ML20151C387
| ML20151C387 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/25/1988 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20151C371 | List: |
| References | |
| NUDOCS 8804120404 | |
| Download: ML20151C387 (7) | |
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RADIOLOGICAL TECHNICAL SPECIFICATIONS i
l TABLE OF CONTENTS Page No.
1.0 DEFINITIONS 1-5 LIMITING SAFETY SAFETY L1MITS SYSTEM SETTINGS 1.1 FUEL CLADDING INTEGRITY 2.1 6 - 22 1.2 REACTOR COOLANT SYSTEM INTEGRITY 2.2 23 - 26
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SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.1 REACTOR-PROTECTION SYSTEN 4.1 27 - 46 3.2 PROTECTIVE INSTRUMENTATION 4.2 47 - 92 A.
Primary Containment Isolation Functions 47 B.
Core and Containment Cooling Systems Initiation 47 and Control (CS, LPCI, HPCI, RCIC, ADS)
C.
Control Rod Block Actuation 47 D.
Radiation Monitoring Systems - Isolation and 48 Initiation Functions 1.
Steam Jet Air Ejector Of f-Gas System 48 2.
Reactor Building Isolation and Standby Gas 48 Treatment Initiation 3.
Liquid Radwaste Discharge Isolation 48 4
Main Control Room Ventilation 48 I
5., Mechanical Vacuum Pump Isolation 48 E.
Drywell Leak Detection 49 F.
Primary Containment Surveillance Information 49 f
Readouts G.
Recirculation Pump Trip 49
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Post-Accident Monitoring 49 I.
Alternate Shutdown Capability 49 j
5.3 REACTIVITY CONTROL 4.3 93 - 106
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A.
Reactivity Limitations A
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B.
94 C.
Scram Insertion Times C
97 D.
Reactivity Anomalies D
98 E.
Restrictions E
98 F.
Recirculation Pumps F
98 i
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98a 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 107 - 113 A.
Normal Operation A
107 1
3 B.
Operation with Inoperable Components B
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C.
Sodium Pentaborate Solution C
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s LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENTS 3.2 (cont'd.)
4.2 (cont'd.)
D.
Radiation Monitoring Systems -
D.
Radiation Monitoring Systems -
Isolation & Initiation Functions Isolation & Initiation Functions 1
Steam J
'ir Ejector Off-Gas System 1.
Steam Jet Air Ejector Off-Gas System a.
Operabi'.ity of the Steam Jet Instrumentation surveillance require-Air Ejector Of f-Gas System ments are given on Table 4.2.D.
monitor is defined in Table 3.21.A.2.
b.
The time delay setting for closure of the steam jet air ejector isolation valves shall not exceed 15 minutes.
c.
Other limiting conditions for operation arg given on Table 3.2.D and Specifications 3.21.A.2 and 3.21.C.6.
2.
Reactor Building Isolation anl 2.
Reactor Building Isolation and Standby Gas Treatment Initiation Standby Gas Treatment Initiation The limiting conditions for opera-Instrumentation surveillance require-tion are given on Table 3.2.0 and ments are given on Table 4.2.D.
Specification 3.21.A.2.
3 Liquid Radwaste Discharge 3.
Liquid Radwaste Discharge Isolation Isolation Instrumentation surveillance re-The li=; ting conditions for opera-quirements are given on Table tion are given on Table 3.2.D and 4.2.D.
Specification 3.21.B.
4.
Mait Control Room Ventilation 4.
Main Control Room Ventilation Isolation Isolation the limiting conditions for opera-The instrument surveillance require-tion ore given on Table 3.2.D and ments are given on Table 4.2.D.
the Section entitled "Additional Safety Related Plant Capabilitias."
5.
Mechanical Vacuum Pump Isolation 5.
Mechanical Vacuum Pump Isolation a.
The mechanical s -
um pump shall The instrument surveillance require-be capable of be.'. 6 automatically ments are given on Tables 4.1.1, 4.1.2, isolated and sac'4 red by a signal of and 4.2.D.
high radiation in the main steam line tunnel whenever the main steam isolation valves are open.
b.
If the limits of (3.2.D.5.a) are not met, the vacuum pump shall bn isolateo.
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LIMfTING CONDIT10N FOR OPERATION SURVEILLANCE REQUIREMENTS E.
Drywell Leak Detection E.
Drywell Leak Detection The limiting conditions of Instrumentation shall be calibrated operation for che instrumentation and checked as indicated in Table j
that monitors drywell leak 4.2.E.
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detection are given in Table l
3.2.E.
F.
Prima ry Containment h ;veillance F.
Primary Contai nent Surveillance Inf o rma tion Information The limiting conditions of Instrumentation shall be calibrated operation for the instrumentarion and checked as indicated in Table 4.2.F.
that provides surveillance information readouts are given in Table 3.2.F.
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G.
Recirculation Pump Trip G.
Recirculation Pump Trip 1
I The limiting conditions for Instrumentation shall be functionally operation for the instrumentation tested and calibrated as indicated on that trips the recirculation Table 4.2.G.
pumps as a means of limiting the consequences of a failure to scram during an anticipated transient are given in Table 3.2 G.
H.
Post-Accident Monitoring H.
Post-Accident Monitoring l
The limiting conditions for oper-Instrumentation shall be functionally I
ation for the instrumentation that tested and calibratad as indicated monitors post-accident' conditions on Table 4.2.H.
are given in Table 3.2.H.
I.
Alternete Shutdown capability I.
Alternate Shutdown Capability 1.
The alternate shutdown instruments 1.
Each monitorfaa instrumentatien listed in Table 3.2.I-1 and controls channel of I:514 3.2.I-1 shall be listed in Trble 3.2.1-2 shall be demonstrated operable by performing operable duting reactor power operations the Channel Check and Channel and when the reactor coolant temperature Calibration at the frequencies shown is above 212*F.
on Table 4.2.I.
2.
With less than the minimum equipment 2.
Each isolation switch, power supply, specified in Table 3.2.I-1 and and control circuit for tha 3.2.1-2 operable, restore the components listed in Table 3.2.I-2 inoperable equipment to operable status shall be demonstrated operable at within 30 days, or notif:' the NRC and least oncs per cycle by operating provide plans to restore alternate each actuated component from the shutdown capability.
Alrcrnate Shutdown Panels. -
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Table 3.2.I-1 l
Alternate Shutdown Instruments Readout Minimum Instrument Location Channels HPCI Turbine Steam Inlet Pressure (Reactor Pressure)
HPCI-ASD Panel 1
HPCI Pu=p Discharge Flow HPCI-ASD Panel 1
Reactor Water Level (fuel zone)
HPCI-ASD Panel 1
Reactor Shroud Level HPCI-ASD Panel 1
Suppression Chamber Level HPCI-ASD Panel 1
Emergency Condensate Storage Tank Level HPCI-ASD Panel 1
RHR System Loop B Flow RHR-ASD Panel 1
Torus Temperature ADS-ASD Panel 1
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i Table 3.2.I-2
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' Alternate Shutdown Controls-I t
Controls l
4 HPCI Turbine HPCI Auxiliary Jube Oil Pump HPCI Fan Coil Unit l
IIPCI Flev Controller HPCI Flow Transmitter (FT-82).
HPCI-MD-14 Turbine Steam Supply Isolation HPCI-MO-15 Steam Supply. Inboard Isolation HPCI-MD-16 Steam Supply Outboard Isolation
=i HPCI-MO-17 HPCI Pump. Suction ECST HPCI-MO-19 HPCI Injection
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HPCI-M0-20 HPCI Pump Discharge HPCI-MO-21 HPCI Test Bypass to ECST HPCI-M0-24 HPCT Test Bypass Shutoff HPCI-M0-25 HPCI Minimum Flow Bypass HPCI-MO-58 HPCI Pump Suction from Suppression Pool RHR-M0-12B RHR HX B Outlet RHR-M0-13D RHR Pump D Suction f rom Torus RHR-M0-15D RHR Pump D Shutdown Cooling Suction EHR-MO-leB RER Pump B and D Minimum Flow RHR-MO-27B RHR Loop B Injection Outboard Throttle RRR-MO-34B Suppression Chamber Cooling Loop B Inboard Isolation RHR-MO-39B Suppression Chamber Cooling Loop B Outboard Isolation l
RRR-MO-65B RHR RX B Inlet i
i RHR-MO-66B RHR RX B Bypass Throttle j
REC Pumps 1C and ID MS-RV-71E Safety Relief Valve Main Steamline-C MS-RV-71F Safety Relief Valve Main Steamline-C MS-RV-71G Safety Relief Valve Main Steamline-D 1
Diesel Generator No. 2 Engine - Local Isolation, Control and Indication l
Diesel Generator No. 2 Generator Relay and Control - Local Isolation, Control and Indication i
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o Table 4.2.I Alternate Shutdown Instrumentation Surveillance Frequencies Channel Channel Ins t rument Check Calibration HPCI Turbine Steam Inlet Pressure (Reacter Pressure) once/ cycle once/ cycle HPCI Pump Discharge Flow once/ cycle once/ cycle Reactor Water Level (fuel zone) cnce/ cycle once/ cycle Reactor Shroud Level once/ cycle once/ cycle Suppression Chamber Level once/ cycle once/ cycle Emergency Condensate Storage Tank Level once/ cycle once/ cycle RHR System Loop B Flow once/ cycle once/ cycle Torus Temperature once/ cycle once/ cycle l
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.. BASES (Cont'd) 3.2 F.
Primary Containment Surveillance Information l
For each parameter monitored, as listed in Table 3.2.F. there are two (2) channels of instrumentation. By comparing readings between the two (2) channels, a near continuous surveillance of instrument performance is a'railable.
Any deviation in readings will initiate an early recalibration, there-l by maintaining the quality of the instrument readings.
The operability of the reactor water level instrumentation in Tables 3/4.2.F ensures that sufficient information is available to monitor and assess accident situations.
G.
Recirculation Pump Trip The recirculation pump trip has been added as a means of limiting the con-sequences of the unlikely occurrence of a failure to scram during an antici-paced transient. The response of the plant to this postulated event falls within the envelope of study events given in General Electric Company Topical Report, NEDO-10349, otted March, 1971.
H.
Post-Accident Monitoring The post-accident ronitoring instrumentation supplements existing instru-l mentation that was designed to monitor primarily the normal operational 1.
ranges of these parameters. Post-accident monitoring instrumentation provides information for the ranges that may exist during the extreme conditions postulated to occur during and after some accidents.
I.
Alternate Shutdown Capability d
The purpose of the Alternate Shutdown System is to provide the capability to shut down the plant in the unlikely event of a fire which disables the controls and d
instrumentation necessary to shut down the plant from the control room. As documented in the CNS Response to 10CFR50 Appendix R, "Fire Protection of Safe Shutdown Capability," Volume III, there are five areas of the plant that i
necessitate alternate shutdown capability in accordance with Section III.G.3 of i
Appendix R.
Those areas are: the control room, the cable spreading room, the I
caole expansion room, the auxiliary relay room and the northeast corner of the l
Reactor Building 903' elevation.
3 The Alternate Shutdown (ASD) System provides a means of controlling the High i
Pressure Coolant Injection (HPCI), Automatic Depressurization (ADS), Residual Heat i
Removal (EHR) Torus Cooling, and Reactor Equipment Cooling Systems independent of l
the five plant areas requiring alternate shutdown.
Using the alternate shutdown system, the plant can be cooled down and depressurized independent of a fire in any 1
of the five plant areas necessicating ASD capability.
REFERENCES l
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"Low-Low Set Relief Logic System and Lower MSIV Water Level Trip for Cooper Nuclear Station" NEDE 22197, December 1982 General Electric Company.
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