IR 05000317/1993024

Insp Repts 50-317/93-24 & 50-318/93-24 on 930719-23 & 28-30. No Violations Noted.Major Areas Inspected:Snubber & Pipe Support Exam & Surveillance Program for ISI & IST Requirements & Structural Concrete Placement

ML20056G377
Person / Time
Site:	Calvert Cliffs
Issue date:	08/24/1993
From:	Chaudhary S, Gray E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20056G376	List: IR 05000317/1993024 ML20056G375
References
50-317-93-24, 50-318-93-24, NUDOCS 9309030059
Download: ML20056G377 (6)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION I

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REPORT NO /93-24 50-318/93-24 1 DOCKET NO LICENSE NO DPR-53 DPR-69

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LICENSEE: Baltimore Gas and Electric Company FACILITY NAME: Calvert Cliffs Nuclear Power Plant INSPECTION AT: Lusby, Maryland j

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INSPECTION CONDUCTED: July 19-23 and July 28-30,1993 l J

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INSPECTOR: ~

}LA/ ) W^/ 7!/9!93 Suresh K. Chaudhary, Sr.11eactor Engineer date Materials Section, EB, DRS

APPROVED BY: cf!2</[f3 E. Harold Gray, Chie@faterials Section Date i EB,DRS Areas Inspected: (1) Snubber and pipe support examination and surveillance program for ISI and IST tequirements, and (2) structural concrete placement for upper base mat in new diesel generator buildin Results: (1) The results of the inspection indicated that the snubber / pipe support inspection and surveillance program was acceptable in program scope and procedural implementation, and (2) structural concrete activities for the new diesel generator building was acceptabl No violation of regulatory requirements was identifie j l

I 9309030059 930826 FDR

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DETAILS PURPOSE AND SCOPE OF TIIE INSPECTION The primary scope of the inspection was to determine, through direct observation and independent evaluations of the licensee's program, if the control system was functioning properly for installation, modification, and maintenance and testing of safety-related supports and restraints; and to determine that these supports and restraints wue in compliance with NRC requirements, applicable codes, and the licensee's commitment This inspection also included a review of planning and preparation, and observation of structural concrete placement in the upper base mat of the new diesel generator buildin The areas reviewed included: Supports and Snubbers

• ISI/IST program for snubbers and pipe supports, i l

• Snubber maintenance shop and bench test, and

• General walkthrough inspection of the plant for visml examination of accessible i snubbers and pipe support .2 Structural Concrete I

e planning and preparation, and

• observation af concrete placemen .0 FLNDLNGS Program (Pipe Support and Snubbers)

The snubber surveillance an -

Stenarme programs for both Units 1 and 2 at Calvert Cliffs Nuclear Power Plant are co, ,

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, a single prog am, and are controlled by the same general requirements and proceux . Tne scope of the ISI/IST program is based on the Technical Specification requirements in this area and the Section XI of the ASME Code.

l The Calvert Cliffs Nuclear Power Plant Units 1 and 2 arc in the second " period" of the second " interval" of the inservice examirction program. The second inspection interval l

! began on April 1,1987, for both units. The first interval for the Unit 2 concluded at the end

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of the spring refueling outage, as permitted by paragraph IWA-2400 of ASME Code,Section XI. The licensee has adopted the 1983 edition, with addenda through the summer of 1983 of Section XI of the Code as the applicable code of record. The 1979 edition, with addenda through the summer of 1975, has been used for selecting the extent of Class 1 piping welds; uwever, the inservice test requirements for snubbers are conducted in accordance with the l

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requirements of plant " Technical Specifications," superseding the Code requirements for snubbers (established in Article IWF-5000). Hence, the snubber inservice test program is covered by the plant's surveillance test progra The general ISI/IST program under the requirements of Section XI of the ASME Code are docume'ited in the " Program Plan Gr the Second Inspection Interval for CCNPP, Units 1 and 2, November 1987." The above plan has been developed and prepared by Southwest Research Institute for the license .1 Procedures The requirements of the plant Technical Specification and the Code are implemented through approved maintenance and surveillance procedures: SNUB-4, Revision 10; SNUB-5, Revision 12; STP-M-ll-2, Revision 7; and STP-M-13-1 and 2, Revision 14. These procedures are applicable to both units and cover the examinations, tests, and refurbishment of snubbers. To determine the adequacy of these procedures, the inspector reviewed the procedures for technical adequacy, clarity of requirements, and acceptance criteria. One of the above procedures was walked through (reviewed in detailed steps) with the responsible ISI personnel to determine the process of implementation and the knowledge level of personnel responsible for implementing these procedure Based on the review of procedures (especially the procedure for maintenance and refurbishment of snubbers) applicable to inspection and examination snubbers, the inspector determined that the procedures were technically good, and were adequate in establishing procedural controls; they were detailed, clearly written, and contained clearly established acceptance criteria, documentation of results, and personne1 qualifications. The procedures met the requirements of the ASME Code,Section XI. The inspector had no further )

questions in this are l Test and Overhaul of IIydraulic Snubbers i

The inspector reviewed procedures applicable to the repair, overhaul, and testing of )

snubbers, and witnessed a snubber overhaul and test in the repair shop. The review covered i

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the following areas:

• hydraulic snubber performance testing,

• hydraulic snubber functional tests,

• snubber service life monitoring,

• hydraulic snubber inspection, e snubber inspection failure tracking, and

• hydraulic snubber overhaul.

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The inspector witnessed the overhaul of snubber #1-83-48, size 1.5" x 5.0" After the overhaul, the snubber was tested for proper functioning, load rating, and stroke time 1 travel on the ITT-Grinnel shock and sway suppressor tester, Model 5434-3, serial #03L ath a maximum load rating of 75,000 lbs, and a 20" stroke. The tester was recently calibrated by the " Machine Calibration Procedure, M-TEC-6, Revision 3." l Based on the review of procedures and data, discussions with shop personnel, and the direct observation of the entire sequence of the snubber overhaul, the inspector determined that the i procedures were satisfactory, the maintenance and test shop were adequately equipped and  !

staffed for the work, and the personnel engaged in the repair and/or overhaul of snubbers ,

were qualified and knowledgeable. The inspector had no further questions in this are l Walkthrough Inspection and Visual Examination of Installed Pipe Support and Snubbens )

i The inspector performed a walkthrough inspection of the accessible areas of the plant to assess the general condition of supports and snubbers. The inspection consisted of visual examination of accessible supports for form, fit, and function; general appearance for coatings and paints; identification; and any obvious sign of degradation, missing parts or fastener The inspector also reviewed the licensee's snubber visual inspection historical record and trend for the past thirteen years to determine obvious trends indicating degradation of snubbers. The records indicated that in the past thirteen years, a total of 6,881 snubbers were inspected in both units, out of which nineteen (19) snubbers had failed to meet the applicable acceptance criteria. It was also noted that these failures were randomly distributed in time and system Based on the above review, discussion, and observation, the inspector determined that the supports and snubbeis were properly maintained, and were able to satisfy the requirements for which they were designed and installed.

l Conclusions l

Based on the above findings, the inspector concluded that the pipe support / snubber inspection / surveillance program at Calvert Cliffs Nuclear Power Plant was satisfactorily implemented, and the program was effective in assuring the safety functions of these support .0 CONCRETE PLACEMENT FOR NEW DIESEL GENERATOR BUILDING The inspector reviewed the documentation, including design and construcdon drawings; construction and purchase specifications, applicable codes and standards (ACI and ASTM);

quality control requirements and procedures; anhthe construction plaa for the concrete

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placement in the upper base mat. The reinforcing steel bars (rebar) installation in the upper base mat area also was visually examined for conformance to the design and installation requirements (DWG #C-1161/85-071-E through -076-E); the grade of the installed reinforcing bars (rebars); and the proper fabrication of and installation of form work and embedded appurtenance !

The inspector determined that the concrete mix was designed by the concrete supplier, Chany Enterprises, in accordance with the requirements of the applicable code (ACI-215). The concrete mix, materials, and cement were tested and qualified by an independent construction ,

materials testing laboratory, Geotechnical and Material Testing, Inc., for the specified i

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strength of 4,000 psi at twenty-eight days. The installed rebar met the specification requirements for grade 60, spacing, lap splice, tieing, and cleanlines The inspector reviewed the licensee's concrete placement plan and preparations, including i work plan and inspection requirements WP&lR-C5 for the upper base mat concrete  ;

placement. The WP&lR was a comprehensive document establishing the work activities, referencing design and specification, qualiv watrol requirements, the approved field ;

changes, and other related WP& irs in other disciplines such as electrical and mechanica The inspector witnessed the structural concrete placement for the upper base mat (ELV. 45' -

l 6") of the new diesel generator building. Approximately six hundred cubic yards (600 cy) of concrete were required for the placement. The inspector verified through the batch tickets that concrete mixed at the offsite batch plant of Chany, and delivered at the placement was as I

required by the design of the building and as listed in the WP&IR. The concrete sampling for routine tests, e.g., slump, air, unit weight, and compressive strength list, was performed at required frequency by Law Engineering Testing Company personnel. No discrepancies or ;

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un2tisfactory work was noted by the inspector. On the basis of the above reviews, discussions, witnessing of placement operadons, and the general planning and scheduling of the concrete work, the inspector concluded that the licensee's plan and execution of the structural concrete work was satisfactory to meet the intent of quality for safety-related structures to assure public health and safety.

! Conclusions l Based on the above reviews and observations, the inspector concluded that the licensee's i planning, preparation, and concrete placement activities were acceptable and effective in assuring high quality structural concrete constructio .0 EXIT MEETING l The inspector discussed his findings at the exit meeting held on Jul-; 23,1993, for the pipe support and snubber portion of the inspection, and on July 30,1993, an informal discussion with cognizant personnel of the site concrete placement was held. The list of attendees at the formal exit meeting of July 23,1993, is shown in Attachment i l

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ATTACIIMENT 1

i Persons Contacted l

Baltimore Gas and Electric Company l M. Gahan PF-CES ,

P. Hebrank Project Engineer l

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D. Hoang Mechanical Maintenance

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K. Hoffman NISV 1 G. Wasson DGP-QA j

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l U. S. Nuclear Regulatory Commission K. Lathrop Resident Inspector  ;

P. Wilson Sr. Resident Inspector j l

In addition to the above, many more licensee personnel, technical and supervisory, were l l

contacted, as the inspector's work interfaced with the l l

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