ML20100H817
| ML20100H817 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/22/1996 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20100H804 | List: |
| References | |
| NUDOCS 9602280067 | |
| Download: ML20100H817 (5) | |
Text
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Attechment 3 to U-602551 S-95-015 Page 2 of 3 kEPLM WITT4 lt45ERT PAGd RCS P/T Limits 3.4.11 16 CURVE A evr.
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1 CURVES A. 8 Mao C ARE WLJo y
Fon 12 EFPY,OF OPERATION g Goo C
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212 ps4 A-HYDAoTEST UMIT WrTH IN VESSEL l
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-l UMIT 2co soGUP C - NUCLEAR CRmCAU 7o*F UMIT I
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' too 2o0 soo 4o0 soo soo MINIMUM REACTOR VESSEL METAL TEMPERATURE (*FI Figure 3.4.11-1 (page 1 of 1)
RCS Pressure Versus Minimum Reactor Vessel Metal Temperatu_re 9602280067 960222 PDR ADOCK 05000461 P
PDR CLINTON 3.4-32 Amendment No. 95
Attcchment 3 to U-602551 I
PS-95-015 Pega 3.of 3 RCS P/T Limits 3.4.11 1600
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CURVES A. 8 AND C ARE VAUD
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FOR 12 EFPY OF OPERATION z 600 g
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A - SYSTEM HYDROTEST UMIT 200 WITH FUEL IN VESSEL B - NON-NUCLEAR HEATING BOLTUP 70'F /
UMIT C - NUCLEAR (CORE CRITICAL) uuT 0
0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE fF)
Figure 3.4.11-1 (page 1 of 1)
RCS Pressure Versus Minimum Reactor Vessel Metal Temperat_ure CLINTON 3.4-32 AmendmentNo.jHI
1 to U-602551 PS-95-015 Page1 of3 i
4 Technical Specification Bases Changes a
'l ep
Attechnent'4 to U-602551 PS-95-015 Pege 2 of 3 RCS P/T Limits B 3.4.11 B 3.4 REACTOR COOLANT SYSTEM (RCS) 4
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l 8 3.4.11 ACS Pressure and Temperature (P/T) Limits j
BASES i
.BACKG D
All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and. temperature In aM4ioS C.,w A changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and l
" 4 " '*f*"* k reactor trips. This LCO limits the pressure and temperature i
P/T lim;& curve.4c changes during RCS heatup and cooldown, within the design M reac h g o assumptions and the stress limits for cyclic operation.
I J
VM 66 W Figure 3.4.11-1 contains P/T limit curves for heatup, m
b" 0" i.'.YS" hand}ns g_gn3 e pg, j
---v
..,--~- - ~
- 1. m.n are r.-- n--
g,,y gy y3 d ': valid for 12 Effective Full Power Years (EFN) of Curyes 8 and C are based'on core beltline 4
leak.hdgr.dAc operation.
conditions with an assumed 130*F shift from an initial weld i
p,,%,,43' 4 d RTuor of -30*F.
Curve A includes beltline adjusted bb W 4c yeakmei reference temperatures (ARTS) of 58*F for 4 EFPY, 88'F for 8 i-l may be. ede 4 y EFPY, and 100*F for 12 EFPY. 9 j
k d*" *E*N Each P/T limit curve defines an acceptable region for normal l
I-
- A *5$*A IN operation. The usual use of the curves is operational l
%cMo., p.,=es guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and m e. ei % e y.,
.porg;3 g gM compared to the applicable curve to determine that operation is within the allowable region.
W hpo% 44 The LC0 establishes operating limits that provide a margin AWgg to brittle failure of the reactor vessel and piping of the 4
i used b eae.
reactor coolant pressure. boundary (RCPB). The vessel is the l
(*
P A Q, component most subject to brittle failure. Therefore, the i
j LCO limits apply mainly to the vessel.
10 CFR 50, Appendix G (Ref.1), requires the establishment of P/T. limits for material fracture toughness requirements of the RCPB materials. Reference 1 requires an. adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic l
tests.
It mandates the use of the American Society of Mechanical Engineers (ASME) Code,Section III, Appendix G (Ref. 2).
(continued)
I i
i i
B 3.4-53 Revision No. 1-1
)
i CLINTON t
d
. _. _ _ _ _ _ ____ _ _ _ _.._ _._= -
._m Attechnent'4 to U-602551 4
PS-95-015 i
Page 3 of 3-RCS P/T Linits.
B 3.4.11 BASES 5
ACTIONS C.1 and C.2
. 1 (continued) i Operation outside the P/T lir.its in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so f
i that the RCPB is returned to a condition that has.been verified by stress analyses. The Required Action must be-initiated without delay and continued until the limits are restored.
I Besides restoring the P/T limit parameters to within limits, an evaluation is required to determine if RCS operation is allowed. This evaluation must verify that the RCPB l
integrity is acceptable and must be completed before i
approaching criticality or heating up to > 200*F.
Several i
methods may be used, including comparison with pre-analyzed -
l transients, new analyses, or inspection of the components.
l ASME Section XI, Appendix E-(Ref. 6), may be used to support i
the evaluation; however, its use is restricted to evaluation j
of the beltline.
i f
SURVEILLANCE SR 3.4.11.1 j
REQUIREMENTS RCS temperature conditions are determined by measuring the metal temperature of the rea or vessel flange surfaces, j
bot * = head ou_tside surfa ttos_ head
_ surface j
((verifickt. ion 7nat operauon 1s wir.nin 11mlts 7s requirMas me l.
every 30 minutes when RCS pressure and temperature
'h.,= p
]
conditions are undergoing planned changes. This Frequenc 4
is considered reasonable in view of the control roon i
indication available to monitor RCS status. Also, since l
temperature rate of change limits are specified in hourly increments, 30 minutes permits assessment and correction of 4
l minor deviations.
i i
i i
Surveillance for heatup, cooldown, or inservice leakage and hydrostatic testing may be discontinued when the criteria l
given in the relevant plant procedure for ending the 4
activity are satisfied.
This SR has been modified by a Note that requires this Surveillance to be performed only during system heatup and cooldown operations and inservice leakage and hydrostatic
. testing.
I (continued)
~
d i
CLINTON.
B 3.4-58 Revision No. 1-1 i
.