ML19329A566
| ML19329A566 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/07/1970 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001070563 | |
| Download: ML19329A566 (4) | |
Text
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I DEC 7 193 Peter A. Morris, Director Division of Reactor Licensing DUKE POWER COMPANY - OCONEE NUCLEAR STATION 1 DOCKET NO. 50-269 i
The enclosed review of the Technical Specifications for the Oconea Nuclear Station, concerns th operating limitations with respect to heatup and cooldown procedures for the reactor coolant system.
Our recommendations are based on the specified operating limitations as determined or limited fracture toughness data submitted by the applicant and are intended to apply for the initial two years of plant operation.
Original,igned by, E. G. Case
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gg) _ g (,/9 Edson G. Case, Director Division of Reactor Standards
Enclosure:
Review of the Technical Specifications for the Oconee Nuclear Station cc w/ encl.
S. H. Hanauer, DR R. S. Boyd, DRL
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.t DUKE POWER COMPANY - OCONEE NUCLEAR STATION DOCKET NO. 50-269 TECHNICAL SPECIFICATION - OPERATING LIMITS We have reviewed the recently proposed heatup and cooldown procedures for the Oconee Nuclear Station, Unit 1 (dated November 14, 1970), for compliance with the AEC fracture toughness c-iteria.
We find that:
1.
For the. first two years, the Oconee 1 reactor coolant system should be operated and hydrotested 4
k in such a manner that at temperatures below 275*F, (a) the pressure does not exceed 550 psig (i.e.,
25 percent of the normal operating pressure), and (b) the rate of temperature change does not exceed 50*F/hr.
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2.
Full pressurization of the reactor coolant system is acceptable during the first two years at temperatures above 275*F.
The above limits should be used as a basis for the Technical Specifications for the Oconee'P.lants and are shown in a dashed line on the. attached figure.. Our proposed. operating limits are intended to apply to both heatup and cooldown procedur'es.
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Our evaluation was based on the material fracture toughness I*f data furnished by B&W and on several, most likely conservative, assumptions.
These assumptions related primarily to the 4
adjustment of the Charpy V-notch data submitted by B&W and were necessary since these data do not include the I
Drop-Weight test results, weld material properties, or the j
i Charpy V-notch upper shelf levels.
Should'the applicant i
be able to demonstrate that the actual properties are i
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better than we have ass,umed, we can review the data and i
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recommend lower operating limits for the Oconee 1 plant.
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These limits will require review,- and probably revision, when the data is made available from the material surveillance
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program test results following the first capsule withdrawal.
We recommend additional testing of the reactor vessel belt-
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line materi~al~by means of Drop-Weight tests to establish the NDT temperature, and by Charpy V-notch specimens to establi,sh upper shelf levels.
We believe also that a surveillance program which includes transverse specimens may provide a 1
basis for the applicant to improve 'on our recommended oper-ating limits and to demonstrate compliance with. the AEC fracture toughness requirements for the operating periods;'
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beyond the first two. years.
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REACTOR COOLANT SYSTEM HEATUP LIMITATIONS i
INT.EGRATED EXPOSURE (APPLICABLE UP TO AN OF 1.7 x 1018 n/ c m2 ~ 0 R D T T - 144 'F)
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