ML19329A345
| ML19329A345 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/05/1974 |
| From: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001020921 | |
| Download: ML19329A345 (4) | |
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K. R. Coller, Assistant Director for Operating Reactors, L OCONEE UNIT 1 CLADDING COLLAPSE (TAR-1198) i Plant Name:
Oconee Unit 1 Docket No.:
50-269 Responsible Branch ORB-1 and Project Manager:
L. McDonough Technical Review Branch Involved: Core Performance Branch Requested Completion Date:
October 25, 1974
Reference:
Letter to A. Ciambusso, Reactor Projects from A. C. Thies, Duke Power Company, dated July 30, 1974 i
The subject letter requesting deleting of the 7500 EFFH creep collapse limit on Oconee 1 has been reviewed and a sununary of the evaluation is enclosed.
It is reconsnended that the 7500 EFFH limit be removed; operation with no expected collapse through cycle 3 is likely, subject to verification of the projected cycle 2 run schedule.
Original Signed hs:
Pdoc SteDe Victor Stello, Jr., Assistant Director for Reactor Safety Directorate of Licensing
Enclosure:
l Summary of I
Evaluation ec:
S. Hanauer F. Schroeder W. Mcdonald Distribution:[
D. Ross Docket files 4
L. Rubenstein CPB Reading N
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R. Purple L Ruainf Reading
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'r L. Mcbonough V. Stello
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S. Varga I'
E. Leins F. Coffman
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UNITED STATE 3 5
ATOMIC ENERGY COMMISSION 4
WASHINGTON, D.C. 20545 NOV 5 IW4 K. R. Coller, Assistant Director for Operating Reactors, L OCONEE UNIT 1 CLADDING COLLAPSE (TAR-1198)
Plant Name:
Oconec Unit 1 Docket No.:
50-269 Responsible Branch ORB-1 and Project Manager:
L. McDonough Technical Review Branch Involved: Core Performance Branch Requested Completion Date:
October 25, 1974
Reference:
Letter to A. Giambusso, Reactor Projects from A. C. Thies, Duke Power Company, dated July 30, 1974 The subject letter requesting deleting of the 7500 EFPH creep collapse limit on Oconee 1 has been reviewed and a summary of the evaluation is enclosed.
It is recommended that the 7500 EFPil limit be removed; operation with no expected collapse through cycle 3 is likely, subject to verification of the projected cycle 2 run schedule.
f:
Victor Stello, Jr.,' Assistant Director for Reactor Safety Directorate of Licensing
Enclosure:
Summary of Evaluation ec:
S. llanauer F. Schroeder W. Mcdonald D. Ross L. Rubenstein R, Purple L..McDonough S. Varga E. Leins F. Coffman J
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- OCONEE UNIT 1 CLADDING COLLAPSE _
b 07/30/74,which
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We have reviewed the Duke Power Company Letter of c"
requested deletion of the 7500 EFPH creep collapse limit (Tech This. change was based on calculations made using Specification 3.11).
the fuel vendor's' creep collapse analysis (II. The vendors analysis (2)
The fuel accepted for license applications with three provisions vendor's collapse calculations for Oconee 1 satisfy two of our three';
(a) the creep equation must appropriately characterize l
provisions:
the actual cladding material, (b) the initial ovality be no less tha[
The third provision is that of surveillance which requires inches.
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~ hat.the results of the long term inreactor confirmatory tests oI t
l times to observed cladding collapse continue to be favorable.
The surveillance requirement (Technical Specification, Appendif 4.13)(3) on Oconee 1 satisfies our requirement for specific confirm Comparable information w'll be available
-information on observed collapse.
through inspections performed on the Fuel Rod and Cladding S 3 -
II(4)
-Information from the Point Beach and H. B. Robinson The suggests cladding creep collapse could occur 'about 21000 EFPH in Oconee 1 but-
. fuel'in Point Beach and H. B. Robinson is similar to that
-not 'directly equivalent. -
- We have independently calculated a predicted time for cladding creep
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collapse'using the computer code BUCKLE (5)
BUCKLE.is conservatively
. biased. BUCKLE uses a generally descriptive creep rate equati EFPH for cycle 3 in Oconee 1.
20500
. predicts' cladding collapse at l
3
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The fuel vendor's cladding collapse analysis, CROV
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ifi-In contrast with BUCKLE, CROV uses creep rate equatio k
believed by the staff biased.
cally developed for Oconee. type fuel cladding and is
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il The CROV analysis
.to be more appropriate for B&W cladding mater a.
l, d the end of predicts cladding collapse times over three months beyon
,L Ec90sure of original fuel through the first-three cycle 3 in Oconee 1.
projected cycles is expected to be 21,500 EFPH.h cycle 3 be It is recommended that the 7500 EFPH limit on Oconee 1 th tion It is recommended both that the available confirmator' removed.
i h the from inreactor tests be re-evaluated to continue complian (2) and that the specific surveillance provision on the B&W analysis l l ted cladding operating history be used tc, precisely update the ca cu a l
2.
. collapse time at the completion of cyc e 1-g 3.
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Refereneg;et 7
t BAW-10084, " Program to Determine In-Reacter Performance of Tuels-Cladding Creep Collapse, CROV".
- 1.
B&W Let :.er from V. Stello to V, Moore, " A Ger_aric Review of the Cladding Creep Collapse Analysis Topical Report 2.
B&W BAU-10084 (TA3-970)", dated 8/9/74.
Secnion 4.13, Fuel Surveillance, Appendix A, Technical
~3 Spe cificati<c, Oconee Unit 1.
ysa3 Supplement 16, Oconce 2, dated July 1973 3
4, J. Pankas',:le, "BUCW, M.b@ i W D 5
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References BAW-10084, " Program to Determine In-Reactor Performance of 1.
B&W Fuels-Cladding Creep Collapse, CROV".
Letter from V. Stello to V. Moore, " A Generic Review of the 2.
B&W Cladding Creep Collapse Analysis Topical Report BAW-10084 (TAR-970)", dated 8/9/74.
Section 4.13, Fuel Surveillance, Appendix A, Technical 3
Specification, Oconec Unit 1.
FSAR Supplement 16, Oconce 2, dated July 1973 4.
P. J. Pankaskie, " BUCKLE", BNWL-1784, May 1974.
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