ML20126F114

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: B11564, Application for Amend to License DPR-61,revising Tech Spec 3.4 Re Combined Heatup,Cooldown & Pressure Limitations to Update Pressure/Temp Limit Curves for Hydrostatic & Leak Testing & for Heatup & Cooldown Rates.Fee Paid ML20126F114
References
NUDOCS 8506170354
Download: ML20126F114 (6)

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

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3 .

J3.4 - C0ftSINED llEATUP C00LDOWN'AND PRESSURE LIl11TATIONS ,

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

. '2. .The pressurizer heatup rate shall not exceed 100UF/hr. 25

3. The pressurizer cooldown rate shall not exceed 2000 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 taken fro: the curves under consideration. The ec=posite cu:ve .

C 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 RT GT shif t vill be verified periodically by the reactor vessel surveillance program.

0 i

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

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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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