IR 05000445/1988073

Safety Insp Repts 50-445/88-73 & 50-446/88-69 on 881005-1101.No Violations,Deviations or Unresolved/Open Noted.Major Areas Inspected:Actions on Previous Insp findings,10CFR50.55(e) Deficiencies & NRC Bulletins

ML20195E101
Person / Time
Site:	Comanche Peak
Issue date:	11/03/1988
From:	Livermore H, Phillips H NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20195E079	List: IR 05000445/1988073 ML20195E075
References
50-445-88-73, 50-446-88-69, IEB-78-10, NUDOCS 8811070237
Download: ML20195E101 (7)

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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF SPECIAL PROJECTS NRC Inspection Report: 50-445/88-73 Permits: CPPR-126

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50-446/88-69 CPPR-127 Dockets: 50-445 Category: A2 4 50-446

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Construction Permit Expiration Dates:

Unit 1: Extension roquest submitte Unit 2: Extension request

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

Units 1 & 2 Inspection At: Comanche Peak Site, Glen Rose, Texas Inspection Conducted: October 5 through November 1, 1988 Inspector: -

/uI/du k . S. ~Phillips, ' Senior Resident Inspector

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if Construction

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i Reviewed by: dAtttdL t.,- /l* 7 "S6b H. H. Livermore, Lead Senior Inspector Date i

l G811070237 GS1103 PDR ADOCK 05000445 a PDC

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Inspection Summary:

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Inspect.on Conducted: October 5 throuch November 1, 1988 (Report 50-445/08-731 50-446/88-69)

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Areas Inspected: Unannounced, resident safety inspection of applicant's actions on previous inspection findings, action on 50.55(e) deficiencies, action on NRC Bulletins, and general plant inspectio Results: Within the areas inspected, no violations, deviations, or unresolved /open items were identified. The NRC inspector observed two positive points; that is, all bulletins, open items, and 50.05(e) packages submitted were complete and the NRC inspector closed all of these items. Also, the TU Electric group (responsible for evaluating industry notices) audited evaluations performed prior to 1986 to determine if the evaluations were adequate. This was a very good solf evaluation (see paragraph 2).

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DETAILS Personn Contacted

• R. W. Ackley, Jr., Director, CECO

• R. P. Baker, Licensing Compliance Manager, TU Electric

• J. L. Barker, Manager, Engineering Assurance, TU Electric

• D. P. Barry, Manager, ESG, SWEC

• J. Beck, Vice President, Nuclear Engineering, TU Electric

• M. Blevins, Manager, Technical Support, TU Electric

• H. Bruner, Senior Vice President, TU Electric

• W. Cahill, Consultant, TU Electric

• J. Conly, APE-Licensing, SWEC

• G. Davis, Nuclear Operations Inspection Report Item Coordinator, TU Electric

• D. Delano, Licensing Engineer, TU Electric

• E. Devincy, Deputy Director, Quality Assurance (QA),

TU Electric

• L. Edgar, Attorney, Newman and Holtzinger

• E. Grabruck, QA, Impoll

• G. Guldemond, Executive Assistant, TU Electric

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

• L. Heatherly, Licensing Complianco Engineer, TU Electric

• B. Hogg, Engineering Manager, Bechtel

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

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

• W. Lowe, Director of Engineering, TU Electric

• W. Madden, Mechanical Engineering Manager, TU Electric

• M. McGrath, TS/SP Manager, Startup, TU Electric

• C. Miller, Site Manager, TENERA

• W. Muffett. Manager of Civil Engineering, TU Electric

• D. Nace, Vice President, Engineering & Construction, TU Electric

• F. Ottney, Representative, CASE

• S. Palmer, Project Manager, TU Electric

• D. Redding, Executive Assistant, TU Electric

• M. Reynorson, Director of Construction, TU Electric

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

• C. Smith, Plant Operations Staf f, TU Elect *:ic

• P., Stevens, Manager, Electrical Engineeriny, TU Electric

• Strector, Director, QA, TU Electric

• Terry, Unit 1 Projo.t Manager, TU Electric

• Tyler, Director of Projects, TU Electric

• Waters, Licensing Jomplianco Engineer, TU Electric The NRC inspector also interviewed other applicant employces during this inspectiou perio * Denotes personnel rtosent at the November 1, 1988, exit meetin _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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2. Applicant Action on Previous Inspection Findings (92701)

(closed) Open Item (445/8834-0-02; 446/8430-0-02): NRC questioned the adequacy of evaluations of industry notico The NRC inspector found the ovaluation of an NRC Information Notice and one Institute of Nuclear Power Operation Bulletin inadequate concerning Plasite coating plugging cooling systems. As a result, the NRC questioned other industry notice ovaluation TU Electric voluntarily committed to reevaluate other industry noticos roccived prior to 1986 to determine if (1) the main concern was addressed, (2) related concerns were addressed, (3) documentation was sufficient to support technical conclusions, and (4) documentation is legible. The group that evaluates industry operation experience reports (IOERs)

reroviewed and reevaluated 392 IOERs with 312 remainin The results woro: (1) main concern not addressed, 7.9%;

(2) related concern not addressed, 3.8%; (3) documentation not sufficient, 16.6%; and (4) no cases whero documents were illegibl The NRC inspector found that Procedures NEO 2.29 and STA-507 control the review and assessment of industry operating experience. Concerning the open item above, a self-initiated review /cvaluation of industry noticos was performed and the review emphasized the acceptability of plant hardwar This

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effort was both comprehensive and offectivo. The NRC is i convinced that the present reevaluations should identify any i significant deficiencies and if identified they will be reported to the NRC. This item is close . Action on 10 CFR Part 50.55(c) Deficiencies Identified by the Applicant (92700) (Closed) Construction Deficiency (SDAR CP-87-08): This deficiency concerned the accuracy of calibrations using pneumatic dead weight testers and dead weight testors ,

(pressure type). Rockwell International letter 87MT0305 l dated March 1987 notified TU Electric that the TR-50 i

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tester's accuracy is 0.1%, not 0.03%.

The NRC inspector reviewed TU Electric's file, SDAR CP-87-08 for Units 1 and 2. The file contained about 20 correspondence and corrective action documents which describe the identification, evaluation, notification, and reporting to NRC and correctivo action concerning the subject deficiency. Based on this review the inspector dctormined that the deficiency was properly identified, evaluated, corrected, and the NRC was notified as require ___ _

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Two key documents, Problem Report 87-416 and Corrective Action Report 87-053, demonstrated that corrective action was adequato. The testers used in calibrating equipment and any tests were identified. The test results woro not adversely affected and this was demonstrated by either adding the inaccuracy to recorded data or determining if the calibration was within the specified calibration range. The deficiency was not safety significan This item is closed, (Closed) Construction Deficiency (SDAR CP-87-31): This deficiency concerned the air pressure regulator on DcLaval diesel generators which supplies control air to i the engine control panel. DeLaval Report 140, a 10 CFR Part 21 notification, advised TU Electric of defects in the dripwell gasket seating surfaces that could cause a loss of control air and in turn could cause a loss of starting air pressure.

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The NRC inspector reviewed TU Electric's filo, SDAR CP-87-31 for Units 1 and 2. The file contained correspondence and evaluation documents which describe the identification, ovaluation, and notification to NR Based on this review, the inspector determined that the deficiency was properly identified, evaluated, and that

the NRC was notifie The NRC inspector agrees with the TU Electric evaluation which dctormined that this item is not reportable. The pressuro regulators were roccived at Comancho Peak ,

in 1979 (Reference CP-34 Receiving Reports (RIR) 8827 '

and 12209). The defective regulators were manufactured in 198 Three spare regulators woro received in 1983 (TSN 174980-8, 661-70226, RIR-83-0385). Since no defective components that were manufactured in 1986 woro roccived at the site, this matter did not apply to this site, t

4. Inspection of NRC Dulletin 78-10 (92700)

(Closed) NRC Bulletin 78-10, "Dergen-Paterson Hydraulic Shock

Suppressor Accumulator Spring Coils": Broken accumulator

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springs in early models were in several operating plants. The failures were caused by carbon steci rusting. Borgen-Paterson recommended replacement with carbon stcol coated with teflon or stainless steel coil TU Electric's file contained eight documents which showed that this bulletin was properly addressed. Two documents,

! Westinghouse letter GTN-29847 and Comancho P(ak Specification

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2323-MS-46A, Revision 7, showed that only mechanical snubbers, r

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not hydraulic snubbers manufactured by Dorgen Paterson, were

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used at Comancho Pea Sinco no Borgon-Paterson snubbers were used, no prob 1cm, as described in the bulletin, existe This item is close . General Plant Inspections (42051, 50073, 50090, 51053, 51063, 52053, 64053)

At various timos during the inspection period, the NRC '

inspector conducted independent and planned inspections of the Unit 1 reactor containment, safeguards, auxiliary, electrical control, and diosol generator buildings. All accessible rooms in these buildings were inspected to observe current work activitics with respect to major safety-related equipment, electrical cabic/ trays, mechanical components, piping, welding, coatings, Hilti bolts, and removal of debris from scismic gap betwoon buildings. The housekeeping, storage, and t

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handling conditions inside those buildings and various outside storage areas were also inspected. One item concerning fire protection is discussed in more detail in the following paragrap The NRC inspector had observed the installation of the new tanks and underground piping for fire protection during the past several months. It is nearing completion and should provido a more maintenance free and reliable system. On October 21, 1988, the NRC inspector was in the plant and heard an announcement of a fire and the call for the fire brigado to i assemble. The inspector went to the area of the fire and observed the fire brigado actions. Three or four security <

personnel controlled the crowd. Two clectricians had previously de-energized the power to the lighting distribution pane The brigade was on hand and was well supervised. The i control room shift supervisor was at the scene. The NRC observed that a delay occurred in getting inside the panel because no one had the proper tool r.ccessary to gain entr One remark was overhead relative to not having the appropriate electrical drawings. In this case, it was no problem because the smoking ceased after de-onergizing the power; however,  !

TU Electric should critique this to assure no problem exist [

The NRC inspector informed the Senior Resident Inspector of  ;

operations, who will include this matter under an existing open ite No violations or deviations were identifie Exit Mocting (307031 An exit meeting was conducted November 1, 1988, with the

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applicant's representatives identified in paragraph 1 of this i

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repor No written material was provided to the applicant by the inspector during this reporting period. The applicant did i not identify as proprietary any of the materials provided to ,

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t or reviewod by the inspector during this inspection. During this mooting, the NRC inspector summari cd the scopo and findings of the inspectio I t

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