ML20100H817

Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv

ML20100H817
Person / Time
Site:	Clinton
Issue date:	02/22/1996
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20100H804	List: ML20100H817 U-602551, Application for Amend to License NPF-62,changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv
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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-l UMIT 2co soGUP C - NUCLEAR CRmCAU 7o*F UMIT I

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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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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

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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.

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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

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..,--~- - ~

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

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1. 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

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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)

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B 3.4-53 Revision No. 1-1

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i CLINTON t

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. _. _ _ _ _ _ ____ _ _ _ _.._ _._= -

._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.

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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

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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.

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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)

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CLINTON.

B 3.4-58 Revision No. 1-1 i

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