IR 05000445/1987028

Insp Rept 50-445/87-28 on 871104-1201.No Violations or Deviations Identified.Major Areas Inspected:Applicant Actions on Previous Insp Findings,Preoperational Testing Program & Plant Tours

ML20237D577
Person / Time
Site:	Comanche Peak
Issue date:	12/15/1987
From:	Kelley D NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20237D575	List: IR 05000445/1987028 ML20237D574
References
50-445-87-28, NUDOCS 8712240044
Download: ML20237D577 (5)

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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF SPECIAL PROJECTS l

NRC Inspection Report: 50-445/87-28 Permit: CPPR-126 Docket: 50-445 Category: A2 Construction Permit Expiration Date:

Unit 1: August 1, i988 Applicant: TU Electric Skyway Tower i

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400 North Olive Street Lock Box 81 Dallas, Texas 75201 Facility Name: Comanche Peak Steam Electric Station (CPSES),

Unit 1 Inspection At: Comanche Peak Site, Glen Rose, Texas Inspection Conducted: November 4 through December 1, 1987

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Inspector Aru p /1/o"[@

Date L. Kelley, SenAorJR531dentInspector, Operations Reviewed by: k[/46mh R. F. Warnick, Assistant Director

/2-M- 77 Date for Inspection Programs Comanche Peak Project Division Office of Special Projects 8712240044 871215 PDR G

ADOCK 05000445 PDR

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Inspection Summary Inspection Conducted: November 4 through December 1, 1987 (Report 50-445/87-28)

Areas Inspected: Routine, unannounced safety inspection including (1) applicant actions on previous inspection findings; (2) Preoperational terting program; and (3) plant tour Results: Within the areas inspected, no violations or deviations were identified.

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DETAILS

. Persons Contacted 1 l

l *R. P. Baker, Engineering Assurance (EA) Regulatory Compliance Manager, TU Electric

• R. D. Best, Nuclear Operations Inspection Report Item Coordinator, TU Electric

• D. N. Bize, EA Regulatory Compliance Supervisor, TU Electric

• J. T. Conly, Lead Licensing Engineer, Stone & Webster Engineering Corporation

• C. G. Creamer, Instrumentation & Control (I&C) Engineering Manager, TU Electric

• R. D. Delano, Licensing Engineer, TU Electric

• P. E. Halstead, Manager, Quality Control (QC), TU Electric

• T. L. Heatherly, EA Regulatory Compliance Engineer, TU Electric

• D. A. Hodge, CPRT Interface, TU Electric

• R. T. Jenkins, Manager, Mechanical Engineering, TU Electric

• J. J. Kelley, Manager, Plant Operations, TU Electric

• J. J. LaMarca, Electrical Engineering Manager, TU Electric

• 0. W. Lowe, Director of Engineering, TU Electric

• D. M. McAfee, Manager, Quality Assurance (QA), TU Electric

• D. E. Noss,-QA Issue Interface Coordinator, TU Electric

• D. M. Reynerson, Director of Construction, TU Electric

• M. J. Riggs, Plant Evaluation Manager, TU Electric

• A. B. Scott, Vice President, Nuclear Operations, TU Electric

• C. E. Scott, Manager, Startup, TU Electric

• J. C. Smith, Plant Operations Staff, TU Electric

• J. F. Streeter, Director, QA, TU Electric

• C. L. Terry, Unit 1 Project Manager, TU Electric

• T. G. Tyler, Director of Projects, TU Electric The NRC inspector also interviewed other applicant employees during this inspection perio * Denotes personnel present at the December 1, 1987, exit intervie . Follow-up on Open Inspection Findings (92701) 1 (Closed) Open Item (445/8601-0-05): During the review of the I auxiliary feedwater (AFW) system, the NRC inspector noted that l Section 10.4.2.9 of the FSAR specified that all single lines supplying water to the motor driven AFW and turbine driven AFW pumps from the condensate storage tank (CST) to the steam generators be through locked open valves. System flow diagram ,

2323-M1-0206 shows all manual valves locked open between the j condensate storage tank and the steam generators; however, the 6 inch test bypass valves which are capable of diverting all the flow back to the CST, are not shown as locked shu System Operating Procedure SOP-304A and operations  !

surveillance Procedure OPT-206A have been revised to show that

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1 the test bypass valves will be locked shut. The NRC inspector has no further questions on this item. This item is considered close (Closed) Open Item (445/8601-0-09): During a review of surveillance Procedure OPT-206A, the NRC inspector noted that the procedure did not require measurement and recording of the l auxiliary feedwater pump suction pressure. This parameter is necessary in order to accurately calculate the total discharge head of the pump The procedure has been revised to include this parameter. The NRC inspector has no further questions on this item. This item is considered close . Review of Preoperational Testing Program (70301)

The NRC inspector completed the review of the applicants procedures for control and conduct of the reperformance of the preoperational test program. This review was of amended drafts of procedures: STA-808, Unit 1 Prestart Test Progra STA-625, Conduct of Daily Schedulin The NRC inspector made no comments concernir.g the above two amended draft procedure It was noted, however, that there are substantive differences between this new test program and the program described in Chapter 14 of FSA These program differences will require amendment to FSAR Chapter 14 and any other affected chapter The applicant is presently drafting a FSAR amendment to address these difference No violations or deviations were identifie . Plant Tours (71302)

The NRC inspector performed frequent tours of Unit 1 and common plant areas during this inspection period. In addition to the general housekeeping activities and general cleanliness of the facility, specific attention was given to areas where safety-related equipment was installed and where activities were in progress involving safety-related equipment. These areas were inspected to ensure that:

. Work in progress was being accomplished using approved procedure .

Special precautions for protection of equipment were implemented and additional cleanliness requirements were being adhered to for maintenance and welding activitie _ _ _ _ _ - - _ _

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. .. Installed' safety-related equipment and components were being protected and maintained to prevent damage or deterioratio . Exit Interview (30703)

An exit interview was conducted on December 1, 1987, with'the applicant's representatives identified in paragraph 1 of this report. During this int'erview, the NRC inspectors summarized the scope of the inspectio E_ _ - )