ML20246B293
| ML20246B293 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/30/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246B295 | List: |
| References | |
| NUDOCS 8907070270 | |
| Download: ML20246B293 (10) | |
Text
_ _ _ _ _ _ _ _ _ _ _
4 ATTACHMENT TO LICENSE AMEN 0 MENT NO.122 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by
{
the captioned amendment number and contain marginal lines indicating the area l
of change.
REMOVE
,. INSERT j
l l
111 111 v
v 3-134 3-135 3-136 4-85 4-85 4-86 1
4-87 4-88 s907070270 890630 PDR ADOCK 0500 5
P
i
. PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE'0F CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE NO 3.0 LIMITING' CONDITIONS FOR OPERATION (Continued)
'3.22.2' Fire Suppression Water System 3-98 3.22.3 Fire Sprinkler System 3-100 3.22.4 Fire Hose Stations 3-101
.3.22.5 Penetration Fire Barriers 3-102 l
3.23 POWER DISTRIBUTION' LIMITS 3-103 1
Linear Heat Rate (LHR) 3-103 3.23.1
. -Linear Heat Rate Limits 3-107 Table 3.23.1 Table 3'23.2 Radial Feaking Factor Limits, F 3-107 Fig. 3.23-1 AllowableLHRasaFunctionofheakPowerLocation 3-108 Fig. 3.23-2 Allowable LHR as a Function of Burnup 3-109
' Fig. 3.23-3 Allowable LHR as a Function of Peak Power Location for Interior and Narrow Water Gap Fuel Rods 3-110 3.23.2 Radial Peaking Factors 3-111 3.23.3 Quadrant Power Tilt - Tg
'3-112 1
3.24 RADIOLOGICAL EFFLUENT RELEASES 3-114 3.24.1 Radioactive Liquid Effluent Monitoring
. Instrumentation 3-114 Table 3.24-1 Radioactive Liquid Effluent Monitoring i
Instrumentation 3-115 Bases for 3.24.1 3-128 3.24.2 Radioactive Gaseous Effluent Monitoring Instrumentation 3-117 Table 3.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation-3-118 Bases for 3.24.2 3-128 3.24.3 Liquid Effluents Concentration 3-120 Bases for 3.24.3 3-129 3.24.4 Liquid Effluent-Dose 3-121 Bases for 3.24.4 3-129 3.24.5 Gaseous Effluents Dose 3-122 1
Bases for 3.24.5 3-130 3.24.5.1 Dose Rate 3-122 Bases for 3.24.5.1 3-130 3.24.5.2 Noble Gases 3-123 Bases for 3.24.5.2 3-131 3.24.5.3 Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form 3-124 Bases for 3.24.5.3 3-131 3.24.6 Gaseous Waste Treatment System 3-125 Bases for 3.24.6 3-132 3.24.7 Solid Radioactive Waste 3-126 i
Bases'for 3.24.7 3-132 I
3.24.8 Total Dose 3-127 Bases for 3.24.8 3-133 j
3.25 ALTERNATE SHUTDOWN SYSTEM 3-134 /
Table 3.25.1 Alternate Shutdown Minimum Equipment 3-135 /-
i iii Amendment No. 37, #$, $3, $7, $$,
55, 10$, 122 TSP 1185 0335 NLO4 j
J
,i
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE NO 4.0 SURVEILLANCE REQUIREMENTS (Continued)
Table 4.11-3 Detection Capabilities for Environmental Sample l
Analysis 4-57 1
4.11.1 Bases for Monitoring Program 4-59a 1
4.11.3 Bases for Land Use Census 4-59a 4.11.5 Bases for Interlaboratoiy Comparison Program 4-59a 4.12 AUGMENTED INSERVICE INSPECTION PROGRAM F3R HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 4-60 Fig. 4.12 A Augmented Inservice Inspection Program - Main Steam Welds 4-63 Fig. 4.12 B Augmented Inservice Inr.pection Program - Feedwater Line Welds 4-64 4.13 REACTOR INTERNALS VIBRATION MONITORING (DELETED) 4-65 4.14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS 4-68 Table 4.14.1 Operating Allowances 4-68d Table 4.14.2 Maximum Allowable Degradation 4-69 4.15 PRIMARY SYSTEM FLOW MEASUREMENT 4-70 4.16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (SKUBBERS) 4-71 4.17 FIRE PROTECTION SYSTEM 4-75 4.17.1 Fire Detection Instrumentation 4-75 4.17.2 Fire Suppression Water System 4-76 4.17.3 Fire Sprinkler Systen 4-78 4.17.4 Fire Hose Stations 4-79 4.17.5 Penetration Fire Barriers 4-80 4.18 POWER DISTRIBUTION INSTRUMENTATION 4-81 4 18.1 Incore Detectors 4-81 4.18.2 Excore Monitoring System 4-82 4.19 POWER DISTRIBUTION LIMITS 4-83 4.39.1 Linear Heat Rate 4-83 4.19.2 Radial Peaking Factors 4-84 4.20 MODERATOR TEMPERATURE COEFFICIENT (MTC) 4-85 1
4.21 ALTERNATE SHUTDOWN SYSTEM 4-86
/
Table 4.21.1 Alternate Shutdown System Montoring
/
Instrumentation Surveillance Requirements 4-87
/
4.22 (Deleted)
/
4.23 (Deleted)
/
4.24 RADIOLOGICAL EFFLUENT RELEASES 4-90 4.24.1 Radiological Liquid Effluent Monitoring Instrumentation 4-90 l
4.24.2 Radiological Gaseous Effluent Monitoring Instrumentation 4-90 4.24.3 Liquid Effluent Concentration 4-90 1
4.24.4 Liquid Effluent Dose 4-90 1
4.24.5 Gaseous Effluent Dose 4-90 v
Amendment No. 37, 48, 04, 67, (E, ES, j
J E, 118, 122 TSP 1185 0335 NLO4 1,i
r
~
1 3 -.25.
ALTERNATE SHUTDOWN SYSTEM
/
/
LIMITING c'JDITION FOR OPERATION
/
1 l/
1 3.25.1 The Alternate Shutdown System instrumentation and components
/
shewn in Table 3.25.1 shall be OPERABLE.
Operability shall be
/
demonstrated by performing the surveillance in accordance
/
with Section 4.20.
//
APPLICABILITY:
//
Reactor coolant temperature > 325*F.
/-
/
ACTION:
//
a.
With less than the "iiinimum Equipment" in Table 3.25.1 Operable,
/
restore the inoperable equipment to Operable within 7 days, or provide
/
equivalent shutdown capability and restore the inoperable equipment
/
to Operable within 60 days; 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 /> and Cold Shutdown wit in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
//
b.
The provisions of Specification 3.0.3 and 3.0.4 do not apply.
/
I
/
Basis
//
The operability of the Alternate Shutdown System ensures that any fire will
/
not preclude achieving safe shutdown. The Alternate Shutdown System
/
components are independent of areas where a fire could damage systems
/
(
normally used to shut down the reactor. This capability is consistent with
/
Regulatory Guide 1.97 and Appendix R to 10CFR50.
/
I 1
3-134 Amendment No. 122 l
ISP1185 0335 NLO4
r.
[,,
' Table 3.25.1
/
/
L ALTERNATE SHUTDOWN MINIMUM EQUIPMENT
/
/
//
h Minimum Readout
/
No Instrumentation Equipment Location
/
/
/
1
. Pressurizer Pressure 1
C150
/
(PI-0110)
/
//
2 Pressurizer Level 1
C150
/
(LI-0102E)
/
/
/
3 Reactor Coolant Hot Leg 1/ Loop C150A
/
Temperature
/
(TI-0112HAA)
/
(TI-0122HAA)
/
/
4 Reactor Coolant Cold Leg 1/ Loop C150A
/
Temperature
/
(TI-0112CAA)
/
(TI-0122CAA)
/
/
5 Steam Generator Pressure 1/S.G.
C150A
/
(PI-0751E)
/
(PI-0752E)
/
/
6 Steam Generator Level 1/S.G.
C150
/
(LI-0757C)
/
(LI-0758C)
/
/
7 Start-up Range Neutron 1
C150A
/
Monitor
/
(N-001A)
/
/
C150
/
Suction Pressure
/
(PS-0741D)
/
/
9 SIRW Tank Level 1
C150A
/
(LT-0332B)
/
//
10 Auxiliary Feedwater 1/S.G.
C150
/
Flow Rate
/
(FI-0727B)
/
(FI-0749B)
/
3-135 Amendment No. 122 TSP 1185 0335 NLO4 I
Table 3.25.1
/
/
(Continued)
/
/
ALTERNATE SHUTDOWN MINIMUM EQUIPMENT
///
Transfer Minimum Switch
/
I No Switches Equipment Location Function
/
/
I
\\
11 HS-0102A 1
C150 Control Room Alarm
/
/
12 HS-D102B 1
C150 S/G Level Indications
/
Pressurizer Level Indications
/
Aux. FW Flow Indication
/
Aux. FW Flow Control
/
/
13 HS-0522C C150 Opens Aux. FW Pump Steam
/
Valve CV-0522B
/
/
14 HS-0102C 1
C150A Control Room Alarm
/
S/G Pressure Indications
/
Hot / Cold Leg Temperature
/
Indications
/
/
/
/
Minimum Controls
/
No Contral Circuits Equipment From Function
/
/
15 Auxiliary FW Flow 1
C150 Controls B S/G
/
Control (HIC-07270)
Aux. FW Flow Control
/
Valve (CV-0727)
/
16 Auxiliary FW Flow 1
C150 Controls A S/G
/
Control (HIC-0749C)
Aux. FW Flow Control
/
Valve (CV-0749)
/
l l
I 1
i 3-136 Amendment No. 122 TSP 1185 0335 NLO4 l
l i
L
L. '
i
,4.20
' MODERATOR TEMPERATURE COEFFICIENT (MTC) l l
SURVEILLANCE REQUIREMENTS 4.20.1 The MTC shall be determined to be within its limits by confirmatory measurements prior to initial operation above 2%
of rated thermal power, after each refueling.
/
/
4-85 Amendment No. FS, JJf>, 122 TSP 1185 0335 NLO4
I
'4.21 ALTERNATE SHUTDOWN SYSTEM
/
/
SURVEILLANCE REQUIREMENTS
/
/
/
/
4.21.1 Each alternate shutdown monitoring instrumentation channel shall
/
be demonstrated OPERABLE by performing a channel check and a
/
channel calibration per Table 4.21.1.
/
/
4.21.2 Each alternate shutdown system transfer switch and control
/
circuit shall be demonstrated OPERABLE by operating each
/
activated component from the alternate shutdown panel, at least
/
once per refueling cycle.
/
4-86 Amendment No. E5, 122 TSP 1185 0335 NLO4
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