ML19319B031
| ML19319B031 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/29/1977 |
| From: | Shao L Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001060034 | |
| Download: ML19319B031 (2) | |
Text
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AUG 2 91977 i
I MEMORANDUM FOR:
K. R. Goller, Assistant Director for Operating Reactors, j
Division of. Operating Reachrs FROM:
L. C. Shao, Chief. Engineering Branch, Division of i
.0perating Reactors
,e i
SUBJECT:
OCOMBE, UNITS 1, 2 AND 3--REVIEW OF PRESSURE-TEMPERATURE i
OPERATING LIMITS, TAC 6980
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k Plant Name: Oconee, Units 1, 2 and 3 i
Docket Numbers: 50-269/270/287 J
HSSS Vendor:.B&W I
Responsible Branch and Project Manager: ORB 1, J. Neighbors f
Requested Completion Date: September 1, 1977 Tee.hnical Review Branch; Engineering Branch Review Status: Complete i
i In a letter dated June 6,1977, Duke Power Company submitted an amendment to Technical Specification 3.1.2 " Pressurization. Heatup, and Cooldown Limitations," for Oconee, Units 1, 2 and 3.
The pressure-temperature operating limits forSc60ehre proposed for operation through 4 EFPY for 18 Unit 1 for Unit 2 through 6 EFPY, and for Unit 3 to a fluence of 1.7 X 10 l
n/cm2 or a DTT of 1440F.
l Estimations of fluences on the vessel wall ID for Oconee, Units 1 and 2 at the vessel wall ID is calculated to be 1.7 X 10ge end of life fluence are based on dosimeter readings. For these units
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n/cm.
For Unit 3 i
the end of life fluence used for calcu: ting the operating limits is the design value from the FSAR of 3.0 X 10 n/cd.
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The pressure-temperatuee operating limits are based on data from i
surveillance capsule F from Unit 1 and capsule C from Unit 2.
Capsule F i
contained no weld material; and-since weld material is the limiting material, the data from this capsule has limited applicability. However, capsule C contained specimens of weld metal WF 209-1. This material has j
s copper content of 0.34% and a phosphorus content of 0.0135.
It is not identical to any of the wilds in the reactor Vessels of Oconee, Units 1 2 or 3.
However, we feel that since this weld has a chemical composition j
and used weld procedures similar to those for high copper Oconee vessel welds, this surveillance weld material will have irradiated mechanical properties representative of the limiting weld metals.in the Oconee rgactor vessels. - Capsule C speciments received a fluence of 9.43 X 1017 n/cm.
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This irradiation produced an in:rease in RTNDT of 1200F. at 50 ftvlbs.
y and a dmp in upper shelf Charpy energy from 68 to 54 ft.-1bs. for the WF 209-1 weld metal specimens.,
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i' We have reviewed the pressure-tegerature operating limits proposed for t
Oconee Units 1. 2 and 3._ We conclude that the operating limits for Unit 1 ane in confomance with Appendix G.10 CFR Part 50 and are acceptable for operation thmugh A EFPY. The pressure-temperature
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operating limits proposed for Unit 2 are essentially the same as those h-for Unit 1.
Since the neutron flux and spectrum, and the weld material mechanical properties for Units 1 and 2 are expected to be similar, we a
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feel that the operating limits for Unit 2 should be applicable for y
operation thmugh 4 EFPY instead.of 6 EFPY. The pmssure-temperature optbating limits for Unit 3 are proposed for operation through 1.7 X i
10' n/cm2 Based on the design value for fluence on the vessel wall l
i ID at end of life of 3 X 1019 n/cm2. this fluence value is expected to
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be reached in 2 EFPY..Since the design fluence value is about 50%
y higher than.that caloolated for Units 1:and 2, we exget that the-fluence t-on the Unit.3 reactor vessel will not reach 1.7 X 10 until after 2 EFPY.
Y However, we feel that the proposed pressure-temperature operating limits d[j for Unit 3 shuuld be applicable for operation only through 2 EFPY. At that time, fluence predictions can be made based on dosimeter readings.
If the fluence calculations based on dosimeter readings are lower than those obtained from the design fluence value. Duke Power Company can r
5 then request that the.use of these operating limits be extended for an appropriate time. period.
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In view of the above. Technical Specification 3.1.2.6 should be changed to read "four! for Unit 2 and "two" for Unit 3. and the titles for Figs.
p 3.1.2-1B, 3.1.2-1C, 3.1.2-28 and 3.1.2-2C should be changed accordingly.
4 With these changes, the pressure-temperature operating limits proposed P
for Oconee. Units 1. 2 and 3 am acceptable and confom with Appendix
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' G.10 CFR Part 50. Conformance with Appendix G.10 CFR Part 50 in
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establishing safe operating limitations will ensure adequate safety i
margins during operation, testing, maintenance and postulated accident conditions and constitute an' acceptable basis for satisfying the mquirements
.of NRC General Design Criterion 31. Appendix A.10 CFR Part 50.
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