ML20246E715
| ML20246E715 | |
| Person / Time | |
|---|---|
| Issue date: | 06/21/1989 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Calvo J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8907120365 | |
| Download: ML20246E715 (26) | |
Text
-
June 21,1989
{
i MEMORANDUM FOR:
Jose A. Calvo, Chief Technical Specifications Branch Division of Operational Events Assessment, NRR FROM:
David C. Fischer, Section Chief Special Projects Section Technical Specifications Branch Division of Operational Events Assessment, NRR
SUBJECT:
MINUTES OF MEETING WITH COMBUSTION ENGINEERING OWNERS GROUP (CE0G) ON THEIR NEW STANDARD TECHNICAL SPECIFICATIONS (STS)
On June 7, 1989 the NRC staff met with the Combustion Engineering Owners Group (CEOG) to hear the presentation of their proposed new Restructured Standard Technical Specifications (RSTS), and to present an overview of the planned review process. The format and organization of the new RSTS were presented by Richard Bernier of the CE0G. The review of the CE0G RSTS begins on June 7, 1989 per the schedule and milestone chart provided.
OHginal Signed By David C. Fischer Special Projects Section Technical Specifications Branch Division of Operational Events Assessment NRR
Enclosures:
List of Attendees CE0G Handout Milestones for the CE0G new STS (RSTS) and lead plant DISTRIBUTION:
Please see attached 8907120365 8906Ei PDR TOPRP ENVC-E C
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MEETING'ON CEOG RSTS JUNE 7, 1989
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.f ATTENDEES
- NAME AFFILIATION
' Kenneth Berry Consumers Power Co. CEOG Member y.g Jim Kuemin-Consumers Power Co.
Thomas McLeod SCE/ Licensing Charles DeDeaux LP&L-David Fischer-NRC/NRR/DOEA/0TSB Jose Calvo NRC/NRR/DOEA/0TSB Larry Phillips NRC/NRR/ DEST /SRXB Sang Rhow NRC/NRR/0EST/SICB Millard Wohl NRC/NRR/DOEA/0TSB Richard A. Bernier Arizona Public Service Co.
Stuart 'ebster Combustion Engineering John Tsao.
NRC/NRR/ DEST /EMTB Chris Hoxie NRC/NRR/00EA/0TSB Bill Arcieri ENSA Yang S. Kim NUS Corporation Jared Wermiel NRC/NRR/ DEST /SPLB Dan Williamson EXCEL /BWROG Don Hickman NRC/NRR/DRSP/PD5 Rich Correia NRC/NRR/DLPQ/HFAB l'
Sai P. Chan NRC/NRR/ DEST /ESGB Howard Richings NRC/NRR/ DEST /SRXB Jim Lazevnick NRC/NRR/ DEST /SELB Bill LeFave NRC/NRR/ DEST /SPLB Chang-Yang Li.
NRC/NRR/ DEST /SPLB James Wing NRC/NRR/DREP/PRAB Daniel Fieno NRC/NRR/ DEST /SRXB Calvin W. Moon NRC/NRR/DOEA/0TSB2 Robert White LLNL Scott Newberry HRC/NRR/ DEST /SICB Warren J. Hall NUMARC
---b_____5m___.___ _. _ _. _ _.. _ _ _ _ _ _ _ _ _ _, _. _ _ _, _ _, _ _ _ _,.,. _ _ _ _ _ _, _,. _ _, _ _ _ _ _ _ _ _ _ _
COMBUSTION ENGINEERING i
OWNERS GROUP
)
PRESENTATION TO THE NRC ON RESTRUCTURED STANDARD TECHNICAL SPECIFICATIONS JUNE 7,
1989 "CE0G RSTS" CEN-355
~
COMBUSTION ENGINEERING OWNERS GROUP PRESENTATION TO THE NRC ON RESTRUCTURED STANDARD TECHNICAL SPECIFICATIONS
)
JUNE 7,
1989 "CE0G RSTS" CEN-355
o 1
ANALOG - DIGITAL Two CLASSES OF C-E PUNTS BASED ON PROTECTIVE SYSTEMS o
ANALOG:
PALISADES FORT CALHOUN MAINE YANKEE MILLSTONE 2 CALVERT CLIFFS 1 & 2 ST. LuCIE 1 & 2 O
DIGITAL:
ANO-2 SONGS 2 & 3 WATERFORD 3 PALO VERDE 1, 2, 3 2
i
i ANALOG - DIGITAL TwO CLASSES OF-C-E PU.NTS BASED ON PROTECTIVE SYSTEMS o
ANALOG:
i PALISADES I
FORT CALHOUN j
MAINE YANKEE M7.LLSTONE 2 (ALVERT CLIFFS 1 & 2 ST. LucIE 1 & 2 o
DIGITAL:
i ANO-2 SONGS 2 & 3 WATERFORD 3 PALO VERDE 1, 2, 3 1
2 1
I I
e.
q J.
APPENDIX C I
TABLE 1 l
LCOs TO BE RETAINED IN CCMBCSTION ENGINEERING
{
l STAh0ARD TEChhlCAL SPECIFICATION 5 f
"b I
CRITERIA
[
LCO l
3.1 REACTIVITY CONTROL SYSTEMS
)
3.1.1 3.1.1.1 Shutdown Margin --Teoid. > 210F (Note 1) 2
)
Shutdowr. Ma gin - Teold. c 210F (Note 1) 2
)
~
e 3.1.2 3.1.1.2 0
3.1.11/12 3.1.1.3 Moderator Temperature Coefficient 2
{
3.3.1 3.1.1.4 Minimum Temperature for Criticality 2
]
2&3
)
3.1.8 3.1.3.1 CEA Position 3.1.9 3.1.3.5 Shutdown CEA Intertion Limit 2
2 3.1.3.6 Regulating CEA Insertion Limits 2
3.1.10 3.1.3.7 Part Length CEA Insertion Limits (1). 3.1.11 D
/
3.2 PCWER DISTRIBUTION LIMITS 2
3.1.3/4 3.2.1 Linear Heat Rate 3.1.4&5/5 3.2.2 Planar Radial Peaking Factors--Fxy 2
3.1.6 3.2.3 Azimuthal Power Tilt -- Tq 2
2 3.1.7
. 3.2.4 DNBR Margin 2
(2) 3.3.3 13.2.5 RCS Flow Rate 3.3.16
' 3.2.6
-Reactor Coolant Cold Leg Temperature 2
2 3.2.7 uial Shape Index 3.1.7/3 2
3.2.8 Pressurizer Pressure 3.3.17 3.3 INSTRUMENTATION Reactor Protective Instrumentation (Note 2) 3 3.2.1-6/-9 3.3.1 ESFAS Instrumentation (Note 2) 3 4
.3.2.7-9/3.2.7-12 3.3.2 Radiation Monitoring.Ic3trumentation (Notes 2 & 3) 3 3.3.3.1 (3) 3.3.3.5 Remote Shutdown System (Notes 2 & 4)
Risk 3.3.3.5 Post-Accident Monitoring Instrumentation 3
(4)
'3.2.10/13
$)
3.2.11/14 I
3.4 REACTOR COOLANT SYSTEM 2&3 3.3.3 3.4.1.1 Startup and Power Operation 2&3 3.3.4 3.4.1.2 Hot Standby 2&3 l
3.3.5 3.4.1.3 Hot Shutdown 2&3
{
3.4.1.4.1 Cold Shutdown - Leops filled 2&3 3.3.6 3.4.1.4.2.
Cold Shutcown - Loops not filled 3.3.7 C-1 Where there are 2 numbers sepa"ated by a slash (/),
the first is analog and the srcond is digital.
(or atmospheric and dual for containment LCOs).
\\
APPENDIX C TABLE 1 LCOs TO BE RETAINED IN CCMBUSTION ENG1hEER!N_G STANDARD TEGhNICAL 5PEC FICATION5 Na$e3 5
c - -
CRITERIA LCO 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 3.1.1.1 Shutdown Margin --Tcold. > 210F (Note 1) 2 3.1.2 3.1.1.2 Shutdown Nargin - Teold. E 210F (Note 1) 2 o
3.1.11/12 3.1.1.3 Moderator Temperature Coefficient 2
3.3.1 3.1.1.4 Minimum Temperature for Criticality 2
2&3 3.1.8 3.1.3.1 CEA Position 3.1.9 3.1.3.S Shutdown CEA Intertion Limit 2
2 3.1.3.6 Regulating CEA Insertion Limits 2
3.1l10 3.1.3.7 Part length CEA Insertion Limits 3.1 11 D (1) 3.1 PCh'ER DISTRIBUTION LIMITS 2
3.1.3/4 3.2.1 Linear Heat Rate 3.1.4&5/5 3.2.2 Planar Radia. Peaking Factors--Fxy 2
2 3.1.6 3.2.3 Azimuthal Power Tilt -- Tq 2
3.1.7 3.2.4 DNBR Margin 2
l3.2.6 3.2.5 RCS Flow Rate (2) 3.3.3 Reactor Coolant Cold Leg Temperature 2
3.3.16 2
3.2.7 Axial Shape Index 2
3.1.7/3 3.2.8 Pressurizer Pressure 3.3.17 3.3 INSTRUMENTATION 3.2.1-6/-9 3.3.1 Ret.ctor Protective Instrumentation (Note 2) 3 3.2.7-9/3.2.7-12 3.3.2 ESFAS Instrumentation (Note 2) 3 3.3.3.1 Radiation Monitoring Instrumentation (Notes 2 & 3) 3 3.3.3.5 Remote Shutdown System (Notes 2 & 4)
Risk (3) 3.3 6
Post-Accident Monitoring Instrumentation 3
4) 3.2.10/13 (G) 3.2.11/14 3.4 REACTOR C00LAN7 SYSTEM 2&3 3.3.3 3.4.1.1 Startup and Pcwer Operation 2&3 3.3.4 3.4.1.2 Pot Standby 2&3 3.3.5 3.4.1.3 Hot Shutdown 3.4.1.4.1 Cold Shutdown - Leops filled 2&3
- 5. & 3 3.3.6 3.4.1.4.2.
Cold Shutoown - Loops not filled 3.3.7 C-1 l
Where there are 2 numbers separated by a slash (/),
the first is analog and the second is digital.
(or atmospheric and dual for containment LCOs).
l 1
L__________
CE TABLE 1 (Continued)
CRITERIA LCO 3.6.6 3.7.3 Component Cooling Water System 3
3 3.6.7 3.7.4 Service Water System 3.6.8 3.7.5 Ultimate Heat Sink 3
3.6.9 3.7.7 Essential Chilled Water System 3
3.6.11 3.7.9 ECCS Pump Room Air Exhaust Cleanup System (Optional) 3 3.8 ELECTRICAL POWER SYSTEMS 3.7.1 3.8.1.1 A.C. Sources - Operating 3
3.7.2 3.8.1.2 A.,C. Sources - Shutdown 3
3.7.3 3.8.2.1 0.C. Sources - Operating 3
D.C. Sources - Shutdown 3
3.7.4 y3.8.2.2 Onsite Power Distribution Sources - Operating 3
3.7.5 3.8.3.1 3.7.6 3.8.3.2 Onsite Power Distribution Sources - Shutdown 3
3.9 REFUELING OPERATIONS 3.8.1 3.9.1 Boron Concentration 2
3.8.2 3.9.2 Instrumentation 3
2 3.8.8 3.9.3 Decay Time 3.3.3 3.9.4 Containment Building Penetrations 3
3.8.4 3.9.8.1 Shutdown Cooling and Coolant Circulation -
l 2
l High Water level 3.8.5 3.9.8.2 Shutdown Cooling and Coolant Circulation -
Low Water Level 2
3.8.3 3.9.9 Containment Purge Valve isolation System 3
3.8.6/7 3.9.10 Water Level-Reactor Vessel 2
i 3.8.10 3.9.11 Water Level-Storage Pool 2
{
3.9.12 Fuel Building Air Cleanup System 3
{
3.8.13 l
Notes:
1.
Required for Modes 3 through 5.
May be relocated for Modes 1 ar.d 2.
2.
LCOs for this system should be retained in STS. The Policy Statem nt Criteria should not be used to relocata specific trip functions, channels, or instruments within these t.COs.
The staff is pursuing alternative approaches which would allow relocatien 3.
I of some of these LCOs on a schedule consistent with the schedule for develop-ment of the new STS. The staff is also initiating rulemaking to delete the requirement that RETS be included in Technical Specifications.
Because fires (either inside or outside the control room) can be a significar.t 4.
contributor to the core relt frecuency anc because the uncertainties with fire inittation frecuency can be significant, the staff believes that this LCO
'hould be retained in the STS at this time. The staff will consider relocation
.,of Rerote Shutdown Instrumentation on a plant-specific basis.
5.
This LCO will be considered for relocaticn to a licensee-controlled docurer.t on a plant-specific basis.
C-3
CE-TABLE 1 (Continued)
CRITERIA LCO 3.6.6 3.7.3 Component Cooling Water System 3
3.6.7 3.7.4 Service Water System 3
3.6.8 3.7.5 Ultimate Heat Sink 3
3.6.9 3.7.7 Essential Chilled Water Fyste":
3 3.6.11 3.7.9 ECCS Pump Room Air Exhaust Cleanup System (Optional) 3 3.8 ELECTRICAL POWER SYSTEMS 3.7.1 3.8.1.1 A.C. Sources - Operating 3
3.7.2 3.B.1.2 A.C. Sources - Shutdown 3
3.7.3 3.8.2.1 0.C. Sources - Operating 3
0.C. Sources - Shutdown 3
3.7.4
>3.8.2.2 3.7.5 3.8.3.1 Onsite Power Distribution Sources - Operating 3
3.7.6 3.8.3.2 Onsite Power Distribution Sources - Shutdown 3
3.9 REFUELING OPERATIONS, 3.8.1 3.9.1 Boron Concentration 2
3.8.2 3.9.2 instrumentation 3
2 3.8.8 3.9.3 Decay Time 3.8.3 3.9.4 Containment Building Penetrations 3
3.8.4 3.9.8.1 Shutdown Cooling and Coolant Circulation -
2 High Water Level 3.8.5 3.9.8.2 Shutdown Cooling and Coolant Circulation -
Low Water Level 2
3.8.3 3.9.9 Containment Purge Valve Isolation System 3
3.8.6/7 3.9.10 Water Level-Reactor Vessel 2
3.8.10 3.9.11 Water Level-Storage Pool 2
3.9.12 Fuel Building Air Cleanup System 3
3.8.13 Notes:
1.
Required for Modes 3 through 5.
May be relocated for Modes 1 and 2.
2, LCOs for this system should be retained in STS. The Policy Statement Criteria should not be used to relocate specific trip functions, channels, or instruments within these LCOs.
3.
The staff is pursuing alternative approaches which would allow relocaticn of some of these LCOs on a schedule consistent with the schedule for develop-ment of the new STS. The staff is also initiating rulemaking to delete the requirement that RETS be included in Technical Sper-fications.
i 4.
Because fires (either inside or outside the control room) can be a significant contributor to the core melt frequency and because the unct.rtainties with fire initiation frecuency can be significant, the staff believes that this LCO should be retained in the STS at this time. The staff will consider relocation of Remote Shutdown Instrumentation on a plant-specific basi 3.
I l
5.
This LCO will be considered for relocatien to a licensee-controlled document on a plant-specific basis.
C-3 i
l I
i r
l
J 57.3 CE-TABLE 2 (Continued) j i
JC0 3.7 PLANT SYSTEMS 3.7.2 Steam Generator Pressure / Temperature Limitation j
3.7.6 Flood Protection 1
3.7.8 Control Room Emergency Air Cleanup System 3.7.10 Snubbers 3.7.11 Sealed Source Contamination 3.7.12 Fire Suppression Systems 3.7.12.1 Fire Suppression hater System 3.7.12.2 Spray and/or Sprinkler Systems 3.7.12.3 CO2 Systems 3.7.12.4 Halon Systems 3.7.12.5 Fire Hose Stations 3.7.12.6 Yard Fire Hydrapts and Hose Houses 3.7.13
~ Fire-Rated Assemblies 3.8 ELECTRICAL POWER SYSTEMS 3.8.4.1 Containment Penetration Conductor Overcurrent Protection Device 3.8.4.2 Motor-Operated Valves-Thermal Overload Protection 3.9 REFUELING OPERATIONS 3.9.5 Communication 3.9.6 Manipulator Crane (Refueling Machine) 3.9.7 Crane Travel - Spent Fuel Pool Building 3.10 SPECIAL TEST EXCEPTIONS 3.1.12/13 3.10.1 Shutdown Margin (Note 6) 3.1.14 D 3.10.2 Group Height, Imrtion, and Pcwer Dist. (Note 6) 3.3.18 3.10.3 Reactor Coolant Loops (Note 6) 3.1.14/15 3.10.4 CEA Position Reg CEA Ins, and Cold Leg Temp. (Note 6)
Gl. 89-01 3.11 RADIOACTIVE EFFLUENTS (Ncte 3) 3.11.1.1 Liquid Waste Discharge to Evap. Ponds -
Concentration 3.11.1.2 Liquid Waste Discharge to Evap. Ponds Dose 3.9.1 3.11.1.3 Liquid Holdup Tanks 3.11.2.1 Gaseous Effluents - Dose Rate 3.11.2.2 Gasecus Effluents - Dose-Noble Gases 3.11.2.3 Gaseous Effluents - Dose--I-131, 133 Tritium & Radionuclides 3.11.2.4 Gaseous Radwaste Treatment 3.9.2 3.11.2.5 Explosive Gas Mixture 3.11.2.6 Gas Storage Tanks 3.9.3 Solid Radioactive Waste 3.11.2 3.11.4 Tctal Dose C-5
/2.SU CE-TABLE 2 (Continued)
LCO 3.7 PLANT SYSTEMS 3.7.2 Steam Generator Pressure / Temperature Limitation 3.7.6 Flood Protection 3.7.8 Control Room Emergency Air Cleanup System 3.7.10 Snubbers 3.7.11 Sealed Source Contamination 3.7.12 Fire Suppression Systems 3.7.12.1 Fire Suppression hater System 3.7.12.2 Spray and/or Sprinkler Systems 3.7.12.3 C02 Systems 3.7.12.4 Halon Systems 3.7.12.5 Fire Hose Stations 3.7.12.6 Yard Fire Hydrspts and Hose Houses 3.7.13 Fire-Rated Assemblies 3.8 ELECTRICAL POWER SYSTEMS 3.8.4.1 Containment Penetration Conductor Overcurrent Protection Device 3.8.4.2 Motor-Operated Yalves-Thermal Overload Protection 3.9 REFUELING OPERATIONS 3.0.5 Connunication 3.9.6 Manipulator Crane (Refueling Machine) 3.9.7 Crane Travel - Spent Fuel Pool Building 3.30 SPECIAL TEST EXCEPTIONS 3.1.12/13 3.10.1 ShutdownMargin(Note 6) 3.1.14 D 3.10.2 Group Height. Insertion, and Pcwer Dist. (Note 6) 3.3.18 3.10.3 Reactor Coolant Loops (Note 6) 3.1.14/15 3.10.4 CEA Position. Reg CEA Ins, and Cold Leg Temp. (Note 6)
GL 89-01 3.11 RADIOACTIVE EFFLUENTS (Ncte 3) 3.11.1.1 Liquid Waste Discharge to Evap. Ponds -
Concentration 3.11.1.2 Liquid Waste Discharge to Evap. Ponds Dose 3.9.1 3.11.1.3 Liquid Holdup Tanks 3.11.2.1 Gaseous Effluents - Dose Rate 3.11.2.2 Gasecus Effluents - Dose-Noble Gases 3.11.2.3 Gaseous Effluents - Dose--I-131, 133, Tritium & Radionuclides 3.11.2.4 Gaseous Radwaste Treatment 3.9.2 3.11.2.0 Explosive Gas Mixture 3.11.2.6 Gas Storage Tanks 3.9.3 Solid Radioactive Waste 3.11.2 3.11.4 Tctal Dese C-5 1
l
9 CLARIFICATIONS:
1 l
l 1.
LCO 3.1.3.7 (NEw 3.1.11 D):
PART LENGTH CEAS NOT USED ON ANALOG PLANTS.
2.
LC0 3.2.5:
RCS FLOW RATE RELOCATED AS SR 3.3.3.2.
1 1
l 3.
LCO 3.3.3.1 RADIATION MONITORS: SPEC HAS BEEN DELETED BASED ON NOTE 3 To TABLE 1 AND GL 89-01.
l THE FOLLOWING HAVE BEEN RELOCATED:
k l
o 1.s 2.c.vz:
W/ PURGE VALVES NEW LCOS 3 - 9. 5 3.8.3.
o 1.c CREACS:
NEW SR 3.6.16.2.
1 l
o 2.A FUEL BLDG.:
NEW SR 3.6.13.2.
o 2.s.r.B, 2.B.II.B RCS LEAKAGE INSTRUMENTS:
NEW LCO 3.3.14.
4 L_-_______-__-_
\\
^
p CLARIFICATIONS:
l 1
i 1.
LCO 3.1.3.7 (NEw 3.1.11 D):
PART LENGTH CEAS NOT USED ON ANALOG PLANTS.
2.
LCO 3.2.5:
RCS FLOW RATE RELOCATED AS SR 3.3.3.2.
3.
LCO 3.3.3.1 RADIATION MONITORS: SPEC HAS sEEN DELETED BASED ON NOTE 3 TO TABLE 1 AND GL 89-01.
THE FOLLOWING HAVE BEEN RELOCATED:
0 1.s 2.C.vI:
w/ PURGE VALVES NEw LCOS 3.5.5 3.8.3.
0 1.c CREACS:
NEW SR 3.6.16.2.
1 0
2.A FUEL BLDG.:
NEw SR 3.6.13.2.
0 2.s.I.s, 2.s.II.s RCS LEAKAGE INSTRUMENTS:
NEw LCO 3.3.14.
i 4
i 1
)
8.
LCO 3.1.3.2 3.1.3.3, :
4 CEA POSITION INDICATION CHANNELS:
THE COMPARABLE SR FOR THE ANALOG PLANTS APPEARS TO HAVE BEEN OMITTED - ADD.
9.
LCO 3.4.5:
A PROGRAM FOR SG TUBE INSPECTION HAS BEEN ADDED TO THE ADMIN. CONTROLS SECTION AS 5.8.4.u.
10.
LC0 3.4.10:
RCP FLYWHEEL APPEARS TO HAVE BEEN OMITTED:
ADD SR 3.3.3.4.
11.
LCO 3.6.1.2:
A PROGRAM FOR CONT. LEAKAGE :HAS BEEN ADDED TO THE ADMIN. CONTROLS.SECTION AS.. 5.8.4.G.
LT AND PT WERE OMITTED FROM THE DESIGN FEATURES SECTION 4.2.3.
12.
LCO 3.6.8.3:
OMITTED, ADD ' AS SR 3.5.14.3 (SIMILAR TO SR 3.5.1.2).
6 l
8.
.LCO 3.1.3.2 3.1.3.3, :
CEA POSITION INDICATION CHANNELS:
THE. COMPARABLE SR FOR THE ANALOG PL. ANTS APPEARS TO HAVE BEEN OMITTED ADD.
9.
LCO 3.4.5:
A PROGRAM FOR SG TUBE INSPECTION HAS BEEN ADDED TO 1ME ADMIN. CONTROLS ~SECTION AS 5.8.4.H.
10.
LCO 3.4.10:
RCP FLYWHEEL APPEARS TO HAVE BEEN OMITTED:
ADD SR 3.3.3.4.
11.
LCO 3.6.1.2:
A PROGRAM FOR CONT. LEAKAGE HAS BEEN ADDED TO THE ADMIN. CONTROLS SECTION AS 5.8.4.G..
LT AND PT WERE OMITTED FROM THE DESIGN FEATURES 1
SECTION 4.2.3.
12.
LCO 3.6.8.3:
OMITTED, ADD AS SR 3.5.14.3 (SIMILAR TO SR 3.5.1.2).
6
GENERAL ARRANGEMENT FRONT MATTER 1.
USE AND APPLICATIONS:
PRESENT DEFINITIONS NEW "How To USE" 2.
SAFETY LIMITS:
COMBINED'LSSS WITH RPS INSTRUMENTATION.
3.
LCOS AND SRS COMBINED WITH SAME PREFIX.
ELIMINATED PRESENT 3/4.2:
PwR DIST.
4.
DESIGN FEATURES ADDED CONTAINMENT LEAKAGE PARAMETERS.
RELOCATED CYCLIC VALUES TABLE.
I
b, GENERAL ARRANGEMENT FRONT MATTER 1
l~
1.
USE AND APPLICATIONS:-
PRESENT DEFINITIONS NEw "How TO USE" 2.
SAFETY LIMITS:
COMBINED LSSS WITH RPS INSTRUMENTATION.
3.
LCOS AND SRS COMBINED WITH SAME PREFIX.
ELIMINATED PRESENT 3/4.2:
PwR DIST.
4.
DESIGN FEATURES ADDED CONTAINMENT LEAKAGE PARAMETERS.
RELOCATED CYCLIC VALUES TABLE.
8
STATISTICS PRESENT STS HAS 159 LCOs LCOS RELOCATED BY CRITERIA APPLICATION:
72 (45%)
LCOS RETAINED:
87 LCOS IN EXPANDED RSTS:
112 0
DUE LARGELY TO INSTRUMENTATION EXPANSION DEFINITIONS EXPANDED BY GL 83-13 (RETS) 4 10
h I
l l
STATISTICS PRESENT STS HAS 159 LCOs LCOS RELOCATED BY CRITERIA APPLICATION:
72 (45%)
LCOS RETAINED:
87 LCOS IN EXPANDED RSTS:
112 o
DUE LARGELY TO INSTRUMENTATION EXPANSION DEFINITIONS EXPANDED BY GL 83-13 (RETS) 10
1 i
OPTIONAL / PLANT SPECIFIC LCOs o
EXAMPLES Toxrc gas MONITOR SPRAY AoorTIvs 12
i y.
L l
l l
l
/
OPTIONAL / PLANT SPECIFIC LCOs o
EXAMPLES toxic gas MONITOR l
SPRAY ApoITIVE
. l l
i i
i l
)
1 1
12 1
w USE & APPLICATIONS
1.1 DEFINITIONS
BASICALLY.PRESENT SECTION.
1.2 LOGICAL CONNECTORS:
1 EXPLAINS USE WITH EXAMPLES.
1.3 COMPLETION TIMES:
EXPLAINS USE.
1.4 FREQUENCY
EXPLAINS USE WITH EXAMPLES.
1.5 LEGAL CONSIDERATIONS:
4 WHAT PART OF CEN-355 SHOULD.BE SUBJECT TO LICENSE PROCESS.
14
p
]
i l
3 USE & APPLICATIONS
1.1 DEFINITIONS
BASICALLY PRESENT SECTION.
I 1.2 LOGICAL CONNECTORS:
l EXPLAINS USE WITH EXAMPLES.
1.3 COMPLETION TIMES:
EXPLAINS USE.
1.4 FREQUENCY
EXPLAINS USE WITH ExnnLES.
i 1.5 LEGAL CONSIDERATIONS:
i WHAT PART OF CEN-355 SHOULD BE SUBJECT TO
\\
LICENSE PROCESS.
l 14 bi
g,'
i l
APPLICABILITY l
1 NEW LCOS:
3.0.5:
PROVIDES EXCEPTION TO LCO 3.0.2 FOR u
EQUIPMENT.BEING RETURNED TO SERVICE AFTER REPAIRS.
3.0.6:
ALLOWS 8 HOURS TO PERFORM SRS PRIOR TO ENTERING ACTIONS.
3.0.7:
SUPPORT SYSTEM INOPERABILITY.
3.0.8:
EXCEPTION TO LC0 3.0.2 TO ALLOW INOPERABLE VALVES TO BE CLOEEO, ETC.
.3.0,9:
IMPLEMENTS MODE REQUIREMENTS.
3.0.10:
EXPLAINS SPECIAL TEST EXCEPTIONS.
i 16 l