IR 05000458/1985048

Insp Rept 50-458/85-48 on 850624-28.No Violations or Deviations Identified.Major Areas Inspected:Preoperational Test Results Evaluation & Operating Procedures

ML20134D054
Person / Time
Site:	River Bend
Issue date:	08/09/1985
From:	Bennett W, Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20134D049	List: IR 05000458/1985048 ML20134D047
References
50-458-85-48, NUDOCS 8508190034
Download: ML20134D054 (3)

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.. ' APPENDIX s .

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

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NRC Inspection Report: 50-458/85-48 Construction Permit: CPPR-145

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.Do'c'ket:' 50-458 . ..

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Licensee: Gulf. State Utilities

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' ' Beaumont, sTexas 77704 Facili.ty Name: River Bend Station

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= Inspection Ati ' River? Bend Site, St. Francisville, Louisiana Inspection Conducted: June 4-28, 1 85

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Inspector- A>> M h76 R. / Bennet Project Insplector, Pro,ect Date~ '

ection A Reactor Projects Branch Approved: -

Jaud d/> M

, Chief, PPoject Section A, Reactor I

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f. Prtr L P[ ject Branch Inspection Summary Inspection Conducted June 24-28, 1985 (Report 50-458/85-48)

Areas Inspected: Routine, unannounced inspection of preoperational test results evaluation and operating procedures. The inspection involved 44 inspector-hours onsite by one NRC inspecto Results: Within the two areas inspected, no violations or deviations were identifie DP h5 OkSO PDR

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DETAILS

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. Persons Contacted Gulf States Utilities (GSU)

• C. J. Banks, Security Compliance Supervisor

• R. P. Carter, Security / Access Screening

• P. J. Dautel, Licensing Staff Assistant

• D. L. Davenport, Security Superintendant

• J. C. Deddens, Vice President D. R. Derbonne, Preoperations Testing Supervisor

• R. W. Frayer, Electrical /I&C Projects Supervisor

• D. R. Gipson, Assistant Plant Manager, Operations, Chemistry Radwaste

• J. M. Glazar, Director, Nuclear Plant Engineering

• C. B. Graham, Preoperational Testing Supervisor

• P. D. Graham, Assistant Plant Manager

• E. R. Grant, Supervisor - Nuclear Licensing

• J. C. Hashagen, Lead Electrical Engineer

• R. W. Helmick, Director - Projects

• B. Hey, Engineer / Licensing

• G. R. Kimmell, Supervisor Operations Quality Assurance (QA)

• G. V. King, Plant Services Supervisor

• H. Odell, Manager of Administration

• T. F. Plunkett, Plant Manager

• S. R. Radebaugh, Assistant Superintendent, Startup and Test

• F. L. Richter, Operations QA J. E. Spivey, QA Engineer

• K. E. Suhrke, Manager, Project Planning and Coordination

• P. F. Tomlinson, Director, Operations QA Other Contractor Contacts K. Bullen, General Electric Startup and Test Engineer

• T. M. Shea, Stone and Webster Senior Electrical Engineer The'NRC inspector also contacted other site personnel including administrati a , clerical, operations, and testing personne * Denotes those attending the exit interview conducted on June 28, 198 . Preoperational Test Results Evaluation The purpose of this portion of the inspection was to assure that the licensee is performing an adequate evaluation of test results and to ensure that all test data is either within established acceptance criteria or that deviations are properly dispositioned.

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-3-The NRC inspector reviewed completed preoperational test procedure 1-PT-210, " Integrated Emergency Core Cooling System and Loss of Offsite Power." Two test exceptions were outstanding and properly documented on the master punch list. All other test exceptions were properly documented and dispositioned. The NRC inspector found seven instances of improper implementation of minor change requests and thirteen instances of improper signoffs which were not discovered by test reviewers or the joint test group. These problems appear to be similar to those discussed in NRC inspection report 50-458/85-49; since they occurred before that report was issued, they are not cited separately herein. The problems are considered an open item, and should be corrected in the action to correct the violation in NRC inspection report 50-458/85-49(8548-01).

3. Operating Procedures The objective of this portion of the inspection was to confirm tha't the plant operating procedures are prepared to adequately control safety-related operations within the applicable regulatory requirement The NRC inspector reviewed the following procedures:

Procedure Revision Title Date of Issue 50P-0003 1 Reactor Recirculation System 5/23/85 SOP-0032 1 Low Pressure Core Spray 3/19/85 SOP-0059 1 Containment HVAC System 5/18/85 S0P-0090 1 Reactor Water Cleanup System 5/13/85 The NRC inspector found that SOP-0059 had valve lineups for safety-related systems without the required independent verification. When notified of this problem, an apparent violation, the licensee stated that they had previously identified this problem and gave the NRC inspector a draft version of Revision 2 to SOP-0059 which showed that proper corrective action had been take No violations or deviations were identified in this portion of the inspectio . Exit Interview An exit interview was held June 28, 1985, with the personnel denoted in paragraph 1 of this report. The NRC senior resident inspector also attended this meeting. At this meeting, the scope of the inspection and the findings were summarized.

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