IR 05000498/1985017

Insp Repts 50-498/85-17 & 50-499/85-15 on 851001-1130.No Violation or Deviation Noted.Major Areas Inspected:Licensee Action on Previous Findings,Preoperational Test Procedure Review & Allegation Followup & Site Tour

ML20154P893
Person / Time
Site:	South Texas
Issue date:	02/18/1986
From:	Breslau B, Carpenter J, Constable G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20154P870	List: IR 05000498/1985017 ML20154P867
References
50-498-85-17, 50-499-85-15, NUDOCS 8603200448
Download: ML20154P893 (7)

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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

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NRC Inspection Report: 50-498/85-17 Construction Permint: CPPR-128 50-499/85-15 CPPR-129

Docket: 50-498 and 50-499 Licensee: Houston Lighting & Power Company (HL&P)

P. O. Box 1700 Houston, Texas 77001 Facility Name: South Texas Project, Units 1 and 2

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Inspection At: South Texas Project, Matagorda County, Texas Inspection Conducted: October 1 - November 30, 1985 Inspectors: .A 2 9 /

. . Carpenter, Resident Inspector Date roject Section C, Reactor Projects Branch itA LA N11 B. A. Breslau, Project Inspector Ddte '

Project Section C, Reactor Projects Branch Approved: . _~ _. -

/ 9 WL.' Const'able, Chief, Project Section C Date Reactor Projects Branch Inspection Summary Inspection Conducted October 1 - November 30, 1985 (Report 50-498/85-17; 50-499/85-15)

Areas Inspected: Routine, unannounced inspection included site tours, licensee action.on previous findings, preoperational test procedure review and allegation follow up. The inspection involved 245 inspection-hours onsite by two NRC inspector Results: With the scope of this inspection, no violations or deviations were identifie PDR ADOCK 05000498

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DETAILS

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Principal Licensee Employees H.' Goldberg,~ Group Vice President, Nuclear .

E. Hill , Project Compliance Engineer l *S. M. Head, Lead Project Compliance Engineer .

K. O'Gara, Project Compliance Engineer R. R. Hernandez, Supervisor, Project Compliance

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F. Alkov, Material Control Supervisor

• L. Dolan, Project Compliance Engineer

• R. Daly, Startup' Manager

• A. G. Peterson, Startup T. J. Jordan, Project QA Manager

*D. R. Keating, Operations QA General Supervisor j J. T. Westermeier, Project Manager j R. C. Arthurs, Project QA General Supervisor-

• W. H. Kinsey, Plant Manager S. M. Dew, Deputy Project Manager R. L. Balcom, Reactor Operations Manager-M. A. Ludwig, Maintenance Manager j Other Personnel Bechtel Power Corporation (Bechtel)

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• J. B. Gatewood, Project QA Engineer ,

M. H. Alexander, Materials Manager ^

R. H. Medina, Lead QA Engineer

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D. M.-Stover, Construction Manager .

J. E.' Noxon, QA Engineer

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• J. A. Brown, Project Services Superintendent Ebasco Services, Inc.1(Ebasco) ,

. *J. E. Blackwood, Construction Superintendent A. M. Cutrona, QA Manager .

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R. M. Zaist, Construction Manager

• R. G. Peck, Deputy Quality Program Site Manager '

Westinghouse A. Hogarth, Site Manager

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-3-In addition to the above personnel, the NRC inspectors held discussions with various operations, engineering, technical support, maintenance, and adminstrative members of the licensee's staf * Denotes those individuals attending the exit interview conducted on December 2, 198 . Site Tours The NRC inspector made plant tours, both independently and with licensee and contractor personnel. These tours were to assess the protection of inplace plant equipment, fire protection, plant status and to observe ongoing construction testing and maintenance activities. The areas toured included: Unit 1; Mechanical and Electrical Auxiliary Building (MEAB),

Fuel Handling Building, Diesel Generator Building, and Reactor Containment Building; Unit 2; Reactor Containment Building, MEAB, Turbine Building and Fuel Handling Building, Balance of Plant (B0P); and the Emergency Cooling Pump Building, Security Building and warehouse The NRC inspector observed control room staffing, startup prerequisite testings and plant maintenance. Operations and QA support personnel were observed in the plant tracing systems for trainin No violation or deviations were identifie . Licensee Action on Previous. Inspection Finding:

(Closed) Unresolved Item 498/499-8408-01 Storage / Maintenance of Nuclear Steam Supply System (NSSS) Equipment This unresolved item concerns how differences between vendor manuals and-

" Westinghouse NSSS Component Receiving and Storage Guidelines Manual" are resolved and documented. A joint group composed of Westinghouse site personnel and Bechtel Storage and Maintenance Technical Support (SMTS)

Group was formed. The purpose of this joint group was to reverify the maintenance requirements for all NSSS equipment received at the time of the review under P0 4000/8000, the NSSS supplier, and identify and correct any discrepant condition This review was accomplished by comparing the Westinghouse NSSS Component Receiving and Storage Guidelines Manual against the applicable manufacturer's technical manuals. Any conflict between these documents was resclved and were incorporated into the Westinghouse NSSS Component Receiving and Storage Guidelines Manual. The review encompassed approximately 1,767 individual sub-assemblies / components and identified no anomalies which could adversely affect the integrity of the equipment. However, the storage level requirement for a semi-automatic refueling machine was changed from Level C to Level B. Westinghouse concurrence on the results of this evaluation has been received by the license _ - __ - __ _ . _ .

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The Westinghouse NSSS Equipment Maintenance Review Form for documenting Maintenance Action Card (MAC) system maintenance requirements and recording Westinghouse' concurrence has been proceduralized in WPP/QCI 28.0, l Revision ll, " Maintenance of Material Equipment."

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i General Surveillance Report S-B-0208 dated March 12, 1985 verified completion of this review program and resolution of the discrepancy discussed above.

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The NRC inspector has reviewed the above documentation and licensee

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actions. Based on the results of the rereview it appears that there was

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no violation of NRC requirements. This unresolved item is closed.

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(Closed) Open Item 498/499-8503-01 Draft Preoperational Test Procedure Review, 1-DJ-P-01 "125V DC Battery System, Channel I"

This open item concerns comments by the NRC inspector on the safety-related l Preoperational Test Procedure 1-DJ-P-01, "125V. DC Battery system, Channel I."

! This draft procedure was provided to the NRC at the same time it was sent to the Joint Test Group (JTG) and was the first safety-related test

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procedure. The procedure was inadequat An extensive list of comments

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The licensee has completely revised procedure 1-DJ-P-01, FSAR i Section 14.2.12.2.20 and 21 (1E Battery acceptances criteria) and their L; method of test draft test procedure revie The NRC inspector has reviewed I the issued Preoperational Text Procedure 1-DJ-P-01, Revision 1, and found l it acceptable with all NRC comments provided on the. draft procedure being j acceptably resolved. This open item is close l (Closed) Unresolved Item 498/499-8415-01 Startup Organization i This unresolved item concerns differences between licensees actual startup organization and that described in the STP Final Safety Analysis Report (FSAR) Section 14.2, Startup Administrative Instruction (SAI) 1.02,

"Startup Organization." In mid-1984, the startup organization was under-going a major reorganization, including a new startup manager. 'The FSAR has since been revised (Amendment 48) to reflect the current organization and assigned responsibilities. SAI 1.02 was reissued as SAI 2, "Startup

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Organization," Revision 0, and also describes the current organizatio The NRC inspector has reviewed the above documentation and concluded that no violation of NRC requirements occurred. This unresolved item is closed.

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{ Preoperational Test Procedure Review l During this inspection the NRC inspectors reviewed the following j preoperational test procedures:

l 1-EW-P-01 Essential Cooling Water-System Performance - Train 1A

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1-EW-P-02 Essential Cooling Water System Performance - Train IB i

i 1-EW-P-03 Essential Cooling Water System Performance - Train 1C

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-5-1-RM-P-01 Reactor Makeup Water System

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1-WL-P-01 Reactor Coolant System Drain Tank

. 1-0J-P-01 125V DC Class 1E System Channel 1 1-DJ-P-02 125V DC Class 1E System Channel 2 1-DJ-P-03 125V DC Class 1E System Channel 3 1-DJ-P-04 125V DC Class 1E System Channel 4

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The listed preoperational test procedures were reviewed to determine if the contents were in accordance with the FSAR, Regulatory Guide 1.68 and the licensee's administrative procedure The NRC inspectors determined that the procedures were technically ade.quate to accomplish their objective The NRC inspector also reviewed the following related instructions and procedures. The Startup Administrative Instructions (SAI), Desk Top

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Instructions (DN), and Quality Assurance Implementing Procedures (QCIP)

were reviewed to verify that they are technically adequate to accomplish the stated purpos SAI-1 Startup Manual Use and Control SAI-2 Startup Organization SAI-3 Startup Quality Assurance Plan SAI-10 Indoctrination Training and Certification of Test Personnel SAI-17 Prerequisite Testing SAI-18 Preoperational Testing SAI-19 Acceptance Testing SAI-22 Conduct of Startup Operations DN-85-001 Desk Top Instructions provides guidelines for preparing / developing preoperational test procedures QAIP- Organization

QAIP- Indoctrination and Training

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-6-QAIP-2,1 Certification Requirements for Site Surveillance Personnel QAIP- Standard Format for Writing and Controlling Procedures and Manuals QAIP- In-Process Document Control QAIP- Records Review QAIP- Audits QAIP- Surveillance QCIP- Receiving Inspection QCIP- Operations Quality Control Call Log QCIP- Inspection Reporting QCIP- Area / Systems Turnover to Nuclear Plant Operations Department QCIP- Quality Control Document Reviews QCIP- Inspection Planning QCIP- Certification of Inspection Examination and Test Personnel Within the areas examined, the NRC inspector found the instructions and procedures adequat No violations or deviations were identifie . Allegation Follow-up: 4-85-A-080 A general allegation was telephoned to Region IV regarding mismanagement of the South Texas Project Safeteam. The caller indicated that a letter with specific information and selected documents would be forth coming. No such letter was received and attempts to contact the individual by telephone and certified mail were unsuccessful (see NRC Inspection Report 50-498/85-19 and 50-499/85-17). A NRC inspector learned that the same allegations by the same individual, a former Safeteam investigator, were received by the Safeteam several months prior to the NRC notification. Since the allega-ticns involved the Safeteam itself the licensee contracted for a third party investigation by an experienced consulting firm. An NRC inspector reviewed the licensee's Safeteam investigation, the independent J

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-7-consultant's investigation and the infor.mation provided to the NRC and found all actions taken were reasonable and acceptable. The results of that investigation was the voluntary termination of general foreman in August 1984. Based on the various reviews by independent organizations, including the NRC and the inability to acquire additional information from the alleger, this allegation is close .No violation or deviations were identifie . Exit Interview An exit interview was conducted on December 2, 1985, with those personnel denoted in paragraph 1 of this report. During the exit interview, the NRC inspectors summarized the scope and findings of this inspection.