IR 05000324/1978022

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IE Insp Rept 50-324/78-22 & 50-325/78-22 on 780925-27. Noncompliance Noted:Failure to Prepare & Implement Procedures,Paragraph 4.b
ML19256B041
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/17/1978
From: Gibson G, Hutman J, Montgomery D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19256B036 List:
References
50-324-78-22, 50-325-78-22, NUDOCS 7901170429
Download: ML19256B041 (5)


Text

101 MARIETT A STREET.N.W.

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Report Nos.

50-324/78-22 and 50-325/78-22 Docket Nos.-

50-324 and 50-325 License Nos.

DPR-71 and DPR-62 Licensee: Carolina Power and Light Company Facility Name: Brunswick Units 1 and 2 Inspection at : Brunswick Site, Southport, N. C.

Inspection conducted: September 25-27, 1978 Inspectors:

G. T. Gibson D. M. Montgomejy

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Reviewed by I k. fluf ham, Chief

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Environmental and Special Projects Section

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Fuel Facility and Materials Safety Branch Inspection Summary Inspection on September 25-27, 1978 (Report Nos. 50-324/78-22 and 50-325/78-22)

Areas Inspected:

A routine unannounced confirmatory measurements inspection involving: examination of licensee analytical equipment; review of quality assurance audits; review of quality control in analytical measure-ments, and collection of actual plant ef fluent samples for future comparisons of analytical results.

The inspection involved 32 inspector-hours onsite and ' i ispector-hours of f site, by two NRC inspectors.

Reselts: Of the five areas inspected no items of noncompliance or deviations were observed in four areas. One item of noncompliance (inf raction: failure to prepare and implement procedures, paragraph 4.b) was identified in one area.

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RII. Report Nos.

50-324/78-22 and 50-325/78-22-2-l DETAILS I Prepared by:

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Gibs n, Radfa non Specialist Date Environmen and Special Projects Section Fuel Facility and Materials Safety Branch Dates of Inspection:

dtember 25-27, 1978.

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Reviewed by: f

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J. W.'Hufham, C.F.ief

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- o (,t W Environmental and Special Projects Section Fuel Facility and Materials Safety Branch 1.

Persons Contacted A. F. Tollison, Plant Manager

  • M. Brown, Technical and Administrative Supervisor
  • A. Padgett, Environmental and Radiation Cont rol Supervisor
  • L. Tripp, Acting, E & RC Supervisor
  • G. McCoy, Engineering Technician
  • R. Pasteur, Chemistry Foreman
  • G. Warriner, Senior Engineer W. Dorman, QA Specialist J. McKnight, Health Physicist
  • denotes those present at the Exit Interview.

2.

Licensee Action on Previous Inspection Findings No previous enforcement matters were within the scope of this inspectnon.

3.

Unresolved Items No unresolved items were identified during this inspection.

4.

Radiochemistry Procedures a.

The inspectors reviewed the licensee's radiochemistry program, reviewed the Radiation Control and Test Instruction procedures (Series 5000), and discussed with licensee personnel the imple-mentation of the radiochemistry and reactor coolant chemistry analysis programs. The inspectors noted the licensee's procedures were approved and reviewed as per Technical Specification 5..

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RII. Report Nos.

50-324/78-22 and 50-325/78-22-3-b.

The inspectors noted on September 26, 1978, that contrary to Appendix B, Technical Specification 5.3.1, requiring written procedures to be prepared, implemented and maintained, including quality assurance procedures for analysis of samples, the licensee did not have an approved, written procedure covering the operation and calibration of the current ND6600 gamma spectroscopy system.

In addition, during a review of RC&T procedures #5102, #5103,

  1. 5201, #5203, #5302, #5304 and #5401, the inspectors noted that current licensee radiochemistry program practices differ from the referenced procedure specifications.

This item constitutes an item of noncompliance with the referenced Technical Specification.

(324 7

'-01 and 325-78-22-01)

c.

The s. etors discussed with licensee personnel the discrepancies obse.

in the program.

Licensee personnel concurred with the inspectors that changes to the program had been made without keeping the procedures current. Although these modifications in the licensee's program were evaluated by the inspectors to be generally acceptable, instances were identified in which analytical systems were r.ot kept in accordance with industry-accepted practices and possible r.onconservatise results may have occurred.

5.

Radiochemistry Equipment and Instrumentation The inspectors examined the licensee's chemistry and radiochemistry laboratory, instrumentation and equipment. The inspector's noted the licensee did not have a current program for control of the analytical balances in the chemist ry lab, which are used to prepare calibration standards. Licensee personnel stated the balar.ce; are scheduled to be included in the Quality Assurance program, " Measuring and Test Equipment" (10 CFR 50, Appendix B, Criterion XII). This item shall be considered an open item and examined during a subsequent inspection (324-78-22-02 and 325-78-22-02 ).

6.

Quality Assurance Audits The inspectors examined the results of the Operations Quality Assurance Surveillance (0QAS) and Quality Assurance Audits (QAA) audit numbers 0QAS-77-11 and QAA 21-6, 21-7, 21-8, and 21-9, respectively.

The inspectors noted that recommendations identified in the audits were promptly corrected by appropriate licensee personnel. The inspectors had no f urther questions regarding this ite *

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RIl. Report Nos.- 50-324/78-22 and 50-325/78-22-4-7.

Analytical Measurements The inspectors examined liquid waste release documentation for the months of September and October 1978, regarding gamma spectroscopy records.

The inspectors observed that the analyses and analytical sensitivity limits of Technical Specifications Table 3.5-1 were met for the records reviewed.

The inspectors had no further questions regarding this item at this time.

8.

Conf i rmatory Measurements The inspectors collected an actual plant steam-jet air ejector (SJAE)

waste gas, liquid waste tank, building particulate filter, and charcoal adsorber ef fluent samples f or confirmatory measurements. These samples were forwarded to the NRC reference laboratory in Idaho Falls, Idaho.

The results of these analyses will be compared with the licensee's results of these samples during a subsequent inspection (324-78-22-03 and 325-78-22-03).

9.

Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1) at the coe lusion of the inspection at the plant on September 27, 1978.

The inspectors summarized the purpose and scope of the inspection and the findiegs.