, where "C'_' isnthe number of:
' snubbers'found which.do not meet'the functional test acceptance criteria..This plan be plotted using an " Accept" line which follows
'the equation N.= 55(1 + C/2).
Each snubber should be plott'd as e
soon'as it is tested.
If the point plotted falls on or below the " Accept",line, testing may be discontinued.
If the point plotted falls above the " Accept"=line, testing.must continue-unless'all snubbers have been tested.
Th'e representative samples for the functional test sample plans shall be randomly. selected from the snubbers required by Specifi-
. cation 3.7.8_and reviewed before beginning the testing.
The review shall ensure as far_as practical that'they are representative of the various configurations, operating environments, range of sizes, and capacities.
Snubbers placed in the same locations as snubbers which failed the previous _ functional test..shall be retested at the time of the next functional. test but shall not be included in the sample i
. plan.
If during the functional testing, additional sampling is required due to. failure of only one type of snubber, the functional testing results shall be reviewed at that time to determine if' additional samples should be limited to the type of snubber which' j.
has failed the functional testing.
f.
Functional Test Acceptance Criteria The snubber functional test shall verify that:
1)
Activation (restraining action) is achieved within the specified range in both tension and compression, except that inertia dependent, acceleration limiting mechanical snubbers may be tested to verify only that activation takes place in both_ directions of travel; 2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; 3)
Where required, the force required to initiate or maintain motion of the snubber is within the specified range in.both I
direction of travel; and 4)
For snubbers specifically required.not-to displace under continuous load, the ability of the snubber to withstand load
~
without displacement.
Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be
. correlated to the specified parameters through established methods.
g.
Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 7-21 Amendment No. 20 (Unit 1) l i
I m
-. - a.
a_,
PLAN 7 S_YSTEMS SURVEILLANCE REQUIRElENTS (Continu!d) _,
[
g.
Functional Test Failure Analysis (Continued) failure.
The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which may be subject to the same failure mode.
~
For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached.
'!he purpose of this engineering evaluation shall be to determine.if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains. capable of meeting the-designed service.
If any snubber selected for functional testing either fails to activate or. fails to move, i.e., frozen-in place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be evaluated in a manner to ensure their OPERABILITY.
This testing requirement shall be independent of the r.equirements stated in Specification 4.7.8e.
for snubbers not meeting the functional test acceptance criteria.
h.
Functional Testing _ of Repaired and Replaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have. repairs which might af fect the functional test result shall be tested to meet the functional test criteria before installation in the unit.
Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent-service, and freedom-of-motion test must have been performed within 12 months before being installed in the unit.
i.
Snubber Seal Replacement Proaram The seal service life of hydraulic snubbers shall be monitored to ensure that the service life is not exceeded bet een surveillance inspections.
The expected service life for the various seals, seal materials, and applications shall be determined and established based on engineering informatien and the seals shall be replaced so that the expected service life will not be exceeded during a period when the snubber is required to be OPERABLE.
The seal replacements shall be documented and the documentation shall be retained in accordance with Specif% cation 6.10.2.
McGUIRE - UNITS 1 and 2 3/4 7-22 k
PLANT SYSTEMS
. TABLE 3.7-4a (Continued)
SAFETY-RELATED HYDRAULIC SNUBBERS
- SMALL SIZE MEDIUM SIZE LARGE SIZE (1,250 lbs. or less (10,350 lbs. to (45,500 lbs. to SYSTEM **
TO 3,000 lbs) 27,300 lbs) 68,200 lbs)
ND 5
1 0
NI 6
1 0
NS 2
0 0
NV 4
0 0
SM 0
40 10 SV.
3 0
0 Subtotal (Unit 2) 41 L1 18 TOTAL FOR UNITS 1 & 2 d28 268
_56 I.
4
- Snubbers may be added or deleted without prior License Amenda.ent to Table 3.7-4a provided that a revision to Table 3.7-4a is included with the next License Acendment request.
In lieu of any other report required by Specification ~6.9.1, at least 15 days prior to the deletion of any listed snubber, a Special Report shall be prepared and submitted to the Commission in accordance with Specification 6.9.2 evaluating the safety significance of the proposed snubber removal.
- A listing of individual snubbers and more detailed information shall be available for NRC review at the McGuire Nuclear Station.
McGUIRE - UNITS 1 and,2 3/4 7-25
PLANT SYSTEMS TABLE 3.7-4b SAFETY-RELATED MECHANICAL SNUBBERS *
]
PACIFIC SCIENTIFIC SMALL SIZE MEDIUM SIZE LARGE SIZE (350 lbs. or less (1,487 lbs. to (50,000 lbs._to SYSTEM **
TO 600 lbs) 15,000 lbs) 120,000 lbs)
UNIT 1 AS-0
-2 0
BB 92 31 0
BW 6
2 0
CA 2
18 0
CF 5
9 O
W 1
9 1
KC 16 23 1
KF 2
2 0
NB 30 3
0 NC 24 50 1
.ND 6
12 1
NF 0
3 0'
NI 20 25 0
-NM 20 8
0 NV 43 35 0
RF 0
2 0
RN 2
9 11 RV 13 11 0
SA 0
8 0
SM 0
10 8
- Snubbers may be added or deleted without prior License Amendment to Table 3.7-4b provided that a revision te Table 3.7-4b is included with the next License Amendment request.
In lieu of any other report required by Specification 6.9.1, at least 15 days prior to the deletion of any listed snubber, a Special Report shall be prepared and submitted to the Commission in accordance with Specification 6.9.2 evaluating the safety significance of the proposed snubber removal.
- A listing of individual snubbers and more detailed information shall be.
available for NRC review at tht McGuire Nuclear Station.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 7-26 Amendment No. 20 (Unit 1)
PLANT SYSTEMS TABLE 3.7-4b (Continued)
SAFETY-RELATED MECHANICAL SNUBBERS
- PACIFIC SCIENTIFIC-SMALL SIZE MEDIUM SIZE LARGE SIZE-(350 lbs. or Less (1,487 lbs. to (50,000 lbs. to SYSTEM **
TO 600 lbs) 15,000 lbs) 120,000 lbs)
SV 0
3 0
VE 1
3 0
VI 30 1
0 VQ
.0 2
0 WG 2
0 0
WL 8
0 0
WS 2
0 0
YC 1
1 0
Subtotal (Unit 1) 326 282 23 UNIT 2 BB 67 55 0
CA 9
59 0
CF 13 80 8
FW 0
4 1
KC 66 81 0
KD 3
'l 0
KF 2
5 0
LO 1
2 0
NB 5
1 0
NC 100 95 2-ND 29 41 0
- Snubbers may be added or deleted without prior License Amendment to Table 3.7-4b provided that a revision to Table 3.7-4b is included with the next License Amendment request.
In lieu of any other report required by Specification 6.9.1, at least 15 days prior to the deletion of any listed snubber, a Special Report shall be prepared and submitted to the Consission in accordance with Specification 6.9.2 evaluating the safety significance of the proposed snubber removal.
- A listing of individual snubbers and more detailed information shall be available for NRC review at the McGuire Nuclear Station.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 7-27 Amendment No. 20 (Unit 1)
PLANT SYSTEMS TABLE 3.7-4b (Continued)
SAFETY-RELATED MECHANICAL SNUBBERS
- 1.
PACIFIC SCIENTIFIC SMALL SIZE ~
MEDIUM SIZE LARGE SIZE
- (350 lbs. or Less' (1,487-Lbs. to (50,000 lbs. to SYSTEM **
TO 600 lbs) 15,000 lbs) 120,000 lbs).
NF 2
2 0
NI-56 56 3'
NM 42 11 0
NR 10 8
0 NV 170 69 0
RF' 1
3 0
RN 28 34 1
RV 9
8 0
SA 9
12 0
SM 2
24 30 SV 0
1 0
TE 1
3 0
VE-3 2
0 VG 1
2 0
VI 26 1
0 VN 0
4 0
VQ 3
1 0
VS 1-0 0-VX 2
1 0
WL 15 7
0 W
0 2
0 Subtotal (Unit 2) 676 675 45-TOTAL for UNITS 1 and 2 1,002 957-65
- Snubbers may be added or deleted without prior License Amendmer.t to Table 3.7-4b provided that a revision to Table 3.7-4b is included with the next License Amendment request.
In lieu of any other report required by Specification 6.9.1, at_least 15 days prior to the deletion of any listed snubber, a Special Report shall be prepared and submitted to the Commission in accordance with Specific-ation 6.9.2 evaluating the safety significance of the proposed snubber removal.
- A listing of individual snubbers and more detailed information shall be
~ available for NRC review at the McGuire Nuclear Station.
Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 7-28 Amendment No. 20 (Unit 1) i-
^-
=-
i
?h[
.I.
$k PLANT SYSTEMS SURVEILLANCE REQUIREMENTS
- .~ r
~
4.7.10.1 The. Fire Suppression Water System shall be demonstrated OPERABLE:
a,
.At[least once per 31 days on a STAGGERED TEST BASIS, by starting each
's
- electric motor-driven pump and operating it for at least 15 minutes on recirculation flow,
~
~
J b.
At least once per 31 days, by verifying that each valve (manual, power-operated, or automatic) in the flow path is in its correct
- position, c.
At least once per 6 months, by performance of a system flush of the outside distribution loop to verify no flow blockage, I
d.
At least once per 12 months, by cycling each testable valve in the flow path through at least one complete cycle of full travel, At 'least once' der 18 months, by performing a system functional test e.
which includes simulated automatic actuation of the system throughout its operating sequence, and:
1)
Verifying 'that each automatic valve in the flow path actuates to its correct position, 2)
Verifying thtt each pump develops at least 2500 gpm at a system pressure of 125 psig,
+
3).
Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 4)
Verifying that each fire suppression pump starts (sequentially) to maintain the Fire Suppression Water System pressure greater than or equal to 125 psig.
f.
At least once per 3 years, by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.
Amendment No. 1 (Unit 2)
.McGUIRE - UNITS 1 and 2 3/4 7-33 Amendment No. 20 (Unit 1)
~
m n
.a
-r-
\\
~
3 PLANT SYSTEMS
. ;f[
SPRAY AND/OR SPRINKLER SYSTEMS
(
e y
l LIMITING C0K01 TION f0R OPERATION s,,.
?/
l 3.7.10.2 The,following Spray and/or Sprink er Systems shall be OPERABLE:
3' s
a' o - Elevatibn 695 ft. - Auxilip y Building
<1 R[omNo!
Equipment
\\
f ~-
- - ~A
^ }C-t 501ii RHR' Pump 1A 500 4
RHR Puitp 1B'
/-506 RHR. Pump 2A 4
0 507 RHR Pump 2B E^P 508.
Corridor
\\
- b.
Elevation 716'ft. - Auxiliary Building Rooni Nb.
Equipment 600 Aux. FW Pump Room - Unit 1 649 Nuclear Services Water Pumps 627 Centrifugal Charging Pump 1A 630 Centrifugal Charging Pump 1B 601 Aux.,FW Pump Room - Unit 2 634...
Centrifugal Charging Pump 2A
., L' -
637 Centrifugal Charging Pump'2B 7
'648 Cable Shaft c.,
Elevation 733 ft. - Auxiliary Building Room No.
Equipment 72.)
Component Cooling Pumps 707-Battery Room Trench Area t
d.,
Elevatiosy[(50ft.-AuxiliaryBuilhing
+v f
' Woom No.
Equipinent -
) 801 Cable. Room - Unit 1
/.
I 801C Cable Room - Uni,t 2 806
.,Compo'nent Cooiing Pumps e.
Elevation 725 f t. - Reactor Buildt.1g 1)
Pipe Corridor
?
- 2)' Lower Containme,nt Ventilation Filters eA f.
Elevetion 738 ft. - Reactor Building Annulus 4
\\
x e.
9 0*
5%
McGUIRE - UNITS 1 and 2 3/4 7-34 j.-
I.
4 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c)
For.each circuit breaker found inoperable during these
- functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
2)
By' selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.
Circuit breakers selected for functional testing shall be selected on a rotating basis.
For the lower voltage circuit breakers the nominal Trio Setpoint and overcurrent response times are listed in Table 3,8-1.
Testing of these circuit breakers shall cor.sist of injecting c current in excess of the breakers nominal setpoint and measuring the response tina.
The measured response time will be compared to the manufacturer's data to insure that it is less than or equal to a value speci-fied by the manufacturer.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prioF'to resuming operation.
For each circuit breaker found inoperable during these functional tests, an additional repre-
/
sentative sample of at least 10% of all the circuit breakers of 1
the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested; and 3)
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% of.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 inoper-able during these functional tests shall be replaced with OPERABLE fuses prior to resuming operation.
For each fuse found inoperable during these furctional tests, an additional representative sample of at least 10% of all fuses of that type
- hall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.
b.
At least once per 63 mot,ths by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
McGUIRE - UNITS 1 and 2 3/4 8-19
~
+i g
TABLE 3.8-l'a UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES' I
E TRIP SETPOINT OR
RESPONSE
CONT. RATING TIME DEVICE NUMBER & LOCAT_ ION (AMPERES)
(SECONDS)
SYSTEM POWEREO m
s g
1.
6900 VAC-Swgr
[
Primary Bkr-RCP1A 5.0 15.4 @ 25A' Reactor Coolart Pump 1A Backup Brk-1TA-5 5.0 16.5 @ 20A Primary Bkr-RCP1B 5.0 15.4 @ 25A Reactor Coolant Pump 1B Backup Brk-1TB-5 5.0 16.5 @ 20A Primary Bkr-RCPIC 5.0 15.4 0 25A Reactor Coolant Pump 1C Backup Brk-1TC 5.0 16.5 @ 20A cp Primary Bkr-RCP1D 5.0 15.4 @ 25A Reactor Coolant Pump 1D g
Backup Brk-1TD-5 5.0 16.5 @ 20A 2.
600 VAC-MCC 1EMXA-2 10 Primary Bkr 20 45 @ 60A NC Pump IC Thermal Barrier 20 N.A.
Outlet Auto Isol Viv 1KC345A Backup Fuse
>5E 1EMXA-2 1E
- 5. $
Primary Bkr 20 45 @ 60A NC Pump 1A' Thermal Barrier l}
Backup Fuse 20 N.A.
Outiet Auto Isol V1v 1KC394A ev"
= _.
1EMXA-2 2A F
Primary Bkr 20 45 0 60A Cont Air Return Fan 1A Damper gg Backup Fuse 20 N.A.
IRAF-D-2 22 S. S.
ee a
y TABLE 3.8-la (Continued)
UNIT 1 CONTAINMENT PENETRATION CONDUCTOR'0VERCURRENT PROTECTIVE DEVICES-i s
TRIP SETPOINT OR
RESPONSE
0
-CONT. RATING TIME 4
l d
DEVICE NUMBER &' LOCATION (AMPERES)
_SECON0Q SYSTEM POWERED
(
~
j g
2.
600 VAC-MCC (Continued) a m
IEMXB-4 7C Primary Bkr 20 45 @ 60A SG 1D Blowdown Line Sample Backup Fuse 20 N.A.
Cont Isol Viv IFM220B 1ENXB-5 1A Primary Bkr 20
.45 0 60A H2 Purge Exhaust Cont Vessel Backup Fuse 20
.N.A.
Isol V1v IVE6B f
s#
1EMXB-5 1C T
Primary Bkr 20 45 @ 60A H2 Skimmer Fan 18 Suction O
Backup Fuse 20 N.A.
Isol Viv_1VX2B 1EMXC-1A
?
Prinary Bkr 200 250 @ 600A Lower Containment Cooling.
Backup Fuse 200 N.A.
Unit No. lA 1EMXC-2A E>
Primary 5kr 200 250 @ 600A Lower Containment Cooling 4
l
[5 Backup h e 200_
N.A.
Unit No. 1C aa
$5 1EMXC-3C
.i i
"5 Pr-: mary Bkr 100 110 @ 300A Control. Rod Drive Vent Fan
_Fp Beckup Fuse 100 N.A.-
No. 1A -
E$s 1EMXC-30 1
Primary Bkr 100 110 @ 300A Control R'od Drive Vent Fan na
((
Backup Fuse 100 N.A.
No. 1C 1
ee DU i
y TABLE 3.12-1 Eg RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM j
m e
c NUMBER OF h
REPRESENT.*TIVE m
EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY H
AND/0R SAMPLE
' SAMPLE LOCATIONS COLLECTION TREQUENCY OF ANALYSIS
(
1.
Direct Forty routine monitoring stations Quartcrly.
Gamma dose quarterly.
Radiation (2) either with two or more dosimeters or with one instrument for measur-ing and recording dose rate con-2 tinuously, placed as follows:
An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; w1 An outer ring of stations, one in s7 each meteorological sector in 4
the_6-to.8-km range from-the site; and The balance.of the stations i
be placed in special interest i
areas such as population cen-p, ters, nearby residences, ea schools, and in one or two
}
hk areas to serve as control j
mg stations.
"5 i
- O a-i e
CC hh
~m t
I
TABLE 3.12-1 (Continued) 2 N_.
RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM
. NUMBER OF-REPRESENTATIVE c-EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY.
II) 5 AND/OR SAMPLE SAMPLE-LOCATIONS COLLECTION FREQUENCY OF ANALYSIS' s[.
2.
Airborne Radioiodine and Samples from five locations:
Continuous sampler Radiciodine Cannister:
o, A
Particulates Three. samples from close to the operation with sample.
1-131 analysis weekly.
three SITE BOUNDARY.1ocations, collection weekly, or m
in different sectors, of the more' frequently if highest calculated annual i
required by' dust Particulate Sampler:
average groundlevel D/Q.
loading.
Gros.; beta radioactivity
- analysisfollogg-filter change;.
g One sample from the vicinity.of Gamma isotopic analysis a ccmmunity having the highest of composite (by calculated annual average ground-
. location) quarterly, level D/Q.
w One sample from a control location, M
as for example 15-30 km distant i
andintheggastprevalentwind di recti on.'
3.
Waterborne Gamma isotopic analysis (5)
Surface (6)
One sample upstream.
Compositesampigver a.
One samplo downstream.
1-month period.
monthly.- Composite for..
tritium analysis quarterly, b.
Ground Samples from one or two sourc Quarterly.
Gamma isotopic ( ) and triti only if likely to-be affected analysis quarterly.
c.
Drinking One' sample'of each of one to Composite sample I-131 analysis on each g
i three of the nearest water over 2-week period composite when the dose supplies that could be affecten when I-131~ analysis-calculated for the co7sur p-by its discharge.
is performed, monthly tion of.the water is g otG composite otherwise.
than 1 mrem per year.
One sampic from a control positeforgross.betaag.
location.
gamma isotopic' analyses
~
monthly.
Composite for j
tritium' analysis quarterly.
.m
.s 0
1 l
s t
i.
i y
TABLE 3.12-1 (Contirued)
I TABLE NOTATION
~
j' m
i g
(1) Specific parameters of distance and direction sector from the. centerline of one reactor, and additional:
4 a
description where pertinent, shall be provided for each and every sample location in Table 3.12-1 ir, a table and figure (s) in the 0DCM.
Refer to NUREG-0133,. " Preparation of Radiological Effluent Technical m
Specifications for. Nuclear Power Plants," October 1978,s and to Radiological. Assessment Branch Technical-H g
Position, Revision 1, November 1979.
Deviations are permitted from the required sampling schedule.if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic 1
o-l sampling equipment _and other legitimate reasons. 'If specimens are unobtainable due to sampling equipment' N
malfunction, every effort shall be made to complete corrective. action prior' to the end of the next. sampling;
}
period.
All deviations from the sampling schedule shall be documented in the' Annual Radiological' Environ -
mental Operating Report pursuant to Specification 6.9.1.6.
It is recognized that, at times, it may not be possible or practicable to continue to.o'otain samples of the media of choice lat the most desired location i
or time.
In these instances suitable alternative media and locations may be chosen for the particular~.
pathway in question and appropriate substitutions made within 30 days in the. Radiological Environmental'
}
}
Monitoring Program.
In lieu of a Licensee Event Report and pursuant'to Specification 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s)'for obtaining rp replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the' report a revised figure (s) and table for the ODCM reflecting _ the new location (s).
i w
i (2) One or more instruments, such as a pressurized. ion chamber, for measuring and recording dcse rate continuously may be used in place of, or in addition to, integrating dosimeters. 'For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be _one phcsphor; two or more phosphors in a.
I packet are considered as two or more dosimeters._ Film badges shall not be used_as dosimeters for= measuring; i
direct radiation.
The-forty stations is not an absolute number. 'The number of-direct radiation monitoring
[p stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will
~
l gg be over water so that the number of dosimeters may be reduced accordingly.
The fregency of analysis or-i g g.
readout for TLD systems will depend upon the characteristics of the specific system used and should be j
gg selected to obtain optimum dose information with minimal fading.
,E g (3) The purpose of this sample is to obtain backgrouad information.
If it is not' practical to establish control locations in accordance.with the distance and wind direction criteria, other sites that provide y
i os valid background data may be substituted.
22 hk j
33 l
. i
]
TABLE 3.12-1 (Continued) he E!
TABLE NOTATION G
m i
g (4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity. 24 h'ours or more after sampling to allow for radon and' thoron daughter decay.
If gross beta activity in air particulate samples is greater than ten. times the yearly mean of control samples, gamma isotopic analysis shall be performed to on the individual samples.
w (5) Gamma isotopic analysis means the identificatinn and duantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
N (6) The " upstream sample" shall be taken at a distance ;beyond significant influence of the discharge.
The "downstfdam" sample shall-be taken in an area beyond but near the mixing-zone.
" Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.
Salt water shall be sampled only when the receiving-water is utilized.for recreational activities.
s (7) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional. to the quantity
[
of flowing liquid and in which the method of sampling employed results in a specimen that.is representative of the liquid flow.
In this progra:n composite sample aliquots shall be collected at time intervals that are N
c'o very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
(8) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
(9) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
(10) If harvest occurs more than once a year, sampling shall be performed during each discrete' harvest.
If harvest occurs continuously, sampling shall be monthly.
Attention shall be oaid to including samples of tuborous and root food products.
m
RADIOLOGICAL' ENVIRONMENTAL MONITORING
'3/4.12.2 LAND USE CENSUS c
- LIMITING' CONDITION FOR OPERATION
' i L3.12.2~ A land use census shall be conducted and shall identify within a-
~
' distance of 8 km (5 miles)"the location in each.of.the 16. meteorological sectors ~ of the nearest. milk animal, the nearest residence.and the nearest
. garden
- of greater than 50 m.(500 ftz) producing broad-leaf vegetation ~
(For 2
- elevated releases ~as defined in Regulatory Guide 1.111, Revision 1, July 1977, i
the11and use census shall also identify witnin a distance of 5 km (3 miles) the locations in-each of the 16 meteorological sectors of~all r. ilk animals and
'all gardens of greater than 50 m2 prodacing broad leaf vegetation;)-
APPLICABILITY:
At all' times; ACTION:
l a.
With a land use census ' identifying a : location (s)'which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee
- Lvent Report, identify the new location (s) in the next Semiannual Radioactive Effluent Release' Report, pursuant.to Specification 6.9.1.7.
b.
With a land use census identifying a location (s) which yields a calculated dose.or doze comrr.itment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new s
- location to the Radiological Environmental Monitoring Program.
The samp1ing location (s), excluding the control station location,~'having the lowest calculated dose or dose commitment (via the same exposure pathway) may be' deleted from this monitoring program after October
. 31 of the year in which this land use census was conducted. 'In lieu =
of a Licensee Event Report and pursuant to Specification 6.9.1.7, the next Semiannual Radioactive Effluent Release' Report shall con -
E tain the following information:
(1) the new location (s),-(2) revised
- figure (s) and table (s) for the OCCM reflecting the' new location (c),-
- and (3) if samples cannot be obtair.ed, an explanation of why samples-7 are not obtainable (substii.ote representative' locations shall l
be~ included, if possible).
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed'at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.
Specifications for broad leaf vegetation sampling in Table 3.12-1.4c shall be~
followed, including analysis of control samples.
e Amendment No. 1 (Unit 2)
McGUIRE - UNITS 1 and:2 3/4 12-13 Amendment No. 20 (Unit 1) d
. = =
y-,
e-+4gy g 99-or y-e+srg-g
->@,u, e
9-m,9-u-w vg3go qyei--+-+w, g wnsw,ygi,,e,--,,,,yy,,,,y,,,p.
wg y
w.
--eww w.g-gwyy wwGur g w
wayur*Tr*Ntw W,r '1W wv twwwv W'f WFNw8Nur-BT@T*-T 1r $F-f 18*t'w-w-*
d-RADIOLOGICAL ENVIRONMENTAL MONITORING
~
- SURVEILLANCE REQUIREMENTS -
.4.12.2 The land.use census shall be conducted during the growing season at leastionce per 12 months using that information which will-provide the best results, suchfas by a door-to-door survey, aerial survey, or by consulting _
local agriculture authorities.
The results of the land use ' ensus shall be c
included in the Annual Radiological Environmental. Operating Report pursuant to.
Specification 6.9.1.6.
4 i.-
d i
i i
McGUIRE - UNITS 1 and 2 3/4 12-14
[
TABLE 3.8-la (Continued)
UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES I
E TRIP SETPOINT OR
- RESPONSE, Z
CONT. RATING TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED
{
2.
600.VAC-MCC (Continued) 1EMXA-2 28 Primary Bkr 20 45 0 60A N2.to Prt Cont Isol Inside Backup Fuse 20 N.A.
V1v INC54A 1EMXA-2 2C Primary Bkr 20 45 @ 60A RCP Mtg Brg Oil Fill Isol s
g P3ckup Fuse 20 N.A.
V1v=INC196A b
co IS1XA-2 3A E
Primary Bkr 30 45 0 90A Accumulator IA Disch Isol Backup Fuse 30 N.A.
Viv 1NI54A o
1EMXA-2 3B Primary Bkr 30 45 @ 90A Accumulator 1C Disch Isol Backup Fuse 30 N.A.
Viv 1NI76A 2-1EMXA-2 3C.
SE Primary 8kr 20 45 0 60A Test Hdr'Inside Cont Isol
((
Backup Fuse 20 N.A.
Viv 1NI95A mu E$
1EMXA-2 4A e"
Primary Bkr 20 45 @ 60A UHI Check Viv Test Line Isol PE Backup Fuse 20 N.A.
Viv 1NI266A E$w 22 hk C3 i
k
" ABLE 3.8-la (Continued)
R E
UNIT 1 CONTAINMENT PFNETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEVICES m
TRIP SETPOINT OR
RESPONSE
l CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERE 1)
(SECONDS)
SYSTEM POWERED
~
2.
600 VAC-MCC (Continued) j o.
N 1EMXA-2 4B UHI Check Viv Test Line Isol:
Primary Bkr 20 45 @ 60A 1
Backup Fuse 20 N.A.
Viv 1NI267A 1EMXA-2 4C Accum 1A Vent to INC34 for-Primary Bkr 20 45 @,60A Backup Fuse _
20 N.A.
Bikout Viv 1NI430A w
30 1EMXA-5 1B 4
Primary Bkr 20 45 C 60A Pzr Steam Sample Line Inside o3 Backup Fuse 20 N.A.
C-ant Isol Viv 1NM3A N
9 1EMXA-5 2B Primary Bkr 20 45 @ 60A Per Steam Sample Line Inside-Backup Fuse 20 N.A.
Cont Isol Viv INM6A 1EMXA-5 3B Primary Skr 20 45 0 60A NC Hotleg 1A Sample Line. Cont Backup Fuse 20 N.A.
Isol Viv 1NM22A 1EMXA-5 20 Primary Okr 20 45 @ 60A NC Hotleg 10 Sample Line Cont Backup Fuse 20
.N.A.
Isol Viv 1NM25A 1EMXA-2 7A SG 1A Upper Shell Sample Cont Primary Bkr 20 45 @ 60A Backup Fuse 20 N.A.
Isol Viv 1NM187A.
c.
.n 4
?f TABLE 3.8-la (Continued)
O gj UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINT OR RESPONSE.
Z CONT. RATING TIME
}
DEVICE NUMBER & LOCATION (AMFERES)
(SECONDS)
SYSTEMS POWERED 2.
600 VAC-!;CC (Continued) i g
IEMXA-2 7B Primary Bkr 20 45 @ 60A SG 1A Blowdown Line Sample Backup, Fuse 20 ti. A.
Cont Isol Viv.1NM190A 1EMXA-2 7C Primary Bkr 20 45 @ 60A SG IC Upper " hell Sample Backup Fus?
20 N. A.
- Cont Isol'Viv 1NM2071, w
3 1EMXA-2 8A e3 Primary Bkr 20 45 0 6GA SG IC Blowdown Line Sample g
Backup Fuse 20 N.A.
Cont Isol Viv INM210A 1EMXA-4 1B Primary Bkr 20 45 @ SOA NC Pump. Seal Return Cont Bacxup Fuse 20 N.A.
Cont Viv INV94AC 1EMXA-3 3A Primary Bkr 20 45 0 60A H2 Purge-Exhaust Cont Vessel Backup Fuse 20 N A.
Isol Viv IVESA 1EMXA-3 3B Primary Bkr 20 45 @ 60A Cont. H2 Purge Blower Inlet Backup Fuse 20 N.A.
Viv IVE8A' lEMXA-3 3C Primary Bkr 20 45 @ 60A H2 Purge' Inlet Cont Vessel 8ackup Fuse 20 N.A.
Isol Viv IVE10A 1EMXA-4 2C Primary Bkr 20
.45 @ 60A.
Standby Makeup Pump Inlet Backup Fuse 20 N. A.
Isol Valve INV842AC
m 1
1
. [
TABLE 3.6-la (Continued)'
- C
. k
. UNIT 21 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TRIP SETPOINT OR-
RESPONSE
g CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERES)
(SECONOS)
SYSTEM POWERED j
g k
2.
600 VAC-MCC (Continued) 1EMXA-3 4A Primary Bkr 20 45 0 60A H2 Skimmer Fan 2A Suction I
Backup Fuse 20 N.A.
fisal V1y IVX1A
.1EMXA-3 SB Primary Bkr 20 45 0 60A RCDT Pung Disch Cont Isol a
l Backup Fuse 20 N.A.
V1v 1WL2A~
i m
1EMXA-3 SC j
h Primary Bkr
- 20 45 0 60A RCDT Vent Cont Isol Viv Backup Fuse 20 N.A.
1WL39A i
1EMXA-3 6A Primary Bkr 20 45 @ 60A RB Sump Pump Disch Cont Isol Backup Fuse 20 N.A.
.Viv 1WL64A i
IEMXA-3 6B l[
Primary Bkr 20 45 @ 60A Cont Vent Unit Condensate gg Backup Fuse 20 N. A.-
Cont Isol Viv.1WL321A ea 2
5E 1EMXB-4 1B z ".
Primary Bkr 20 45 @ 60A NC Pump IS Thermal Barrier
,o Backup Fuse 20 N.A.
Outlet Auto Isol Viv 1KC3648 m "
1EMXB-4 1C jy Primary Bkr 20 45 @ 60A NC Pump ID Thermal Barrier Backup Fuse 20 N.A.
Auto Isol'Viv-1KC4138-i UO 4
e
TABLE 3.8-la (Continued)
Cy UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINI OR
RESPONSE
l Z
CONT. RATING TIME
[
DEVICE NUMBER & LOCATION
'(AMPERES)
(SECONDS)
SYSTEM POWERED
[
2.
600 VAC-MCC (Continued) 1EMXC-4C Primary Bkr 90 110 9 2 0A Containment Air Return Fan Backup Fuse 90 N.A.
Primary Bkr 90 110 0 270A Hydrogen Recombiner Backup Fuse 90
.N.A.
No. 1A m
1EMXC-SA E
Primary Bkr 40 45 @ 120A.
Containment Pipe Tunnel Backup Fuse 40 N.A.
Booster Fan CPT-BF-1A 1EMXC-6B Primary Bkr 30 45 @ 90A Upper Containment Air Backup Fuse 30 N.A.
Handling Unit 1A IEMXC-6C 2F Primary Bkr 30 45 @ 90A Upper Contair, ment Air Hdig j
((
Backup Fuse 30 N.A.
Unit 1C i
aa 5E 1EMXC-60
=
Primary Bkr 90 110 @ 270A Hydrogen Skimmer Fan
.E Backup Fuse 90 N.A.
No. 1 m *
'1EMXC-7C EE Primary Bkr 30 45 0 90A Upper Corit Return Air Fan yy Backup Fuse 30 N.A.
No. 1C UU
~ '
4
h-TABLE 3.B-la (Continued) c k
UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERC3JRRENT PROTECTIVE DEVICES I
TRIP SETPOINT OR
RESPONSE
g CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERES (SECONDS)
SYSTEM POWERED g
k 2.
600 VAC-MCC (Continued) 1EMXC-70 Primary Bkr 20 45 @ 60A Pzr Pwr Oper Relief Backup Fuse 20 N.A.
Isol Viv 1NC33A 1EMXC-8C Primary Bkr 20 45 @ 60A Incore Instrumentation Ra~
g Backup Fuse 20 N.A.
Air Hdig Unit 1A m
1EMXC-8D h
Primary Bkr 20 45 @ 60A Upper Containment Return Backup Fuse 20 N.A.
Air Fan No. lA 1EMXA-4 3C Primary Bkr 30 45 G 90A NC Loop IC Discharge to ND Backup Fuse 30 N.A.
System Cont Isol Viv 1ND 2AC 1EMXD-1A l[
Primary Bkr 200 259 @ 600A Lower Containment Cooling pg Backup Fuse 200 N.A.
Unit No. IB co a 5E 1EMXD-2A
=[
Primary Bkr 200 250 @ 600A Lower Containment Cooling F
Backup Fuse 200 ti. A.
Unit No. 10 m *
-1EMX0-3B Primary Bkr 40 45.0 120A-Containment Pipe Tunnel pp Backup Fuse 40 N.A.
Booster Fan CPT-BF-1B C3
~
~
R.
TABLE 3.8-la (Continued)
S g
UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINT OR
RESPONSE
Z CONT. RATING
. TIME
]
DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED 2.
600 VAC-MCC (Continued) m.
3 N'
IEMXO-3C
~110 @ 300A Control Rod Drive Vent' Fan:
Primary Bkr 100 Backup Fuse 100 N.A.
-No. IB 1EMXD Primary Bkr 100 110 0 300A Control Rod Drive Vent Fan Backup Fuse 100 N. A.
- No. 1D u,k 1EMXD-4C es Primary Bkr 90 110 @ 270A Containment Air Return Fan i
Backup Fuse 90 N.A.
No. 18 Fan CPT-BF-1A o
1EMXD-40 i
Primary Bkr 90 110 @ 270A Hydrogen Recombiner No.-1B Backup Fuse 90 N.A.
1EMXD-6C P*imary Bkr 30 45 0 90A Upper Containment Air Hdig Unit Backup Fuse 30 N.A.
No. 1B IEMXD-60 Primary Okr 30 45 @ 90A Upper Containment Air Hdig Unit.
. Backup Fuse 30 N.A.
No. 10 4
1EMXD-6E Primary ~Bkr 90 110 @ 270A Hydrogen Skimmer Fan No. IB 4
Backup Fuse 90-N.A.
m
.tu
~;.
R TABLE 3.8-la (Continued)
Ejj UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT' PROTECTIVE DEVICES _
E TRIP SETPOINT OR
RESPONSE
Z CONT. RATING TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED' I
E
?.
600 VAC-MCC (Continued) a 1MXM F2E Prima,ry Bkr 20
-45 @-60A Ice Cond AHU 1A4LBlower_A Backup Fuse 20 N.A.
1MXM F3A Primary Bkr 20 45 @'60A.
Ice Cond AHU 1A5 Blower A g,
Backup Fuse 20 N.A.
s o3 IMXM F3B l
J, Primary Bkr 20 45 @ 60A Ice Cond AHU 1A6. Blower A Backup Fuse.
20 N.A.
4 IMXM F3C Primary Bkr 20 45 @ 60A Incore Inst Room Sump Pump Backup Fuse 20 N. A.
1MXM F3D Primary Bkr 100 110 @ 300A Upper Cont Welding Recpt Backup Fuse 100 N.A.
IMXM F4A Primary Bkr 20 45 0 60A Ice Cond AHU 1A7 Blower A Backup Fuse 20 N.A.
1MXM F48 Primary Bkr 20 45 @ 60A Ice Cond AHU 1A8 Glower A Backup Fuse 20 N.A.
- i l
l I'
[
TABLE 3.8-la (Continued)
C UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINT OR RESPONSE-Z CONT. RATING TIME 4
[
DEVICE flUMBER & LOCATION (AMPERES)
'(SECONOS)
SYSTEM POWERED
(
2.
600 VAC-MCC (Continued) j 1MXM F4D Primary Bkr 100 110 @ 300A Welding Feeder Backup Fuse 100
'N.A.
1MXM FSC i
Primary Bkr 50 110 @ 150A Ice Cond Floor Cooling Backup Fuse 50 N.A.
-Defrost Heater 1A co 1MXM F6C O
Primary Bkr 60 110 9 180A Reactor Coolant Orain Tank Backup Fuse 60 N.A.
Pump 1A 1MXM F7A Primary Bkr 20 45 0 60A Ice Cond AHU 1A9 Blower A Backup Fuse 20 N.A.
1MXM F78 5E Frimary Bkr 20 45 @ 60A Ice.Cond AHU 1A10 Elower A E{
Backup Fuse 20
.N.A.
1 ma l
AE IMXM F7C 2"
Primary Bkr 30 45 0 90A Lower Cont Aux Charcoal Filter f
Backup Fuse 30 N.A.
Fan 1A j
4 m
1MXM F8A 22 Primary Bkr 20 45 @ 60A-Ice Cond.AHU 1A11 Blower A yy Backup Fuse 20 N.A.
00 4
s
,s
,)-
I" TABLE 3.8-la (Continued)~
Es UNIT 1 CONTAINMENT-PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES m
I E
TRIP SETPOINT OR
RESPONSE
I Z
CONT. RATING TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
TSECON05)
SYSTEM' POWERED-ll 2.
600 VAC-MCC (Continued) i
^'
1MXM R4F Primary Bkr 30 45 @ 90A
.RCP 10 Oil Lift. Pump-Backup Fuse 30 N.A.
4 i
1MXM R58 Primary Bkr 20 45 @ 60A Ice Cond AHU 189: Blower A' l
g2 Backup Fuse 20 N.A.
.u os 1MXM RSC J3 Primary Bkr 20 45 @ 60A Ice Cond AHU:1810 Blower A-Backup Fuse 20 N.A.
4 IMXM R5D Primary Bkr 175 200 @ 525A Ice Cand Equip Pwr Pnibd IB Backup Fuse 175 N.A.
2 1MXM R6A Primary Bkr 20 45 @ 60A.
-Rod Cntri. Cluster Change Backup Fuse 20 N.A.
Fixture. Hoist Drive IMXM R68 Primary Bkr 20 45 @ 60A Ice Cond AHU 1B11' Blower A I
Backup Fuse 20 N.A.
1MXM R7A Primary Bkr
.20 45 @ 60A Stud Tensioner Hoirt Backup Fuse 20 N.A.
IMXM R60 Primary Bkr 150' 110 @ 450A_
175 Ten Polar Crane Backup Fuse
.150 N.A.
i i
TABLE 3.8-la.(Continued) h UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES ~
e TRIP SETPOINT OR
RESPONSE
g Cont. Rating Time DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED g
k 2.
600 VAC-MCC (Cuntinued) 1MXM R78 Primary Bkr 20 45 9 60A Incore Inst Drive 1A Backup Fuse 20 N.A.
1MXM R70 Primary Bkr 20 45 9 60A
' Ice Cond AHU 1812 g
Backup Fuse 20 N.A.
.e.
co IMXM R7E h
Primary Bkr 20 45 @ 60A Ice Cond AHU 1813 Blower A Backup Fuse 20 N.A.
1MXM R8A Primary Bkr 20 45 0 60A Incore Inst Drive IB Backup Fuse 20 N.A.
IMXM R8B l[
Primary Bkr 20 45 0 60A Incore Inst Drive IC gg Backup Fuse 20 N.A.
ea E$
IMXM R8D z[
Primary Bkr 20 45 0 60A
' Ice Cond AHU 1814 Blower A
,o Backup Fuse 20 N.A.
m "
1MXM R8E Primary Bkr 20 45 9 60A Ice Cond AHU 1815 Blower A p ;-
Backup Fuse 20 N.A.
C3
4 4
[
TABLE 3.8-la (Contir.neo)
C h
UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINT OR RESPONS2 Z
CONT. RATING TIME-DEVICE NUMBER & LOCATION (AMPERES)~
(SECONDS)
SYSTEM POWERED g
[
2.
600 VAC-MCC (Continued) 1MXN-R3A Primary Bkr 20 45 @ 60A Ice Cond AHU 1B3 Blower B Backup Fuse 20 N.A.
1MXN-R3B Primary Bkr 20 45 @ 60A Ice Cond AHU 1B4 Blower B g
Backup Fuse 20 N.A.
s co IMXN-R3C A
Primary Bkr 20 45 @ 60A Ice Cond AHU 1B5 Blower B Backup Fuse 20 N.A.
1 1MXN-R3D Primary Bkr 30 45 @ 90A RCP 1C 011 Lift Pump No. 2 Backup Fuse 30 N.A.
$E Primary Bkr 50 110 0 150A
~
Ice Cond Bridge Crane
({
Backup Fuse 50 N.A.
ma 5$
IMXN-R4B 2[
Primary Bkr 30 45 @ 90A RB Equip Hatch Hoist No. 1 F
Backup Fuse 30 N.A.
i
- ro IMXN-R4D GE Primary Bkr 20 45 @ 60A Ice Cond AHU 186 Blower B
%y Backup Fuse 20 N.A.
d$
?F TABLE 3.8-la (Continued)
E-UNIT 1 CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEVICES m
i E
TRIP SETPOINT OR
RESPONSE
Q CONT. RATING _
TIME DEVICE' NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWEREO
[
2.
600 VAC-MCC (Continued)
E IMXN-R4E Primary Bkr 30 45: @ 90A RCP 10 Oil Lift Pump No. 2 h)
Backup Fuse 30 N.'A.
' i, 1MXN-RSO Primary Bkr 175 200 0 525A Ice Cond Equip Pwr ?nibd 1A Backup Fuse 175 N.A.
1MXN-R6A 45 @ 60A Ice Cond AHU 187 Blower 8-Primary Bkr 20 as 4
Backup Fuse 20 N.A.
cn 1MXN-R68 Primary Bkr 20 45.@ 60A ice Cond AHU 188 Blower B 20 N.A.
q Backup Fuse 1MXN-R6C Primary Bkr 20 45 @ 60A Ice Cond AHU 189 Blower B Backup Fuse 20 N.A.
1MXN-R60 Primary Bkr 100 110 @ 300A Welding Fdr Backup Fuse 100 N.A.
IMXN-R7A Primary Bkr 20 45 @ SOA
' Ice Cond AHU 1810 Blower B Backup Fuse 20 N.A.
1MXN-RSA Primary Bkr 20 45 @ 60A Control Room Area Duct Backup Fuse
-20 N.A.
Heater CRA-H
t 4
f TABLE 3.8-la (Continued)
C l
h UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE' DEVICES'
. TRIP SETPOINT OR
RESPONSE
g CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
-SYSTEM POWERED g
k 2.
600 VAC-MCC (Continued) l MXN-R5B Primary Bkr 20 45 @ 60A Control Room Area Duct.
i Backup Fuse
.20 N.A.
Heater i
s i
SMXG-F3G j
Primary Bkr 20 45 6 60A Staney Makeup Pump'to l
q Backup Fuse 20 N.A.
Cont Sump Isol Viv INV1012C t
L co SMXG-F4G l
h Primary Bkr 20 45 ft 60A Standby Makeup Pump to NC Backup Fuse 20 N.A.
Pump Seals'Isol Viv.1NV1013C-1MXNA-3C i
Primary Bkr 20 45 @ 60A
.NC Pump Motor Drain Tank Backup Fuse 20 N.A.
Pump No. 1 IMXNA-3fi l[
Primary Bkr 20 45 @ 60A Ice Cond Equip Access Door 1B
{
g.g Backur Fuse 20 N.A.
<a n 5$
SMXC-70 z"
Primary Bkr 15 45 @ 45A Unit 1 Personnel Lock
,o Backup Fuse 15 N.A.
$w EE SMXA-F4A hh Primary Bkr-15 45 9.45A Unit 1 En.ergency Personnel Lock' Backup Fuse 15 N.A.
gy vv i
i
R TABLE 3.8-la (Continued)
S UNIT 1 CONTAINM5NT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINT OR
RESPONSE
CONT. RATING TIME.
vs
. DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED w
8 3.
600 VAC-Press Htr Pwr o-Pnis N
Backup Press Hte Pwr i
Pnl 1A-1A Pressurizer Heaters.1, 2,1& 22 Primary Bkr 90 110 @ 270A Backup Fuse 90 N.A.
Backup Press Htr Pwr 1
u,);
Pn1 1A-18 Primary Bkr 90 110 @ 270A Pressurizer Heaters 5, 6, & 27 e3 J,
Backup Fuse 90 N.A.
o Backup Press Htr Pwr Pnl 1A-1C Primary Bkr 90 110 @ 270A Pressurizer Heaters 9, 10, Backup Fuse
.90 N.A.
& 32 Backup Press Htr Pwr Pnl 1A-2C Primary Bkr 90 110 @ 270A Pressurizer Heaters 11, 12, Backup Fuse 90 N.A.
& 35 Backup Press Htr Pwr Pnl 1A-2D Primary Okr 90 110 3 270A Pressurizer Heaters 13, 14, Backup Fuse 90 N.A.
& 37 Backup Press Htr Pwr Pn1 1A-2E Primary Bkr 90 110 @ 270A.
Pressurizer Heaters 17, 18, Backup Fuse 90 N.A.
& 42
~,
4
.).
[
' TABLE 3.8-la (Continued)
C j{
UNIT 1 CONTAINMENT' PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINT OR
RESPONSE
Z CONT. RATING
. TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
(SECONOS)
SYSTEM POWERED 3.
600 VAC-Press Htr Pwr 5
[
Pnis (Continued)
Backup Press Htr Pwr Pnl 10-20' Primary Bkr 90 110 @ 270A Pressurizer Heaters 38,.07, Backup Fuse 90 N.' A.
& 68 w
Backup Press Htr Pwr
)?
Pn1 10-2E o>
Primary Bkr 90 110 @ 270A Pressurizer Heaters 43, 73, J,
Backup Fuse
-90 N.A.
1& 74 un 4.
120 VAC-Panelboards 1EKVD-12 Primary Bkr 20 40 @ 60A Rad Mon Sys Sample Solenoid Backup Fuse 6
N.A.
Vivs IMISV 5581 & 5583 KRA-22 Primary Bkr 30 45 @ 90A Rad Mans 1 EMF 9 &'1 EMF 16 Backup Fuse 1
N.A.
XXA-13 Primary Bkr 20 40 @ 60A
. Rad Mon Sys Sample Solenoid Backup Fuse 4.
N.A.
Vivs IMISV 5584, 5585, & 5586:
- Primary Bkr 30 45 0.90A RCP 18 Space Htr Backup Fuse 30 N.A.
i-
N
[
TABLE '3.8-la _ (Continued) c UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES B
E~
TRIP SETPOINT OR
RESPONSE
l Z
CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED g
l
[
4.
120 VAC-Pane 1 boards (Continued) 1KM-2 Primary Bkr 30 45 @ 90A RCP 1C Space Htr i
Backup Fuse 30 N.A.
i 1KM-28 j
Primary Bkr 20 36 @ 60A Cont Spray Sys Rh Trans j
Backup Fuse 20 N.A.
-INSMT S400 l!
cn 1KM-30 E
Primary Bkr 20 36 @ 60A Cont Spray Sys Rh Trans Backup Fuse 20
'N.A.
INSMT 5410 1KN-1 3'
Primary Bkr 30 45 @ 90A-RCP 1B Space Heater Backup Fuse 30 N.A.
I 1KN-2 5I Primary Bkr 30 45 @ 90A RCP ID Space Heater i
y{
Backup Fuse 30 N.A.
mn 5@
1KN-25 z[
Primary Bkr 20 36 @ 60A' Incore Inst Dehum. #1 u
?E Backup Fuse 20 N.A.
~
- 1KN-27 EE Primary Bkr 20 36 0 60A Fuel Handling Control
{.h Backup Fuse 20 N.A.
Console
-m 1
vv l
l f
TABLE 3.8-la (Continued) 5 g
UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES k
TRIP SETPOINT OR
RESPONSE
g CONT. RATING
. TIME DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED g
k 4.
120 VAC-Panelboards (Continued) 1KN-29 Primary Bkr 20 36 @ 60A Incore. Inst Dehus. #2 Backup Fuse 20 N.A.
i 5.
250 VDC-Lighting i
y RB Deadlight Pnibd i
IDLD #1 cp Primary Bkr 20
_40 @ 60A Ltg Pnl Nos. ILR1 & ILR2 g
9ackup Fuse 20 N.A.
l RB Deadlight Pnlbd 1DLD #3 7
Primary Bkr 20 40 0 60A Ltg Pnl Nos. ILR4,'1LRS, &
Backup Fuse 20 N.A.
1LR6 1
i y,
RB Deadlight Pnibd ma 1DLD #4 l
h(
Primary Bkr 20 40 @ 60A Ltg Pnl.Nos. 1LR7, ILR8, a
gg Backup Fuse 20 N.A.
& 1LR9 eo q
g" RB Deadlight Pnibd,
4
,o 1DLD #6 gg Primary Bkr 20.
40 0 60A Ltg Pnl Nos. ILR12 j
Backup Fuse 20 N.A.
gg
??
C3 i
i 1
?F TABLE 3.8-la (Continued)
E UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES l
g Ei TRIP SETPOINT OR
RESPONSE
Z CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED:
s s
5.
250 VDC-Lighting j
i (Continued)
N RB Deadlight Pnibd 1DLD #7..
Primary Bkr 20 40 @ 60A Ltg Pnl.No. ILR16 Backup Fuse 20 N.A.
RB Deadlight Pnibd w
1 1DLD #9 Primary Bkr 20 40 @ 60A Ltg Pnl Nos.'ILR18 & ILR17 a3 J,
Backup Fuse 20 N.A.
co j
~
i i
.^.
- y 7 s
4 e
{
r e
TABLE 3.8-lb 5g UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.
i c
5 TRIP-SETPOINT OR
RESPONSE
d CONT RATING TIME l
DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED g
k 1.
6900 VAC-Swgr Primary Bk'r-RCP2A 5.0 15.4 @ 25A
' Reactor Coolant Pump'2A N
Backup Brk-2TA-5 5.0 16.5 @ 20A Primary Bkr-RCP2B 5.0 15.4 @ 25A Reactor Coolant Pump 28 i
Backup Brk-2TB-5 5.0 16.5 @.20A Primary Bkr-RCP2C 5.0 15.4 @ 25A Reactor Coolant' Pump 2C w)
Backup Brk-2TC-5 5.0 16.5 @ 20A Primary Bkr-RCP2D 5.0 15.4 @ 25A Reactor Coolant Pump 20
~
i e
Backup Brk-2TD-5 5.0 16.5 @ 20A 2.
600 VAC-MCC l
2EMXA-2 10 Primary Bkr 20 45 @ 60A NC Pump 2C Thermal Barrier i
Backup Fuse 20 N.A.
Outlet Auto Isol Viv 2KC345A 32Y gg 2EMXA-2 1E gg Primary Bkr 20 45 @ 60A
, NC Pump 2A Thermal Barrier gg Backup Fuse 20
.N.A.
Outlet Auto Isol Viv 2KC394A 2"
Fg 2EMXA-2 2A Primary Bkr 20 45 @ 60A Cont Air Return Fan 2A Damper
.y l
oH Backup Fuse 20 N.A.
2RAF-D-2 EE S. S.
r+ r
i
[
TABLE 3.8-1b.(Continued)
UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
TRIP SETPOINT OR
RESPONSE
U CONT. RATING TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
(SECONOS)
SYSTEM POWERED
(
2.
600 VAC-MCC (Continued) 2EMXA-2 2B Primary Bkr 20 45 @ 60A N2 to Prt Cont Isol Inside i
Backup Fuse 20 N.A.
Viv 2NC54A l
2EMXA-2 2C Primary Bkr 20 45 @ 60A RCP Mtg Brg 011 Fill Isol Backup Fuse 20 N.A.
Viv 2NC196A cn 2EMXA-2 3A l
A Primary Bkr 30 45 @ 90A Accumulator 2A Disch Isol i
Backup Fuse 30 N.A.
Viv 2NI54A 1
2EMXA-2 3B j
Primary Bkr 30 45 @ 90A
. Accumulator 2C Disch Isol Backup Fuse 30 N.A.
Viv 2NI76A.
i 2EMXA-2 3C l
Il E Primary Bkr 20 45 0 60A Test Hdr Inside Cont Isol y{
Backup Fuse 20 N.A.
Viv 2NI95A i
r ea S$
2EMXA-2 4A z"
Primary Bkr 20 45 0 60A UHI Check V1v Test Line Isol
-[
Backup Fuse 20 N.A.
Viv 2NI266A Ew i
22 S. 3.
r c+
,r.
{
TABLE 3.8-1b (Continued)
C y
UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.
1 I
E TRIP SETPOINT OR REPONSE Cl CONT. RATING TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED 5
2.
600 VAC-MCC (Continued) a 2EMXB-4 SA Primary Bkr 20 45 @ 60A NI Accum 28 Sample Line Backup Fuse 20 N.A.
Inside Cont Isol Viv 2NM758-2EMXB-4 5B Primary Skr 20 45 @'60A NI Accum 2C Sample Line Backup Fuse 20 N.A.
Inside Cont Isol Viv 2NM78B wh 2EMXB-4 SC as di Primary Bkr 20 45 @ 60A Accum 2B Vent to 2NC32 Backup Fuse 20 N.A.
for Bikout Viv 2NI431B 2EMXB-4 6A Primary 8kr 20 45 @ 60A NI Accum D2 Sample Line Backup Fuse 20 N.A.
Inside Cont Isol Vlv 2NM818 2EMXB-4 6B Primary Bkr 20 45 @ 60A
.SG 2B Upper Shell Sample Backup Fuse 20 N.A.
Cont Isol Viv 2NM1978 2EMXB-4 6C Primary Bkr 20 45 @ 60A SG 2B Blowdown Line Sample Backup Fuse 20 N.A.
Cont Isol Viv 2NM2008 2EMXB-4 7B Primary Bkr 20 45 @ 60A SG 20 Upper Shell Sample Backup Fuse 20 N.A.
Cont Isol Viv 2NM2178
k TABLE 3.8-1b (Continued) 5g UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES e
C5 TRIP SETPOINT OR
RESPONSE
y CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED g
k 2.
600 VAC-MCC (Continued) 2EMXB-4 7C Primary Bkr 20 45 0 60A SG 2D Blowdown Line Sample Backup Fuse 20 N.A.
Cont Isol Viv 2NM2208 2EMXB-5 1A Primary Bkr 20 45 @ 60A H2 Purge Exhaust Cont Vessel Backup Fuse 20 N.A.
Isol Vlv 2VE6B m
2EMXB-5 1C h
Primary Bkr 20 45 @ 60A H2 Skimmer Fan 2B Suction Backup Fuse 20 N.A.
Isol Viv 2VX2B 2EMXC-1A Primary Bkr 200 250 @ 600A Lower Containment Cooling Backup Fuse 200 N.A.
Unit No. 2A 2EMXC-2A l[
Primary Bkr 200 250 0 600A Lower Containment Cooling g.g Backup Fuse 200 N.A.
Unit-No. 2C ea 5$
2EMXC-3C g ",.
Primary Bkr 100 110 0 300A Control Rod Drive 'lent Fan F
Backup Fuse 100 N.A.
No. 2A m "
2EMXC-3D jy Primary Bkr 100 110 0 300A Control Rod Drive Vent Fan p;
Backup Fuse 100 N.A.
No. 2C CD
k taste 3.8-1b (Continued)
C k
UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE' DEVICES ~
E TRIP SETPOINT OR
RESPONSE
Z*
CONT. RATING TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED
{
2.
600 VAC-MCC (Continued) 2EMXC-4C Primary Bkr 90 110 @ 270A Containment Air Return' Fan Backup Fuse 90 N.A.
No. 2A 2EMXC-4D Primary Bkr 90 110 0 270A Hydrogen Recombiner y
Backup Fuse 90 N.A.
No. 2A
+
co 2EMXC-6A E
Primary Bkr 40 45 @ 120A Containment Pipe Tunnel Backup Fuse 40 N.A.
Booster Fan CPT-BF-2A 2EMXC-6B Primary Bkr 30 45 @ 90A Upper Containment Air Handling.
Backup Fuse 30 N.A.
Unit 2A 2EMXC-6C
<o E Primary Bkr 30 45 @ 90A Upper Containment Air Hdig h{
Backup Fuse 30 N.A.
Unit 2C No. 2C co a 5$
=[
Primary Bkr 90 110 0 270A Hydrogen Skimmer Fan
,o Backup Fuse 90 N.A.
m 2EMXC-7C EE Primary Bkr 20 45 0 60A.
. Upper Cont Return Air _ Fan I
hh Backup Fuse 20 N.A.
No. 2C 00 i
i,
I
[
TABLE 3.8-lb (Continued)
Cy UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PHOTECTIVE DEVICES E
TRIP SETPOINT OR
RESPONSE
Z CONT. RATING TIME DEVICE NUMBER & LOCATION (AMPERES (SECONDS)
SYSTEM POWERED g
(
2.
600 VAC-MCC (Continued) 2EMXC-70 Primary Bkr 20 45 @ 60A Pzr Pwr Oper Relief Backup Fuse 20 N.A.
Isol Viv 2NC33A 2EMXC-8C Primary Bkr 20 45 @ 60A Incore Instrumentation Rm Backup Fuse 20 N.A.
Air Hdig Unit 2A m
2EMXC-78 E
Primary Bkr 20 45 0 60A Upper Containment Return Backup Fuse 20 N.A.
. Air Fan No. 2A 2EMXA-4 3C Primary Bkr 30 45 0 90A NC Loop 2C Discharge to ND Backup Fuse 30 N.A.
System Cont Isol Viv 2ND 2AC l
g 2EMXD-4 mE Primary Bkr 200 250 @ 600A Lower Containment Cooling Unit-y{
Backup Fuse 200 N.A.
No. 28 ma 5E 2EMXD-2A Primary Bkr 200 250 0 600A Lower Containment Cooling Unit
=
.f Backup Fuse 200 N.A.
No. 20 m
2EMXD-3B 22 Primary Bkr 40 45 @ 120A Containment Pipe Tunnel Booster
'{.[-
Backup Fuse 40 N.A.
-Fan CPT-BF-28 CU O
[
TABLE 3.8-1b (Continued)
C UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TRIP SETPOINT OR
RESPONSE
-4 CONT. RATING TIME
[
DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED
(
I 2.
600 VAC-MCC (Continued) 2MXM F2B Primary Bkr 40 45 0120A Lighting Pnibd 2LR15 Backup Fuse 40 N.A.
2MXM F2D Primary Bkr 20 45 @ 60A Ice Cond AHU 2A1 Blower A y
Backup Fuse 20 N.A.
co 2MXM F2E O
Primary Bkr 20 45 @ 60A Ice Cond AHU 2A2 Blower A.
Backup Fuse 20 N.A.
2MXM F3A N
Primary Bkr 40 45 @ 120A Lighting Pnibd 2LR16 U
Backup Fuse 40 N.A.
2MXM F3B j
l[
Primary Bkr 40 45 @ 120A Lighting Pnibd 2LR17 g.g Backup Fuse 40 N.A.
s es a 5$
2MXM F3C
=[
Primary Bkr 25 45 @ 75A Reactor Bldg Equip Hdig 5 Ton Backup Fuse 25 N. A.
Jib Crane i.
o m
2MXM F3D EE Primary Bkr 20 45 @ 60A Ice Cond AHU 2A3 Blower A hh Backup Fuse 20 N.A.
O" I
1
t I
ng TABLE 3.8-1b (Continued) i UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TRIP SETPOINT OR
RESPONSE
g CONT. RATING TIME-DEVICE NUMBER & LOCATION (AMPERES)
(SECONDS)
SYSTEM POWERED g
k i
2.
600 VAC-MCC (Continued) 2MXM F3E Primary Bkr 20 45 0 60A Ice Cont. AHU 2A4 Blower A'-
Backup Fuse 20
_N.A.
2MXM F4A i
Primary Bkr 20 45 @ 60A Ice Cond ANU 2A5 Blower A R
Backup Fuse 20 N.A.
l m
2MXM F4B i
g Primary Bkr 20 45 9 60A Ice Cond AHU 2A6 Blower A 1
Backup Fuse 20 N.A.
1 i
2MXM F4C i
Primary Bkr 20 45 9 60A Incore Inst Room Sump Pump
~
I Backup Fuse
.20 N.A.
i 2MXM F4D i
l[
Primary Bkr 100 110 @ 300A Upper Cont Welding Recpt gg Backup Fuse 100 N.A.
ma 5E 2MXM FSA g[
Primary Bkr 20
.45 0 60A Ice Cond AHU 2A7 Blower A-
,o Backup Fuse 20 N.A.
2MXM FSB
((
Primary Bkr 20 45 9 60A
-Ice Cond AHU'2A8 Blower A I.
pp Backup Fuse 20 N.A.
i 1
-