ML17212A389
| ML17212A389 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/06/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| Shared Package | |
| ML17212A390 | List: |
| References | |
| NUDOCS 8107220445 | |
| Download: ML17212A389 (7) | |
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$0 JUL P6 198t Docket Ho. 50-335 Dr. Robert E. Uhrig Vice President Advanced Systems 8 Technology Florida Power 5 Light Company P.
O. Box 529100 Miami, Florida 33152
Dear Dr. Uhr ig:
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SUBJECT:
CONTROL ELEMEhlT ASSEMBLY (CEA) GUIDE TUBE lJEAR AT ST.
LUCIE UhlIT WO.
1 As an interim fix for the fretting wear of the relatively soft Zircaloy-4 guide tubes for the control element assemblies (CEAs) by the harder Inconnel-625 cladding on the CEAs, you and other licensees of Combustion Engineering (CE) designed facilities have been instal.ling stainl'ess steel sleeves to improve the wear characteristics of these guide tubes.
Extensive post 3rradiation testing (ECT, visual, etc.) results from all the affected facilities have been reported.
Based on these reports we have concluded that NRC approved guide tube sleeves of the CE design are satisfactory for mitigating further fretting wear in irradiated or fresh fuel assemblies.
In addition, recent inspections of CEAs revealed insignificant fretting wear to the CEA cladding.
Although we are aware that CE is continuing to search for a "permanent"
, fix, e.g. possibly reduce guide tube flow or make modifications to the shroud flow path, we believe it is time to accept the sleeving of guide tubes as a solution to the wear problem.
Acceptance of sleeving the CEA guide tubes with CE sleeve design and installation procedures pr oven by test results would r educe the analyses required for a refueling application and possibly could allow core reloads under the provisions of 10 CFR 50.59. It would also ~educe the hJRC staff resources commit-ment to core reload reviews.
However, to achieve such a reduction in your required analyses and in our review effort, we find it necessary to control the guide tube sleeving operation with appropriate Technical Specifications (TS).
8107220445 8 i070bj, PDR ADQCK 05000335';
PDR JUL 28 t98t OFFICE/
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NRG FOAM 318 (10-80) NRCM 0240 0 FFlC IAL R E COB D COPY VSGPO: 1981~0960
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50 +5 You are, therefore, requested to propose changes to the Design Features section of the TS (Section 5 of the Standard TS) along with your next core reload amendment application or at least 90 days before reactor shutdown for a refueling outage performed under 10 CFR 50.59.
A sample
'S change page is enclosed for your use.
I He appreciate yourr esponsiveriess in dealing with.the entire CEA guide tube wear issue.
Enclosure:
CE-STS page 5-4 Sincer ely, Oripinai signed by Robert < Clark Robert A. Clark, Chief Operating Reactors Branch 03 Diyision of.Licensing cc:
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Florida Power
& Light Company CC:
Robert Lowenstein, Esquire Lowenstein,
- Newman, Reis
& Alexrad 1025 Connecticut Avenue, N.W.
Washington, D. C.
20036 Norman A. Coll, Esquire McCarthy, Steel, Hector
& Davis 14th Floor, First National Bank Building Miami Florida 33131 Indian River Junior College Library 3209 Virginia Avenue Fort Pierce, Florida 33450 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 U.S. Environmental Protection Agency Region IV Office ATTN:
E IS COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
4853 Cordell Avenue, Suite A-1
- Bethesda, Maryland 20014 Mr. Jack Schreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector/St.
Lucie Nuclear Power Station c/o U.S.N.R.C, P. 0.
Box 400 Jensen Beach, Florida 33457 Bureau of Intergovernmental Relations 660 Apalachee Parkway Tallahassee,.Florida 32304
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nESIGH FEATURES 5.3 REACTOR CORE FUEL ASS EHBLIES 5.3.1 The reactor core shall contain fuel assemblies with each fuel assembly containing fuel rods clad with (Zircaloy-4).,
Each fuel rod shall have a nominal active fuel length of inches and contain a
maximum total weight, of gr ams uranium.
The ini ideal core loading shall have a maximum enrichment~oi weight percent U 235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a
maximum enrichment of weight percent U-235.
5.'3.2 Except for soecial tes+
as authorized by the HPC, all fuel assemblies under control element assemblies shall be sleeved with a sleeve design previously approved by the HRC.
CONTROL ELBlEHT ASSENBLIES 5.3.3 The reactor core shall contain full length and part length control element assemblies.
REACTOR COOLANT SYSTBl OESiGN PRESSURE AND TEHPERATURE 5.4.1 The reactor coo1ant systan is designed and shall be maintained:
a.
b.
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in accordance with the code requirements specified in Section (5.2) of the FSAR with allowance or normal degradation pursuant o
the applicable Surveillance Requir ements, For a pressure of
- psia, and N
For a temperature of
'F, except for the pressurizer which is oF CE-STS
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