IR 05000324/1988022
| ML20151D253 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1988 |
| From: | Jape F, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20151D249 | List: |
| References | |
| 50-324-88-22, 50-325-88-22, IEB-80-11, NUDOCS 8807250026 | |
| Download: ML20151D253 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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101 MARIETTA STREET, N.W.
c ATLANTA, GEORGI A 30323
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Report Nos.. 50-325/88-22 and 50-324/88-22 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 Insper; tion Conducted: June 14-17, 1988 Inspector:ha.
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- F. / ape ~, Section Chief Date Signed ngineering Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was in the areas of the snubber surveillance program and IEB 80-11 Results:
In the areas inspected, violations or deviations were not identified.
One unresolved item was identified involving the adequacy of QC inspection procedures and records relating to plant modifications -
Paragraph 3.
8807250026 881707 PDR ADOCK 05L90'00
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REPORT DETAILS
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1l Persons Contacted Licensee Employees S. Bertz, Mechanical Engineer
- C. Dietz, General Manager - Brunswick Nuclear Project
- K. Enzor, Director - Regulatory Compliance
- L. Jones, Director - Quality Assurance / Quality Contro'
- J. McKee, Quality Control Supervisor
- M. J.-Pasta, Compliance Specialist l
R. Ramson, Civil Engineer
- Attended exit interview-2.
Snubber Surveillance Program, Units 1 and 2 (70370)
The inspector examined procedures and quality records related to the snubber surveillance program.
Acceptance criteria ut ezed by the inspector are specified in Technical Specification (TS) 3/4.7.5.
a.
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-19.6.3, Inspection of Safety-Related Snubbers Which Have Experienced an Unusual Shock
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(4) Procedure number PT-19.6.4, Safety-Related Snubber Seal Life Monitoring b.
Review of Snubber Surveillance Records The inspector reviewed the results of visual inspections performed on Unit 1 inaccessible snubbers in January 1988 - February 1988.
No visually inoperable snubbers were identified during this visual surveillance inspection.
The next visual inspection will be scheduled to be performed in 18 months per TS 4.7.5.b.
The inspector also reviewed the results of functional tests performed on Unit 2 snubbers during January 1988 - February 1988.
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Withir the areas inspected, no violations or deviations were ida:,ci fi ed.
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-(Fased) IEB 80-11, Masonry Wall Design (25537)
The licensee responded to IEB 80-11 in letters
',o NRC Region II, dated July 5,1980, November 5,1980, November 25, 1980, and ' December 9, 1980.
These responses reported that the design re-analyzes required by IEB 80-11 disclosed that approximately 20 walls required modifications to meet seismic design requirements.
In letters dated July 20, 1983, and April E7,1984, to the NRC Office of Nuclear Reactor Regulation (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 requirements.
The licensee stated in their responses that repairs on the wall requiring upgrading would be scheduled as part of five year modification plant for the Brunswick Plant.
Final acceptance of the licensee * s design reanalyzes of masonry walls and the schedule for implementation of required repairs is documented in a Safety Evaluation Report (SER), dated January 30, 1985.
The inspector examined plant modifiestion numbers PM 84-384 and 84-385 which implemented n.odifications to masonry wall numbers 6b, 6, 8a, 8c,
and 8d, in the control building (PM 84-384) and wall numbers 6a, and 9e, in the diesel generator building (PM 84-385). The inspector examined the complete documenta tion packages for PM 84-384 and 385.
These packages included design drawings, design changes, QC inspector records, and the licensee's safety evaluations. The inspector made-~a detailed review of QC inspection records including inspection of welding, structural steel erection, expansion anchor installation, and grouting. The inspector also walked down wall numbers 6a and 9e in the diesel generator building and wal1 numbers 8a and 8d in the control building and examined the completed
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modifications.
Based on the walkdowns and review of the inspection records, the inspector concluded that the modifications were completed in accordance with the design requirements.
However, discussion with licensee engineer and review of QC inspection records and various site procedures used to control implementation of plant modifications disclosed the following unresolved item.
The records documenting inspection of welds for the wall modifications consist of a stamp on the drawing which is initialed and datec' by the QC inspector. Discussion with QC inspector personnel and licensee engineers disclosed that this stamp is the only record documenting that the all welds on the drawing were completed in accordance with licensee procedures, specifically BSEP specification 005-010, Visual Weld Acceptance Criteria, CP&L procedure number OSPP-WLD 601, General Welding Procedure, and BSEP Specification 248-107, Instal-lation of Seismic Pipe Supports and Miscellaneous Structural Steel.
The inspector questioned the licensee inspectors regarding records identifying the welder, and documentation of fitup inspection for welds, when
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required, and visual inspections of individual welds on the design drawings.
Licensee personnel informed the inspector that these. records are disposed of 'af ter the "QC Accepted" Stamp is ' affixed to the drawing.
-Review of the procedure listed above disclosed that this method for
' documentation of weld inspections is not specified in a procedure.
This a'ppears to. be in conflict with licensee's commitments for future structural work (plant modification) to Regulatory Guide 1.94 and ANSI N45.2.5-1974 contained in FSAR Section 1.8 and the requirement of Appendix B to 10 CFR 50.
Pending a review of QC inspection procedures used for inspection of plant modification, and records documenting these inspections, this item was identified to the licensee as Unresolved Item 325, 324/88-22-01, Determine-Adequacy of QC ' Inspection Procedures for Inspection of Plant Modifications and Determine Adequacy of Quality Records Documenting Inspection of Modifications with the close out of PM 84-384 and 385, the modifications to masonry walls required by IEB 80-11 are-completed.
Based on review of the licensee's actions to complete IE Bulletin 80-11 requirements during inspections which are documented in NRC Inspection Report Numbers 50-325, 324/88-22, 85-27, 85-40, and 87-16, and review of the licensee's design evaluations by the NRC office of Nuclear Reactor Regulation, IE Bulletin 80-11 is' closed.
Within the areas insp.ected, no violations or deviation were identified.
4.
Exit Interview The inspection scope and results were summarized on June 17, 1988, with
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those persons indicated in paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection findings listed below.
The licensee did not identify as proprietary any of the material provided to or reviewed by the inspectors during this inspection.
Dissenting comments were not received from the licensee.
Unresolved Item 325, 324/88-22-01, Determine Adequacy of QC Inspection Procedures for Inspection of Plant Modifications. Determine Adequacy of Quality Records Documenting Inspection of Modifications.
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