ML20195B553
| ML20195B553 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/24/1999 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20195B552 | List: |
| References | |
| NUDOCS 9906020014 | |
| Download: ML20195B553 (11) | |
Text
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Docum:nt Centr:I De:k LR-N99236 Attachm:nt 3 LCR H99-05 I
HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS) l l
TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this change request:
1 l
TECHNICAL SPECIFICATION PAGE 1
Index iv, vi, vii, ix, x, xiii, xiv, xviii and xix Table 4.11.1.1.1-1 3/4 11-2 t
l i
1 9906020014 990524 PDR ADOCK 05000354 P
PDR 4
I
INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS T
SECTION PAGE 2.1 SAFETY LIMITS THERMA L POWER, Low Pres s u re o r Low F10w.............................
2-1 i
THERMAL POWER, High Pressur. and High F1ow..........................
2-1 Reactor Coolant System Pressure.....................................
2-1 Reactor Vessel Water Leve1..........................................
2-2
- 2. 2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints.................
2-3 Table 2.2.1-1 Reactor Protection System Instrumentation S e tpo i n t s...........................................
2-4 BASES 2.1 SAFETY LIMITS THERMAL POWER, Low Pressure or Low F1ow............................
B 2-1 THERMAL POWER, High Pressure and High F1ow......................
3 2-2.
Table 82.1.2-1 Uncertainties Used in the Determination of the Fuel Cladding Safety Limit.....................
B 2-3 Teele 02.1.2-2 F.;;'r.el "eis;; ;f.":r: :ter; ";;d fr. tr.:
l'
!. [*.i'.!" f. b.i..b. '.$'5.,IM!..;.S.II"'IUI
"}_
,h 6
w e,
Reacter Coolant System Pressure.....................................
B 2-5 R eacter Ves se l Wate r L eve l..........................................
B 2-5
- 2. 2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection Systes Instrumentation Setpoints.............
~B 2-6 HOPE CREEK iv.
i
INDEX LIMITING CONDITIONS FOR OPERATICN AND SURVEILLANCE REQUIREM sE: !ON c__aG_E l
3,4 2.2 APRM SETPOINTS.
3/4 2-2 i
3,4. 2. 3 MINIMLM CRITICAL DOWER RATIO.
3/4 2-3 l
3/4.2.4 L:NEAR HEAT GENERATION RATE..
l 3/4 2-5 3/4.3 INCTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.....
3/4 3-1 Table 3.3.1-1 Reactor Protection System Instrumentation...............
......... 3/4 3-2
-T wi. 3.3.1-23.9ecter?rstectica5,et: R;;;;n::
j[r im&5.
ai, aa Figure 4.3.1.1-1 Reactor Protection System Surveiltance Requirements...........................
3/4 3 7 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION...................... 3/4 3-9 Table 3.3.2-1 Isolation Actuation Instrumentation....... 3/4 3-11 Table 3.3.2-1 Isolation Actuation Instrumentation Setpoints...
3/4 3-22 8
-Taviv3.3.2-3jjuletien0,ste;:netr;;;nt:tinR;;;;n::
j['
im.
ai n a a, Table 4.3.2.1-1 Isolation Actuation Instrumentation
- Surveillance Requirements.................
3/4 3-28 HOPE CREEK vi.
Amen.e nt No. 34 I
l
l j
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l
EME'RGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4.3.3 3/4 3-32 Table 3.3.3-1 Emergency Core Cooling System Actuation Instrumentation......
3/4 3-33 Table 3.3.3-2 Emergency Core Cooling System Actuation Instrumentation Setpoints.............
3/4 3-36
--TeLie 3.3.3-3 p.;r; = y Cer: Cce!"; Sys t-- Res?cns"
,,m.
., ~
Table 4.3.3.1-1 Emergency Core Cooling System Actuation Instrumentation Surveillance Requirements......................
..... 3/4 3-39 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMFNTATION ATWS Recirculation Pump Trip System Instrumentation.......
3/4 3-41 Table 3.3.4.1-1 ATWS Recirculation Pump Trip System Instrumentation.........................
3/4 3-42 t
Table 3.3.4.1-2 ATWS Recirculation Pump Trip System Instrumentation Setpoints.............. 3/4 3-43 Table 4.3.4.1-1 ATWS Recirculation Pump Trip Actuation Instrumentation Surveillance Requirements............................
3/4 3-44 End-of-Cycle Recirculation Pump Trip System Instrumentation...........................................
3/4 3-45 4
Table 3.3.4.2-1 End-of-Cycle Recirculation Pump Trip System Instrumentation..................
3/4 3-47 l
Table 3.3.4.2-2 End-of-Cycle Recirculation Pump Trip Setpoints...............................
3/4 3-48
"- Table 3.3.4.2-3 End-of-Cycle Recirculation Pump Trip System Response Time....................
3/4 3-49 Table 4.3.4.2.1-1 End-of-Cycle Recirculation Pump Trip j
System Surveillance Requirements......
3/4 3-50 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEN ACTUATION INSTRUMENTATION...
3/4 3-51 HOPE CREEK vii
INDEX LIMITING CONDITIONS POR OPERATION AND SURVEILLANCE REQUIREMENTS srcIcw 23 fag Table 3.3.7.4-1 Remote Shutdown Monitoring Instrumentation 3/4 3-75 Table 3.3.1.4 2 Remote Shu'tdown Systems Controls 3/4 3-77 Table 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Surveillance Requirements 3/4 3-82 Acetdent Monatoring Instrumentation 3/4 3 84 Table'3.3.7.5-1 Accident Monitoring Instrumentation 3/4 3 85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements 3/4 3-37 Source Range Monitors 3/4 3-88 Traversing In-Core Probe System 3/4 3-89 Radioactive Liquid Effluent Monitoring Instrumentation.
3/4 3-91 Table 3.3.7.
Radioactive Liquid Effluent 9
Monitoring Instrumentation 3/4 3-92 Table 4.3.7.
Radioactive Li paid Ef fluent Monitoring fo Instrumentation Surveillance Requirements 3/4 3 94 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-96 Table 3.3.7. d Radioactive Gaseous Effluent i
j Monitoring Instrumentation.
3/4 3-97 l
Table 4.3.7 Radioactive Gaseous Effluent Monitoring
(
Instrumentation Surveillance
. Requirements.
3/4 3-100 3/4.3.8 DE h 3/4 3-103 l
3/4.3.9 FEEDW TER/ MAIN TUR3INE TRIP SYSTEM ACTUATION INSTRIMENTATION 3/4 3-105 Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation.
3/4 3-106 HCPE CREEK 1x Amendment No.31 l
- NCEA
.:w!':NG CON 0!T!0NS FOR 08ERATION AND SURVEILLANCE REQUIREWENTS 5!-:4 PAGE
- acie 3 3.9-2 Feoowater/ Main Turnine Trio System Actuation Instrumentation Setooints.
3/4 3 ':-
- acle 4.3.9.1-1 Feeswater/ Main Turoine Trip System Actuation Instrumentation Surveillance Requirement................
3/4 3-;;a 3/4 4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops..........................
3/4 4-1 Figure 3. 4.1.1-1 % tated Thermal Power Versus Core Flow................
3/4 4-3 Je' h a.,;...............................................
3/4 4 4 L. & talation Loop Flow....
3/4 4-5 Idle Recirculation Loop Startup........
3/4 4-6 ~,
3/4.4.2 SAFETY / RELIEF VALVES Safety / Relief Va1ves..................................
3/4 4-7 Sa fety/ Relief Valves Low Low Set Function................
3/4 4-9 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.................................
3/4 4-10 Ope r a t i onal Leekage.......................................
3/4 4-11 Table 3.4.3.1-1 poector Ceelant Systes Pressure
^
Isolation Valves........................
3/4 4-13
'L
~
Tatte 3.4.3.2-2 Asacter Coolant System Interface Valves Leekage Pressure Monitors.......
3/4 4-14 3/4.4.4 casu sTw................................................
3 / 4 4 - 15 Table 3.4.4-1 Reacter Coolant Systas Chemistry Lietts....................................
3/4 4-17 3/4.4.5 SPECIFIC ACTIV1fY.........................................
3/4 4-18 Tabis 4.4.5-3. Primary Coelant specific Activity Sample and Analysis Progras......................
3/4 4*20 Amendment Me. 3 MOPE CREEK x
INDEX LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS SECTION PAGE 3/4.7.3 FLOOO PROTECTION..........................................
3/4 7-9 Table 3.7.3-1 Perimeter Flood Doors.....................
3/4 7-10 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.....................
3/4 7-11 3/4.7.5 SNUB 8ERS..................................................
3/4 7-13 Table 4. 7.5-1 Snubber Visual Inspection Interval........ 3/4 7-17a l
Figure 4.7.5-1 Sample Plan 2) for Snubber Functional Test.........................................
3/4 7-18 3/4.7.6 SEALED SOURCE CONTAMINATION...............................
3/4 7-19 3.4.7.7 MAIN TURBINE BYPASS SYSTEM................................
3/4 7-21 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C.
Sources-Operating....................................
3/4 8-1 Table 4.8.1.1.2-1 Diesel Generator Test Schedule........
3/4 8-10 A.C. Sources-Shutdown.....................................
3/4 8-11 3
1 3/4.8.2 0.C. SOURCES D.C.
Sources-Operating....................................
3/4 8-12 Table 4.8.2.1-1 Battery Surveillance Requirements.......
3/4 8-6' D.C. Sources-Shutdown.....................................
3/4 8-17 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS Distribution - Operating..................................
3/4 8-18 Di stri bution - Shutdown...................................
3/4 8-21 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Primary Containment Penetration Conductor Overcurrent Protective 0evices......................................
3/4 8-24 Table 3.8.4.1-1 F,*inary Containment Penetration Conductor Overcurrent Protective Devices..........
3/4 8-26 Motor Operated Valve Thermal Overload Protection (Bypassed)..............................................
3/4 8-30 HOPE CREEK xiti Amendment No. 50
4 INDEX LIMITING CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMNTS SECTION PAGE
-Tetle 3.0.0.P1 "et;r 0;;r;t:d V:lv::"h: =1 Overle:d j./
"r; tecti r. (0g ;;;; )...................
3/4 G-31 Motor Operated Valve Thermal Overload Protection (Not Bypassed)..........................................
3/4 8-38 Table 3.8.4.3-1 Motor Operated Valves-Thermal Overload Protection (Not 8ypassed)...............
3/4 8-39 Reactor Protection System ilectric Power Monitoring.......
3/4 8-40 Class 1E Isolation areaker Overcurrent Protection Devices (Breaker Tripped by LOCA Signal)................
3/4 8-41 Table 3.8.4.5-1 Class 1E Isolation Breaker Overcurrent Protective Devices (3reaker Tripped by a l
LOCA S jna1)...........................
3/4 8-42 Power Range Neutron Monitoring Systes Electric Power Monitoring..............................................
3/4 8-44 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR M00E SWITCH.......................................
3/4 9-1 3/4.9.2
-INSTRUMENTATION...........................................
3/4 9-3 3/4.9.3 CONTROL R00 P0SITION......................................
3/4 9-5 j
3/4.9.4 DECAY TIME................................................
3/4 9-6 3/4.9.5 C0094UN I CAT I ONS............................................
3/4 9-7 3/4.9.6 REFUELING PLATF0RM........................................
3/4 9-8 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L....................
3/4 9-10 l
3/4.9.4 WATER LEVEL - REACTOR VESSE L..............................
3/4 9-11 3/4.9.9 iiITERLEVEL-SPENTFUELSTORAGEP00L.....................
3/4 9-12 3/4.9.10 CONTROL R00 REMOVAL Single Control Rod Remova1................................
3/4 9-13 Multiple Control Rod Remova1..............................
3/4 9-15 H0PE CREEK xiv l
r INDEX RASES SECTICN g
INSTRUMDf?ATION (Continued)
Remote Shutdown Monitoring Instrumentation i
and Controls B 3/4 3-5 Accident Monitoring Instrumentation B 3/4 3-5 Source Range Monitors B 3/4 3-5 Traversing In-Core Probe System B 3/4 3-5 Radioactive Liquid Effluent Monitoring Inst rumentation B 3/4 3-6 Radioactive Gaseous Effluent Monitoring Ins t rumentation B 3/4 3-6 3/4.3.8 DELETED B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TJRBINE TRIP SYSTEM ACTUATION INSTRUMENTATION B 3/4 3-7 Figure B3/4 3-1 Reactor Vessel Water Level.
B 3/4 3-3 3/4.4 REACTOR COOIAlff SYSTEM 3/4.4.1 RECIRCULATION SYSTEM.
B 3/4 41 3/4.4.2 SAFETY / RELIEF VALVES B 3/4 g " M L
3/4.4.3 REACTOR COOIANT SYSTEM LEAKAGE Leakage Detection Systems B 3/4 4-3 operational Leakage B 3/4 4-3 3/4.4.4 CHEMISTRY B 3/4 4-3 3/4.4.5 SPECIFIC ACTIVITY B 3/4 4-4 3/4.4.6 PRESSURE / TEMPERA'!URE LIMITS B 3/4 4-5 1
Table 33/4.4.6-1 Reactor Vessel Toughness B 3/4 4-7 F1 ure 53/4.4.6-1 Fast Neutron Fluence (E>1Mov) at (1/4)T as a Function of Service life.
B 3/4 4-8 HOPE CREEK Kv111 Amendment No.82 l'
INDEX BASES SECTION PAGE 3/4.4.7 MAIN STEAM LINE ISOLATION VAL,VES.....................
B 3/4 4-6 3/4.4.8 STRUCTURAL INTEGRITY.................................
8 3/4 4-6 3/4.4.9 RESIDUAL HEAT REMOVAL................................
8 3/4 4-6 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1/2 ECCS - OPERATING and SHUTD0WN........................
B 3/4 5-1
.a.
3/4.5.3 SUPPRESSION CHAMBER...........................
8 3/4 5-t1 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity........................
8 3/4 6-1 Primary Containment Leakage..........................
8 3/4 6-1 Primary Containment Ai r Locks........................
B 3/4 6-1 8'
NSIV Sealing System..................................
8 3/4 6-1 Primary Containment Structural Integrity.............
8 3/4 6-2 Drywell and Suppression Chamber Internal Pressure....
8 3/4 6-2 Drywell Average Ai r Temperature......................
8 3/4 6-2 Drywel l and Suppres si on Chamber Purge Systas.........
8 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS.............................
8 3/4 6-3 8 3/4 6-5 3/4. 6. 3, PRIMARY CONTAIMENT ISOLATION VALVES.................
8 3/4 6-5 3/4.6.4j.VACUUMRELIEF........................................
8 3/4 6-5 3/4.6.5 SEC0 MARY C0NTAIMENT................................
3/4.6.6 PRIMARY CONTAIMENT ATMDSPHERE CONTR0L............... 8 3/4 HOPE CREEK xix
r--
TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of of Detection Liquid Release Sampling Analysis Activity (LLD)*
Type Frequency Frequency Analysis (gCi/ml)
A.
Batch Waste P
P Principal Release" Each Batch Each Batch Gamma 5 x10
Sample Emitters
- Tanks M I-131 1x10
P M
Dissolved and 1x10-5 One Batch /M Entrained Gases (Gamma Emitters)
P M
H-3 1x10 '5 8
Each Batch Composite Gross Alpha 1x10
P Q
Sr-89, Sr-90 5x10
8 Each Batch Composite Fe-55 1x10
B. Continuous M
Principal Gamma 5x10" d
Releases
- Composite Emitters
- Station Service NA Water ystem I-131 1x10
(5 5 w s) M (If contaminated W
M Dissolved and 1x10
as indicated Grab Sample Entrained Gases by SACS or (Gamma Emitters)
RACS system.
NA M
H-3 1x105 8
?
Composite Gross Alpha 1x10
NA Q
Sr-89, Sr-90 5 x10
8 Composite Fe-55 1x10
HOPE CREEK 3/4 11 2 Amendment No. 108