ML20215D199

From kanterella
Jump to navigation Jump to search
Forwards Engineering Assurance Program Insp Repts 50-498/86-39 & 50-499/86-39 on 860825-29.Corrective Actions for Tasks 85-1,85-2 & 85-3 Acceptable.Next Engineering Assurance Program Insp Scheduled for Wk of 861215
ML20215D199
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 12/11/1986
From: Grimes B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Goldberg J
HOUSTON LIGHTING & POWER CO.
Shared Package
ML20215D202 List:
References
NUDOCS 8612160256
Download: ML20215D199 (2)


See also: IR 05000498/1986039

Text

a

p* **%q

4,,

UNITED STATES

e

'

[

g

NUCLEAR REGULATORY COMMISSION

r R

WASHINGTON, D. C. 20566

7;

% * * * * * */

DEC 11 M

Docket Nos. 50-498

50-499 .

Mr. J. H. Goldberg

Group Vice President - Nuclear

Houston Lighting and Power Company

P. O. Box 1700

Houston, TX 77001

SUBJECT:

SOUTH TEXAS PROJECT ENGINEERING ASSURANCE PROGRAM (EAP)

INSPECTION REPORT 50-498/86-39, 50-499/86-39

Dear Mr. Goldberg:

This letter conveys, the results and conclusions of NRC's evaluation of cor-

rective actions associated with the following Stone and Webster Engineering

Corporation (SWEC) EAP Independent Technical Assessment Tasks:

85-1, Control

Room HVAC System; 85-2, Component Cooling Water System; and 85-3 Offsite AC

Power and Medium-Voltage AC Power Supply Systems.

The inspection was conducted

by a team of personnel from the NRC's Office of Inspection and Enforcement and

consultants at the offices of Bechtel Energy Corporation (BEC), Houston, Texas,

August 25, 1986 to August 29, 1986. Additionally, the status of all outstanding

items from previous NRC inspection reports Nos. 50-498/85-09, 85-14, 85-22 and

85-26 were reviewed.

Based on our inspection, it was concluded that corrective actions for Tasks

85-1, 85-2, and 85-3 have been acceptably completed and that all previous inspec-

tion report items have been adequately resolved.

In tt.e process of resolvint

previous inspection report open items, the staff identified a new civil / structural

technical issue regarding the application of a 20% factor to live loads when

combined with seismic loads in the design of the reactor containment building.

This issue was referred to NRR for resolution since it was viewed by IE to be

a deviation from an FSAR licensing commitment.

The results of the inspection were reviewed with your EAP manager in an exit

meeting on August 29, 1986; notwithstanding this I regret the delay in issuing

the inspection report.

The next inspection of your EAP is tentatively scheduled for the week of December 15,

1986.

The purpose of this inspection is to verify the adequacy of corrective

Q21boassos3g33

G

ADOCK 05000490

PDR

..

J. H. Goldberg

-2-

actions associated with EAP Tasks 84-4, Separation and Fire Protection Criteria;

85-4, HELBA; 85-5, ASME Class 1 Pipe Stress Analysis; and 86-1, Field Walkdowns.

Sincerely,

'

-

Brian K. Grimes, Director

Division of Quality Assurance, Vendor,

and Technical Training Center Programs

Office of Inspection and Enforcement

Enclosure:

Inspection Report

,