ML19301A398
| ML19301A398 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/28/1981 |
| From: | Sells D Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19301A399 | List: |
| References | |
| NUDOCS 8111130026 | |
| Download: ML19301A398 (2) | |
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'lD40RANDUM FOR:
'D. G. Eisenhut, Of rector, Division of Licensing, NRR-
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TliRU:.
R. L.' Tedesco, Assistrant' Director for Licensing, DL l
F. J. Miraglia, Chief. Licensing Branch Ho. 3. DL R
FR04:
D. E. Sells, Project llenager, Licensing Branch No. 3, DL I
SUBJECT:
SU41ARY OF QUADREX REFORT - SOUlt TEXAS PP,0 JECT i
The following tab 41ation is a very brief sumary of the Quadrex Report that deals with the engineering design status of the South Texas Project.
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i The' study conducted by the Quadrex Corporation was not an in-depth analysis of I
Brown and Root'.s design effort to date. The study T6cked at \\ [t s d if)p, areas:
f 1.
Civil / Structural
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O f
2.
Cmipute.- Codes 3.
Electrichl/ Instrumentation and Control 0OI2 S 1984 'g"I I
4.
HVAC 7 E3* kutu ar% -
5.
Mechanical 2
N2 6.
Nuclear / Mechanical Analysis 7.
Piping and Support s
8.
Radiological' Control M
Within each area Quadrex placed each concern that was identified into one of the following categories; o most serious._- fat;ncts licensing o serious - ti:apacts reliability o noteworthy - contributes to project schedule and/or cost increases o potential jiroblem - may or may not be a problem, further investigation L
required. 1 o ' other-minor or not amenable' to corrective action.
The attached table provides the number of concerns in each category for each area reviewed.
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i In adottion the Quadrex Report identified four problem areas with regard to
' Inservice-Inspection and cited 21 specific areas with regard to maintenance i
access engineering.
i There were a total of 17 finoings that were classified by Quadrex as generic.
Pending tue results of the Bechtel in-oepth analysis it wculd be pre-mature to-i
_' place great weight on the following lunary list excerpted from Section 3 of e
Volume 1 of the Quadrex Report:
1.,
No indication of an effective systems integration and overvient function.
2.
Input data not consistently reviewed with calculations containing errors verified as correct. Vendor submitteo reports not consis-tent.
3.
Thorough and consistent treatment of various plant operating modes and environmental conditions is not evident.
4.
Distinction between Safety-Related and Non-Safety Related equipment i
and calculations is questionable.
5.
No written guidelines exist for the conduct of failure pode and effects analysis.
6.
Ho documented evidence that FSAR corxnituents are being met.
7.
Little evidence of a well-thougnt-out and consistent basis for design.
8.
Specific reliabi11ty requirements have not been established.
9.
Nuclear-related analysis questionable.
- 10. Use of preliminary data permittea up to the point of fuel loading.
l 11.
Inadequate consideration of plant operation criteria.
12.
Ineffective use of natural plant symetry.
- 13. Incomplete specification of valve closure rates.
14.
Inadequate analysis concerning access for maintenance and in-service-
-inspection.
- 15. Test ;>rovisions do not appear to have been systematically consicered i
and implemented.'
- 16. Local temperatures during maintenance may not have been considered adequately.
- 17. Use of abnormally low seismic valves for valve ano pump end loads.
t Volume I of the Report provides the results of the study and Volumes 11 and-III
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provides the back-up information that was obtained in the brief time (3 months) that was devoted to gathering infonnation by Quadrex.
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Donald E. Sells, Project Flanager e
i Licensing Branch Ho. 3 Division of Licensing l
cc: See next page.
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