ML20210Q297
| ML20210Q297 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/21/1997 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20210Q294 | List: |
| References | |
| NUDOCS 9708290085 | |
| Download: ML20210Q297 (2) | |
Text
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i 2.0 SAFETY LIMITS LIMITING SAFETY SYSTEM SETTINGS 2.1 FUEL CIADDING INTEGRITY 2.3 FUEL CIADDING INTEGRITY Applicability Applicability Applies to the interrelated variables associated Applies to trip settings of the instruments and with fuel thermal behavior devices which are provided to prevent the reactor system safety' limits from being exceeded.
Objective:
Obiective:
To define the level of the process variables at To establish limits below which the integrity which automatic protective action is initiated to of the fuel cladding is preserved.
prevent the safety limits from being exceeded.
Specification:
Specification:
The Limiting safety system settings shall be as specified below:
A.
Core Thermal Power Limit (Reactor Pressure >800 psia and Core Flow is >10% of Rated)
A.
Neutron Flux Scram When the reactor pressure is >800 psia and core 1.
APRM - The APRM flux scram trip setting flow is >10% of rated, the existence of a shall be:
1.0@-
minimum critical power ratio (MCPR) less than a.
For two recirculation loop operation N for two recirculation loop operation, or (TLD):
less t 1-08'for single loop operation, shall S s 0.66V + 70%
where.
l~ g4 constitute violation of the fuel cladding S - Setting in percent of rated integrity safety limit.
thermal power, rated power being 1670 MWT V - Percent of the drive flow 4 %(fk x)du.c$ h o e cy ckt, kg %g
- required to produce a rated j
core flow of 57.6 x 10 lb/hr 6
b.
For single recirculation loop operation (SID):
S $ 0.58(W - 5.4) + 62%
c.
No greater than 1204.
2.1/2.3 6
REV 134 1/27/93
^
9708290085 970821 PDR ADOCK 05000263 P
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'O 2.0 SAFETY LIMETS LIMITING SAFETY SYSTEM SETTINGS
~
2.1 FUEL CLADDING INTECRITY 2.3 FUEL CIADDING INTERCRITY Applicability Applicability.
[
Applies to the interrelated variables associated Applies to trip settings of the instruments and with fuel thennal behavior.
devices which are provided to prevent the reactor.
system safety limits from being exceeded.
Obiective:
Obiective:
To establish limits below which the integrity To define the level of the process variables at of the fuel cladding is preserved.
which automatic protective action is initiated to prevent the safety limits from being exceeded.
Specification:
Specification:
A.
Core Thermal Power Limit (Reactor Pressure >800 The Limiting safety system settings shall be as psia and Core Flow is >10% of Rated) specified below:
When the reactor pressure is >800 psia and core A.
Neutron Flux Scram flow is >10% of rated, the existence of a 1.
APRM - The APRM flux scram trip setting minimum critical power ratio (MCPR) less than shall be:
1.08*, for two recirculation loop operation, or
- a. For two recirculation loop operation less than 1.09* for single loop operation, (TID):
shall constitute violation of the fuel cladding S $ 0.66W + 70%
integrity safety limit.
where S - Setting in percent of rated thermal power, rated power being 1670 MWT W - Percent of the drive flow required to produce a rated 6
core flow of 57.6 x 10 lb/hr b.
For single recirculation loop operation (SLO):
55 0.58(W - 5.4) + 62%
- MCPR values for cycle 18 only.
c.
No greater than 120%.
2.1/2.3 6
REV
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