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NUCLEAR REGULATORY COMMisstON f
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MAR 12 1984 MEMORANDUM FOR:
R. Wayne Houston, Assistant Director j
for Reactor Safety Division of Systems Integration FROM:
Brian W. Sheron, Chief Reactor Systems Branch Division of Systems Integration
SUBJECT:
GRAND GULF UNIT 1 TECHNICAL SPECIFICATIONS l
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Reactor Systems Branch'has reviewdd the Grand Gulf Technical Specifications j
revised thr'ou'gh Amendment 12.
Enclocure 1 lists the sections which we i
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reviewed. provides our comments.
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Brian W. Sheron, Chief Reactor Systems Branch Division of Systems Integration
Enclosures:
As stated cc:
D. Hoffman RSB Section B Members R. Mattson R. Capra
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ENCLOSURE 1 TECHNICAL SPECIFIC TIONS, BASES AND.DEF.INI,UDNS. REVIEWED BY THE REACTOR SYSTEMS BRANCH FOR GRAND GULF UNIT 1 i
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Definition
- 1. 3.
Average Planar Linear Heat Generation Rate 1.8 Critical Power Ratio 1.12 Emergency Core Cooling System (ECCS) Response Time 1.13 End-of-Cycle Recirculation Pump Trip System Response Time 1.21 Linear' Heat Generation Rate 1.24 Minimum Critical Power Ratio II.
Safet'y Limits and Limiting Safety System Settines 3
2.1.1 Thermal Power, Low Pressure or low Flow 2.1. 2-Thermal Power, High Pressure and High Flow 2.1. 3 Reactor Coolant System Pressure 2.1.4 Reactor Vessel Water Level 2.2.1 Reactor Protection System Instrumentation Setpoints III.
Limitine Conditions for Ooeration and Surveillance Recuriements 3 / q.2.i nuv-w mov Liw w e w, - G m m ~ u s.
3/4.2.2 APRM Setpoints 3/4.2.3 Minimum Critical Power Ratio 3/4.3.1 Reactor Protection System Instrumentation 3/4.3.2 Isolation Actuation Instrumentation 3/4.3.3 Emergency Core Cooling System Actuation Instrumentation 3/4.3.4 Recirculation Pump Trip Actuation Instrumentation /ATWS Recirculation Pump Trip System Instrumentation 3/4.3.5 Reactor Core Isolation Cooling System Actuation l_
Instrumentation l
3/4.3.7.4 Remote Shutdown Monitoring Instrumentation l
3/4.3.7.5 Accident Monitoring Instrumentation l
i 3/4.3.8 Plant Systems Actuation Instrumentation I
3/4.4.1 Recirculation System 3/4.4.2-Safety Valves 3/4.4.6.2 Reactor Steam Dome 3/4.4.7 Main Steam Isolation Valves 3/4.4.9 Residual Heat Removal 3/4.5 Emergency Core Cooling System 3/4.7.3 Reactor Core Isolation Cooling Refueling Operations; Water Lev, System 3/4.9.8 el - Reactor Vessel 3/4.9.11 Refueling Operation; Residual Heat Removal and Coolant Circulation 3/4.10.4 Special Test Exceptions; Recirculatior. Loops s.4 6 c, v C..t.,.. r sw,m IV.
Bases Bases for all the areas identified in Sections II and III above.
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ENCLOSURE 2 COMMENTS ON GRAND GULF UNIT 1 TECHNICAL SPECIFICATIONS I
1) 2.2.1 Reactor Protection Systen Instrumentation Setooints Table 2.2.1-1 Item 3, "R'eactor' Vessei Steam Ooine' Pressure-High;" The allowable value should be less than or equal to 1045 psig (Reference page.5-5 of the SER).
2)
Ba'ses 2.1.2 Thermal Power, High Pressure and High Flow The la'st' paragraph of the text lists a GE report number as NED0-203040~. The correct report number is NED0-20340.
3) 3.4.2.2 APRM Setcoints The time ' constant for the thermal power monitor needs to be included in the LCO's and surveillance requirements.
(Reference page 15-4 of Grand Gulf SER).
4) 3/4.3.3 Emergency Core Cooling System Actuation Instrumentation 1.
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Table 3.3.3-2 item B.2.e "LPCI Pump B and C Discharge Pressure -
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High" should have the same allowable value as item A.2.f "LPCI Pump A Discharge Pressure - High" which is 115-135 psig, increasing.
2.
Table 3.3.3-3 " Emergency Core Cooling System Response Times" gives the LPCI A & B Pump response time as < 45 seconds.
Table 6.3-1 of the FSAR states that LPCI rated flow is achieved in < 40 seconds for the DBA analysis. The specifi-cation should be changed to read < 40 seconds.
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