IR 05000445/1973001

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Regulatory Operations Insp Repts 50-445/73-01 & 50-446/73-01 on 730215.No Unresolved Items or Enforcement Actions Noted. Major Areas Inspected:Organizations,Reactor Operator Insp, Operator Responsibilities & inspector-licensee Relationship
ML20212N861
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 03/01/1973
From: Flora J, Madsen G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20212N850 List:
References
FOIA-87-119 50-445-73-01, 50-445-73-1, 50-446-73-01, 50-446-73-1, NUDOCS 8703130187
Download: ML20212N861 (6)


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U. S. ATOMIC ENERGY COMMISSION i

REGION IV

DIRECTORATE OF REGULATORY OPERATIONS

I g. ;4 RO Inspection Report No. 73-01 License No.

Texas Utilities Services, Inc.

Priority Comanche Peak Electric Stations Units 18e 2

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Category A-1

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Type of Licensee:

Westinghouse,1150 Mwe (PWR)

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Type of Inspection: Announced, Initial Corporate Management Meeting i

Date of Inspection:

February 15, 1973 Date of Previous Inspection:

None t

j Principal In spector:

Not Currently Assigned 1.Q

.Sa l 47A.l.i Regulatory Operations Representatives:

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L J.

lora, Director, RO:IV Date

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,I 2 d 4L.L,a a,hs G. L. Madsen, Chief, Reactor Construction and Date Operations Branch, RO:IV

Reviewed by:

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J. \\. Flora, Director, RO:IV Date l

Fo14-07-1I9

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Proprietary Information:

None (continued)

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8703130187 8701)))

PDR FOIA WILLIAM 87-119 PDR

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Enforcement Action

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None A

Licensee Action on Previously Identified Enforcement Matters

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Status of Previously Identified Unresolved Items

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Persons Contacted in

---i The following corporate officers and technical staff personnel were

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pres'ent at a corporate level meeting held at the Texas Utilities J..

Services, Inc. offices in Dallas, Texas, on February 15, 1973:

JL c';T Texas Utilities Services, Inc. (TUSI)

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"O P. G. Brittain, Executive Vice President

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J. L. Forbis, Vice President Design & Construction R. W. Caudle, Project Manager-Nuclear Plants J

H. C. Schmidt, Manager-Quality Assurance

C. W. Garrard, Manager-F6el

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D. N. Chapman, Project Engineer - Site B

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I R.' H. Hickman, Project Engineer - Comanche Peak

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D. T. Keating, Nuclear Engineer y

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J.,W. Flora, Director, Denver Office l

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.j G! L. Madsen, Chief, Reactor Construction and Operations Branch

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Management Interview

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The following subjects were discussed with the corporate officers and technical personnel listed above:

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The Regulatory and RO organizations, and the DL-RO

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relationship.

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11.I-A typical RO inspection, frequency of inspections, the infor-

'i mation needs of the inspector and the necessity for pertinent records to be readily available.

The RO inspection' responsibilities and methods of communicating with the licensee, with particular emphasis on the management interview at the conclusion of each inspection.

The inspector-licensee relationship and the requirements for i

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clear channels of communications.

The qualification requirements for the RO inspectors and the inspector's code of ethics.

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The enforcement procedures avaiIable to RO, including civil penalties.

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The RO inspection reporting system and the introduction of

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documents into the Public Document Room.

l The conclusion which the regulatory staff must reach before

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an operating license can be issued and the role of RO in reaching the conclusion.

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The needs of RO relative to ready access to licensee and

"I contractor personnel.

E The necessity for complete documentation of deviations, (

including methods of resolution and approvals.

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, The' RO vendor inspection programs and the utilization of

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consultants in areas of specialized concern.

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The security requirements for nuclear power plants and

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the general implications upon the design of the facility.

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The nonradiological environmental matters and the

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associated involvement of RO.

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- The nec'essity for advising RO promptly of significant discrepancies and a general coverage of regulatory reporting requirements.

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c-The need for correlating vendor procurement and site Y:

construction to the Safety Analysis Report, and the

advantages associated with maintaining the Safety Analysis

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Report current.

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An explanatioh of the requirements for a QA program, as

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defined by Appendix B,10 CFR 50. The following were

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included:

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The responsibilities of licensees.

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Degree of involvement by the licensee.

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Independence of the QA organization.

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Involvement in the vendor programs.

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Audit programs.

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Programs for corrective actions.

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Establishment of permanent documentation.

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Comments by TSUI relating to policies / procedures being

'a; planned to implement the Appendix B criteria. A representative

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of TUSI asked if RO would be able to review and comment

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.g on the QA program content prior to their submission of an C

application. He was informed that it could be done, providing (

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that there is a clear understanding that such comments would

g in no way prejudice the later review by the Directorate of

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M:y Licensing staff, or future RO findings. Such an understanding

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was acknowledged.

The presentation of examples and RO experiences in the c

inspection of site construction and component fabrication.

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l The emphasis regulatory places on QA/QC records for obtaining objective evidence relative to the quality of the plant. The need for complete, accurate, and technically useful recorris

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was stressed.

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A discussion of the planned initial RO QA inspection, for the

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purpose of reviewing the TUSI QA Manual to determine the

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method and degree of response to the requirements of 10 CFR

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i Sff 50,- Appendix B and the PSAR. Special emphasis, during the

initial QA inspection, will be placed on the controls relating to

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design, engineering, procurement, and vendor inspection.

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