Text

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;
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	NUDOCS 9602280067
	Download: ML20100H817 (5)
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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 , ,

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1 E l E

1 y CURVES A. 8 Mao C ARE WLJo

- Fon 12 EFPY,OF OPERATION g Goo C

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212 ps4 A- HYDAoTEST UMIT WrTH IN VESSEL l HEmmo e - now

-l 2co - UMIT

soGUP C - NUCLEAR CRmCAU 7o*F UMIT I I I I I i o soo o- ' too 2o0 soo 4o0 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

I Attcchment 3 to U-602551 PS-95-015 Pega 3.of 3 RCS P/T Limits 3.4.11 1600 WW

g. ,Ei ,i2 B C 1400 i j [i i i I I

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1200 ---

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W m 800 I) 7

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? I Y o I i _.

b

[ [ CURVES A. 8 AND C ARE VAUD z 600

/ / FOR 12 EFPY OF OPERATION g j l t- f i 2

a r /

j to / 1 m 400 m

in (D 312 PSC

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A - SYSTEM HYDROTEST UMIT 200 WITH FUEL IN VESSEL BOLTUP ! B - NON-NUCLEAR HEATING 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 Attachment 4 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

~

l 8 3.4.11 ACS Pressure and Temperature (P/T) Limits j

$ BASES i All components of the RCS are designed to withstand effects l

.BACKG D '

of cyclic loads due to system pressure and. temperature .

$ In aM4ioS C.,w A changes. These loads are introduced by startup (heatup) and l shutdown (cooldown) operations, power transients, and

" 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 assumptions and the stress limits for cyclic operation.

M reac h g o m I J VM 66 W Figure 3.4.11-1 contains P/T limit curves for heatup, e pg,

"# b" 0" g_gn3 j g,,y gy y3 i.'.YS"

. ---,. --. hand}ns

- r.-- n-- - --..- ---v .. ,--~- - ~ 1. m .n are d ': valid for 12 Effective Full Power Years (EFN) of Curyes 8 and C are based'on core beltline leak.hdgr.dAc operation.

4

, i

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 j l may be. ede 4 y EFPY, and 100*F for 12 EFPY. 9 d*" *E*N Each P/T limit curve defines an acceptable region for normal l k !

I- # A *5$*A IN operation. The usual use of the curves is operational

%cMo., p.,=es guidance during heatup or cooldown maneuvering, when l pressure and temperature indications are monitored and

m e. ei % e y ., compared to the applicable curve to determine that operation

.porg;3 g gM is within the allowable region.

W hpo% 44 The LC0 establishes operating limits that provide a margin ;

4 AWgg to brittle failure of the reactor vessel and piping of the ;

i

(* used b P eae.

reactor coolant pressure. boundary (RCPB). The vessel is the l' component most subject to brittle failure. Therefore, the i

. A Q, LCO limits apply mainly to the vessel. ,

j !

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 Revision No. 1-1 i

CLINTON - B 3.4-53 )

t d

_ _ _ . _ . ___. . _ . . _ _ .. . _. _ _ _ _ _ ____ _ _ _ _ .._ _._= - ._m ,

4 Attechnent'4 to U-602551 ;

i

PS-95-015 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, i and 3 (including defueled conditions) must be corrected so f 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 i integrity is acceptable and must be completed before 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 the evaluation; however, its use is restricted to evaluation i

j of the beltline.

i SURVEILLANCE SR 3.4.11.1 ,

f ,

j REQUIREMENTS ;

RCS temperature conditions are determined by measuring the j

' metal temperature of the rea or vessel flange surfaces, ttos_ head _ surface j bot * = head ou_tside surfa !

l. ((verifickt. ion 7nat operauon 1s wir.nin 11mlts 7s requirMas me -

every 30 minutes when RCS pressure and temperature 'h.,= p l

]

4 conditions are undergoing planned changes. This Frequenc is considered reasonable in view of the control roon l i

indication available to monitor RCS status. Also, since l l

temperature rate of change limits are specified in hourly 4 increments, 30 minutes permits assessment and correction of l minor deviations. i i

i i Surveillance for heatup, cooldown, or inservice leakage and .

hydrostatic testing may be discontinued when the criteria l l

4 given in the relevant plant procedure for ending the 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

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ML20100H817

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