ML20023B463
| ML20023B463 | |
| Person / Time | |
|---|---|
| Issue date: | 04/15/1983 |
| From: | Barnes I, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20023B462 | List: |
| References | |
| REF-QA-99900401 NUDOCS 8305050097 | |
| Download: ML20023B463 (6) | |
Text
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' ORGANIZATION: COMBUSTION ENGINEERING, INCORPORATED POWER SYSTEMS GROUP UTNn90R rnNNF'TTrflT REPORT INSPECTION INSPECTION N0.:
99900401/83-01 DATE(S) 3/8-10/83 ON-SITE HOURS:
12 CORRESPONDENCE ADDRESS:
Combustion Engineering, Incorporated Power Systems Group ATTN: Mr. M. R. Etheridge, Vice Pres., General Services 1000 Prospect Hill Road Windsor, Connecticut 06095 ORGANIZATIONAL CONTACT: Mr. C. W. Hoffman, Group QA Director TELEPHONE NUMBER:
(203) 688-1911 PRINCIPAL PRODUCT:
Nuclear steam supply systems.
NUCLEAR INDUSTRY ACTIVITY:
The Power Systems Group of Combustion Engineering (CE) has contracts for 22 of the domestic reactor units to date, of which 14 are in the design and construction phase.
In addition, they have modification / repair /
service contracts for 22 reactor units, i
l l
ASSIGNED INSPECTOR:
b.
s/O
/[2/83 l
W. M. McNeill, R'eactive and Component Program Date l
Section (R& CPS)
OTHER INSPECTOR (S):
APPROVED BY:
[ Mw 4/6' cDi' I. Barnes, Chief, R& CPS Date 1
INSPECTION BASES AND SCOPE:
A.
BASES: Topical Report CENPD-210-A, Revision 3, and 10 CFR Part 21.
B.
SCOPE: Status of previous inspection findings.
l PLANT SITE APPLICABILITY:
Shoulder gap problem 368, 528, 361, 583, 382.
DESIGNATED ORIGINAL B305050097 830419 Ohf jpg WW U
ORGANIZATION:
COMBUSTION ENGINEERING, INCORPORATED POWER S" STEMS GROUP WINDSOR, CONNECTICUT iREPORT INSPECTION N0.:
99900401/83-01 RESULTS:
PAGE 2 of 3 A.
VIOLATIONS:
Noce B.
NONCONFORMANCES:
None C.
UNRESOLVED ITEMS:
None D.
STATUS OF PREVIOUS INSPECTION FINDINGS:
(Closed) Nonconformance (82-04): The shoulder gap modification of Batch C assemblies for Arkansas Nuclear One, Unit 2, was not accomplished with the implementation of the design change procedure as evidenced by:
(1) a Field Action Request was not issued to document the problem and its solution; and (2) no documentation was available which would indicate that a review had been performed in regard to:
(a) determination of the cause and corrective action, (b) applicability to other projects, and (c) determination if changes are required to the design process to prevent similar deficiencies.
The records of training of design personnel as corrective action in regard to Field Action Requests were reviewed. The references in the CE corrective action response letter dated January 20, 1983, were i
reviewed. The first three of these nine references had been made avail-able to the NRC inspector previously.
Two of these references had not been made available and four had not been issued at the time of the previous inspection.
Collectively, they document the shoulder gap problem, its solution, and the cause and corrective action.
In summary, the cause of the problem has been identified as the under prediction of rod growth and the over prediction of guide tube growth.
The corrective action being implemented is to add sleeves to the guide tubes which enlarges the fuel rod to upper end fitting gap. These references identify that their problem is applicable to Palo Verde Nuclear Stacion, Unit 1; St. Lucie Plant, Unit 2; San Onofre Nuclear Station, Unit 2; and Waterford Generating Station, Unit 3.
i Modifications have been made to all St. Lucie, Unit 2, Batch C fuel assemblies and 16 Batch B fuel assemblies. Modifications have also been made for all Batch C and 28 Batch B fuel assemblies for Waterford, Unit 3, and all Batch C and 9 Batch B fuel assemblies for Palo Verde.
San Onofre fuel remains to be L
ORGANIZATION:
COMBUSTION ENGINEERING, INCORPORATED POWER SYSTEMS GROUP WINDSOR, CONNECTICUT REPORT INSPECTION N0.:
99900401/83-01 RESULTS:
PAGE 3 of 3 modified. The shoulder gap problem has been documented in the CE " Corrective Action Program." Presently, no changes are planned to the design process.
The control of the design change process was verified by review of the St. Lucie modification. The new design was found to be based on a new model for fuel rod growth.
This model was documented in Design Memos TDF-82-351 and A-PH-648.
In addition, the Waterford design calcula-tions were reviewed with the review and approval of the design change being found to follow the established procedures.
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PERSONS CONTACTED S b !SS Company Dates kk/M 48/
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