IR 05000324/1987016

Insp Repts 50-324/87-16 & 50-325/87-16 on 870527-29.No Violations or Deviations Noted.Major Areas Inspected:Ie Bulletin 80-11 & Snubber Surveillance Program

ML20234C052
Person / Time
Site:	Brunswick
Issue date:	06/24/1987
From:	Jape F, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20234C033	List: IR 05000324/1987016 ML20234C030
References
50-324-87-16, 50-325-87-16, IEB-80-11, NUDOCS 8707060316
Download: ML20234C052 (5)

Text

{{#Wiki_filter:,

.       I
  *

UNITED STATES .

[[ tan )p oe%g Iog g,

NUCLEAR REGULATORY COMMISSION REGION il

      '!

I

*' e MARIETTA STREET, N.W., SUITE 2900 8-  ATLANTA, GEORGIA 30323
%, . . . . . $f      ,
       ;
      .l
       -

l I l Report Nos'.: 50-325/87-16 and 50-324/87-16 Licensee: Carolina Power and Light Company P. O. Box 1551' Raleigh, NC 27602

      '! '

Docket Nos.: 50-325 and 50-324 License Nos.: DPR-71 and DPR-62 Facility Name: Brunswick 1 and 2

       ]

Inspection. Conducted: May 27-29, 19 Inspector: h 6 E7 )

   - '

Date Signe J.J.Lenahanf Approved by: b/ kMV f F. Jape, Section I:hief

     '
    (/ /  Date Sfgned Engineering Branch Division of Reactor Safety
       ,

SUMMARY-Scope: This. routine, unannounced inspection was conducted in the areas of IEB 80-11 and the snubber surveillance progra Results: No violations or deviations were identifie l i 9707060316 870626-  ! gDR ADOCK 05000324 l PDR l l l l l

    :c

,

.

     ~

t REPORT DETAILS Persons Contacted i Licensee Employees S. Bertz, Mechanical Engineer

*C. R. Dietz, General Manager - Brunswick Nuclear Plan '
 .
*K. E.-Enzor, Director, Regulatory Compliance
*P. W. Howe, Vice President - Brunswick Nuclear Project R. Kitchen, Maintenance Supervisor, Unit 2 W. Monroe, Principal Engineer R. Nease, Civil - Structural Engineer
*J. O'Sullivan, Manager, Maintenance
*R. M. Poulk, Senior Specialist, Regulatory Compliance D. Thrift, Mechanical Maintenance Foreman
*T. Wyllie, Manager, Engineering and Construction Other licensee employees contacted were a construction engineer and two civil. engineer NRC Resident Inspectors    u
* H. Ruland L. W. Garner-
     '
     -
* Attended exit interview    '. i Exit Interview The inspection scope and findings were summarized on May 29,1987,Yith those persons indicated in paragraph 1 above. The inspector descr.ibed the areas inspected and discussed in detail the inspection- finding No dissenting comments were received from the license The licensee did not identify as proprietary any of the ma w.ri.sls provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during this inspectio .

l i

T,

-

5. Snubber Surveillance Program, Units 1 and 2 (70370) The inspector examined procedures and quality records related to the snubber surveillance program. Acceptance criteria utilized by the inspector are specified in Technical Specification (TS) 3/4. Review of Snubber Surveillance Procedures The inspector examined the following procedures which control snubber surveillance activities:

(1) Procedure number PT-19.6.0, Visual Inspection of Snubbers on Safety-Related Systems (2) Procedure number PT-19.6.1, Inspection of Snubber Functional Testing (3) Procedure number PT-19. Inspection of Safety-Related Snubbers Which Have Experienced an Unusual Shock (4) Procedure number PT-19.6.4 Safety-Related Snubber Seal Life Monitoring Review of Snubber Surveillance Records The inspector reviewed results of visual inspections performed on Unit I accessible and inaccessible snubbers in February 198 The visual inspections were performed in accordance with PT-19.6, As a result of the visual inspections and subsequent functional tests, two inaccessible snubbers were declared inoperabl Since these snubbers were installed on two separate systems, the next visual inspection will be required to be performed in 12 months per TS 4.7. The inspector also reviewed the results of functional tests performed on the 17 Unit I snubbers that were declared, when tested in accordance with procedure PT-19.6.1, to be inoperable as a result of function test failures. Five of the snubbers failed the drag test, that is, the frictional resistance to movement exceeded the licensee's acceptance criteria, one snubber exhibited excessive fluid loss during testing, while the remaining 11 failed due to low bleed rates after snubber activation. The licensee determined that the low bleed rates were the result of fluid contamination. As a result of the number of functional test failures, the licensee perforra:d functional tests on 100 percent of the snubber Within the areas inspected, no violations or deviations were identifie . IE Bulletin 80-11. Masonry Wall Design (25537)

The licensee responded to IE Bulletin 80-11 in letters to NRC Region II, dated July 5, 1980, November 5, 1980, November 25, 1980, and December 9, 198 These responses reported that on-site survey disclosed that

~

.

approximately 20 walls had not been constructed in accordance with original design requirements and that the design reanalysis identified some additional walls which required modifications to meet seismic design requirements. In letters dated July 29, 1983, and April 27, 1984, to the NRC Office of Nuclear Reactor Regulaticn (NRR), the licensee responded to requests for additional information concerning masonry wall design. These responses provided additional information regarding design criteria used by the licensee in the design re-evaluation of masonry walls and identified the walls that required modification to meet the seismic design requirement The walls that had not been constructed in accordance with original design requirements were repaired by the licensee using the original construction drawing requirements. The licensee stated in their responses that repairs on the walls requiring upgrading would be scheduled as part of a five year modification plan for the Brunswick Plant. Final acceptance of the licensee's design re analysis of masonry walls and the schedule for implementation of required repairs is documented in a Safety Evaluation Report (SER), dated January 30, 198 The inspector reviewed the status of the licensee's masonry wall modification programs for walls which required upgrading to meet seismic design requirements. The status is summarized in the Table belo Table Status of Masonry Wall Modifications Masonry Wall Repairs Under Status Numbers Plant Mod. Number of Repairs DGB 4a PM 83-235 Completed DGB 2a, 2b, 2c & 2d PM 84-301 Completed CB 9e, 9b, 9c & 9d PM 84-302 Completed DGB Sa, 5b, Sc, 5d, 6a & 9e PM 84-385 Repair Work Not Started CB 6b, 69, 8a, 8c & 8d PM 84-384 Repair Work Not Started Abbreviations DGB: Diesel Generator Building CB: Control Building The inspector examined the complete documentation packages for PM 83-235, PM 84-301, and PM 84-302. These packages included design drawings, design changes, QC inspection records, and the licensee's safety evaluation The inspector made a detailed review of QC inspection records including inspections of grouting, structural steel erection and bolting, expansion anchor installation, and weldin The inspector also walked down the walls and examined the completed repairs. These walkdowns included DGB Walls 2a, 2b, 2c, 2d and 4b, the east side of CB walls 9b and 9c and the west side of CB walls 9a and 9d. Based on the walkdowns and review of inspection records, the inspector concluded that he repairs were completed

<

. ..

in accordance with design requirements. The inspector also reviewed design drawing showing the proposed repairs to DGB walls 6a and 9e (PM-84-385) and CB Walls 6b, 69, 8a, 8c and 8d (PM-84-384). IEB 80-11 , will remain open pending completion of the repairs to the remaining wall Within the areas inspected, no violations or deviations were identified. }}