ML19329A178

Provides Review of Pressure Temp Operating Limits Proposed 751001 by Util.Proposed Tech Specs Acceptable,Except for Two Discrepancies

ML19329A178
Person / Time
Site:	Oconee
Issue date:	01/06/1977
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Goller K Office of Nuclear Reactor Regulation
References
NUDOCS 7912300205
Download: ML19329A178 (2)

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i JAN 6N MEMORANDUM FOR:

K. R. Goller, Assistant Director for OR, D0R FROM:

D. Eisenhut. Assistant Director for OT, D0R

SUBJECT:

l OCONEE, UNITS 1, 2 AND 3 - REVIEW 0F PRESSURE-TEMPERATURE OPERATING LIMITS TAR ORB-1-195 Plant Name: Oconee, Units 1, 2 and 3 Docket Numbers: 50-269/270/287 Responsible Branch and Project Manager: ORB 1, J. Neighbors Requested Completion Date: December 30, 1976 l

Technical Review Branch: Engineering Branch Review Status: Complete i

In letter dated October 1,1975. Duke Power Company submitted a propo amendment to Technical Specification 3.1.2, " Pressurization, Heatup and Cooldown Limitations," for Oconee, Units 1. 2 and 3.

I The revised pressure-temperature operating limits were based on data from capsule OCl-F.

This data is reported in BAW-1421 Rev.1 dated September 1975.

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Capsule OCl-F contained specimens from base. HA{7andcgrrela (heat A119501) and received a fluence of 8.3x10 base material were machined in both the transverse a/cm. Specimens of n

nd longitudinal j

directions.

specimens (transverse direction) is 114 ft-lbs.The upper shelf Ch We have reviewed BAW-1421, Rev. I and the proposed pressure-temperat operating limits.

value since the fluence was low and there were no weld s the capsule.

and its specimens have been tested.A second capsule was pulled from i

This capsule contained weld We should receive the report on this capsule in early 19 i

The pressure-temperature operating limit curves F i

through SEFPY.

In view of the limited date available on Oconee, Unit 1 l

4 EFPY in lieu of 5 EFPY. vessel welds, we recommend that the prop t

This recomendation is based on preducted adjustments to reference temperature obtained from Regulatory Guide 1 The pressure-temperature operating limit curves Figs. 3.1.2-1B, 3.1.2-3 I

and 3.1.2-3, for Oconee,18 n/cm2 Units 2 and 3, were celculated for to a fluence of 1.7 X 10 similar to that in Fig. 3.1.2-1A.that Fig. 3.1.2-1B should be

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, For all three units, a criticality specification should be added to Specification 3.1.2.1.

Acceptable wording for this specification is:

i "When the core is critical (except for low power physics tests) the vessel temperature shell be no less tahn the temperature indicated on the criticaltty curve in Fig. 3.1.2-1 A."

Except for the above two discrepancies the proposed Technical Specification 3.1.2 conforms to Appendix G,10 CFR Part 50 and is acceptable. The i

use of Appendix G in establishing safe operating limitations will ensure adequate safety margins during operation, testing, maintenance and l

postulated accident nonditions and constitute and acceptable basis i

for satisfying the requirements of HRC General Design Criterion 31, Appendix A,10 CFR 50.

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D. G. Eisenhut, Assistant Director for Operational Technology Division of Operating Reactors i

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