ML20126F114

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Proposed Tech Spec 3.4,Pages 3-5 & 3-6,re Combined Heatup, Cooldown & Pressure Limitations,Updating Pressure/Temp Limit Curves for Hydrostatic & Leak Testing & for Heatup & Cooldown Rates
ML20126F114
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 06/30/1985
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20126F101 List:
References
NUDOCS 8506170354
Download: ML20126F114 (6)
v • d • e


Text

n:

Docket No. 50-213

-Attachment 1 Haddam Neck Plant Proposed Revision to Technical Specifications F_igures 3.4-1, 3.4-6, and 3.4-7 Pages 3-5 and 3-6 D

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~ U February 27, 1978

^

3 J3.4 - C0ftSINED llEATUP C00LDOWN'AND PRESSURE LIl11TATIONS s.

. Applicability: ' Applies.to pressure and. temperature conditions du' ring heatup, cooldown, hydrostatic and leak testing of the reactor coolant 4

system.-

Objective:

~To naintain operational limits within allowable design limits of.the reactor coolant system.

Specifications:

A.

REACTOR VESSEL 1.

The reactor coolant system pressure and temperature relationship to be applied for hydrostatic and leak testing shall be maintained within~ limits as shown in Figure 3.4-1.

2.

The reactor coolant system temperature, pressure and' system heatup and cooldown rates shall be maintained within limits as shown in Figures 3.4-2 through 3.4-9,for the specified service period.

- 3.

The average rate of reactor coolant temperature change during normal heatup or cooldown shall not exceed 100*F/hr when averaged over a

one-hour period.

-4.

Allowahle combinations' of' pressure and temperature fo: specific temperature change rates are below and to the right of the limit curves (labelled operating zcne) as shown in Figures 3.4-2 through 3.4-9.

B.

PRESSURIZER

~ 1.- The pressurizer shall not be pressurized above 500 psig unless the temperature of the pressurizer is above 70*F.

U

'2.

.The pressurizer heatup rate shall not exceed 100 F/hr.

25 0

3.

The pressurizer cooldown rate shall not exceed 200 F/hr.

4.

The temperature difference between the pressurizer and the reactor coolant system shall not exceed 200'F.,

C.

STEAM GENERATORS 1.

The primary side of the steam generators shall not be pressurized above 500 psig unless the temperature of the reactor coolant system is above.70*F.

2.

The maximum heatup and cooldown rate for the steam generators shall not exceed 100'F/hi.-

3.

The temperature difference across the tube, sheet shall not exceed 100'F.

4.

The secondary side of the steam generators must not be pressurized above 200 psig if the temperature of the vessel is below 70*F.

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~

Basis:

The clicvablo'.Pr:ssure-ta=parsturo r:1stionships fer th3 specified hestup and cooldown' rates of.the reactor coolant system were calculated in accordance with Appendix C in Section III of the ASE Boiler and Pressure Vessel Code. The mini =um full pressurization limits to be applied during hydro-static and leak testing of the reactor coolant system were de-rived in accordance with ' Appendix C to ASE III.

The system leakage test and system by-

  • drostatic test pressure limitations are based on paragraph 15-522 of the k' inter 1972 Addenda to ASE Section II.

The total stress of a ' component in the reactor coolant system is the co=bined stress caused by internal pressure and by ther=al gradients. The Appendix G approach specifies that the allowable total stress intensity factor (K I) at any ti=e during heatup and cooldovn cannot be greater than that shown on the KIR curve (Ref erence 1) for the metal ta=perature at that ti=e.

The derived operating li=it curves (Tigures 3.4-2 through 3.4-9) contain explicit safety factors of 2.0 and-1.25 (addit-ienal conservatism above code requirements) on stress intensity f actors induced by pressure and te=perature gradients, respectively.

A11ovable pressure te=perature relationships for both steady-state and finite heatup and cooldovn rates were generated assu ing the presence of code reference 1/4 7 deep flav at either the ID or OD of the reactor vessel. Tinally, a ec=posite cu:ve was constructed based on a point-by-point co:parisen of the ste.ady state and finite heatup and cooldown data. At any given te=perature, the allevable pressure is taken to be the lesser of the two values C

taken fro: the curves under consideration. The ec=posite cu:ve vas then adjusted to allev fer pessible errors in the pressure and temperature sensing instruments.

The criticality limit is defined as the mini =u: full pressurization te=perature plus I.007 when reactor is critical.

The bestup, cocidown and hydrostatic and leak testing operating li=its vere based on the adjusted trend curve (Reference 2),

derived from surveillance Capsule A and T results. The projected GT shif t vill be verified periodically by the reactor vessel RT surveillance program.

The heatup and cooldoen rates of 200 T/hr of the pressurizer and 0

i 200 F/hr for heatup and cooldown of the steam generators are C

specified since they are both design limits to maintain stresses in these vessels within acceptable design 11=1ts.

A temperature difference of 2000T between the pressurizer and reactor coolant system is specified to maintain therr.a1 stresses

~

within the surge line below design limits.

Temperature requirements for pressurization of the pressurizer and steam generators correspond with DIT measured for each c.aterial of each' component.

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