IR 05000324/1978019
| ML20062B568 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/20/1978 |
| From: | Kellogg P, Ouzts J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20062B567 | List: |
| References | |
| 50-324-78-19, 50-325-78-19, NUDOCS 7810310134 | |
| Download: ML20062B568 (8) | |
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paasCu uNtTED STATES
[c, NUCLEAR REGULATORY COMMISSION
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e REGloN If Ii7 g
101 M ARIETTA STREET, N.W.
- f AT1.ANTA. GEORGI A 30303
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Report Nos.: 50-324/78-19 and 50-325/78-19
- - Docket Nos.: 50-324 and 50-325 License Nos.: DPR-71 and DPR-62 Licensee: Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Brunswick Units 1 and 2 Inspection at: Southport, North Carolina Inspection conducted: August 8-11, 1978 Inspector:
J. E. Ouzts Reviewed by: N' '
/M Ye..
k!N!77 NuclearSuppor[tSectionNo.2 P. J. Kellogg,, Chief (
' Date Reactor Operations and Nuclear Sucport Branch i
Insoection Sugmary j
Inspection on Aucust 8-11, 1978:
(Recort Nos. 50-324/78-19 and
50-325/78-19 Areas Insoected: Routine, unannounced inspection of calibration, surveillance, procurement, design changes and modifications for Units 1 and 2.
The inspection involved 28 inspector-hours on site by one NRC inspector.
l Results: Within the four areas inspected, no items of noncompliance or deviations were identified.
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RII Report Nos. 50-325/78-19 and 50-324/78-19 I-1 DETAILS I Prepared by: I[
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J. E. Ouzts, ReagAor Inspqstor Date
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Nuclear Support Section No. 2
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Reactor Operations and Nuclear Support Branch Dates of Inspection: August 8-11, 1978 Reviewed by: l.
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9/u/M P.J.Kellogg,{blef
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'Date Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted
- A. C. Tollison, Plant Manager
- W. R. Allen, Stores Foreman
- R. Creech, I&C Foreman
- K. E. Enger, Administrative Supervisor
- J. L. Kiser, RC&T Jr. Engineer
- G. A. Kohans, RC&T Foreman
- J. McKnight, RC&T Foreman
- R. Pasteur, RC&T Foreman
- L. A. Rogers, NRC Coordinator
- S. E. Thorndyke, Operating Supervlaor
- D. C. Smiley, RC&T Technician
- L. Tripp, Acting E&RC Super:isor W. M. Tucker, Technical and Admicistrative Superintendent
- J. M. Waldorf, Project Engineer Seven I&C Technicians and two mechanics were also contacted.
- Denotes those attending exit interview.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unreso!ved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliacce or deviations. One unresolved item disclosed during the inspection is discussed in paragraph 8.
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l RII Report Nos. 50-325/78-19 and 50-324/78-19 I-2 j
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Exit Interview
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The inspector met with licensee representatives (denoted in paragraph 1)
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at the conclusion of the inspection on August 11, 1978. The inspector summarized the scope and findings of the inspection as discussed in paragraphs 5, 6, 7, 8 and 9.
The licensee acknowledged the inspection
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findings, and agreed to investigate his method of handling the stamping of design drawings affected by design changes and modifications, in order to reduce the time to stamp the drawing that a modification to the drawing is outstanding.
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5.
Instrumentation Calibration Program Verification The inspector conducted a review of the following calibration procedures and associated test results:
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PT1.1.1 - Reactor High Pressure Trip Channel Calibration
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PTI.1.3 XC - High Drywell Pressure Channel Calibration and Functional
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Test PT1.1.4PC - Reactor Low Water Level No.1 Channel Calibration
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PT1.1.4 XC - Reactor Low Water Level No. 1 Channel Calibration
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and Functional Test
PT1.1.18PC - APRM Rod Block Channel Calibration
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PT1.2.3PC - APRM 15% Neutron High Channel Calibration
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PT1.5PC - RBM Channel Calibration
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PT1.8(1.8D) - APRM Calibration
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PTI.9 - LPRM Calibration
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PT2.1.4 PC - Reactor Low Water No. 2 Channel Calibration and
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Functional Test PT2.1.17PC - Steam Line High Flow Channel Calibration and Functional
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Test PT2.1.26PC - Main Steam Line Low Pressure Channel Calibration and
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Functional Test
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RII Report Nos. 50-325/78-19
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and 50-324/78-19 I-3
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PT3.1.2PC - CST Low Water Channel Calibration and Functional Test i
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PT3.1.6PC - High Drywell Pressure Spray and Functional Test
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PT3.1.7PC - Reactor Low Water Level No. 2 and No. 3 Channel
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Calibration and Functional Test
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PT3.1.12PC - Core Spray Pump Discharge Pressure Interlock Channel
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Calibration PT3.1.14 - Reactor Low Pressure Channel Calibration Functional
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Test PT3.1.14 XC - Reactor Lou Pressure Channel Calibration and Functional
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Test PT3.1.14 XC - Reactor Low Pressure Channel Calibration and Functional
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Test PT11.1.4PC - Drywell Pressure Channel Calibration
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PT50.5 - Total Core Flow Calibration I
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PT55.1PC - Drywell Pressure Loop Calibration
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PT2.1.5PC - RCIC Turbine Steam Line Low Pressure Calibration and
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Channel Functional Test
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The procedures and calibration results were reviewed to verify:
Reviews and approvals were being conducted and data were recorded
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and evaluated.
Test instruments were listed and identified in test results.
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Adherence to Technical Specifications requirements and limiting
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conditions for operations were observed.
Technical contents were correct and verification of return of
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equipment to service and removal of test equipment was being done.
The inspector conducted an inspection of measuring and test equipment laboratory facilities and reviewed records as follows:
Instrument and Control Standards Laboratory
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Measuring and Test Tool Storage and Issuing Room
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RII Report Nos. 50-325/78-19 and 50-324/78-19 I-4 These facilities were inspected to verify:
That standard test instruments were labeled and included in the Q
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equipment calibration program.
Instruments were calibrated on schedule and labeled with calibra-
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tion status.
Storage facilities were proper for protecting the equipment.
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Nonconforming equipment was being tagged and provided with segre-
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gated storage.
Certification and calibration records were available and being
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maintained for measuring and test equipment.
The inspector used one or more of the following acceptance criteria for evaluating the above items in the calibration program:
Corporate Quality Assurance Program - Section 6
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Technical Specifications (3/4.3)
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ANSI N45.2 (1971) (13)
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ANSI N18.7 (1972) (5.2.2) (5.2.16) (5.3.6)
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Inspector Judgement
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Within the areas inspected no items of noncompliance or deviations were identified.
6.
Inspection of Chemistry Laboratory An inspection of the chemistry laboratory and associated equipment was conducted by the inspector to verify that procedures and equipment were available for determining coolant chemical analysis as required by Technical Specifications. The method of preparation and verifica-tion of shelf life of chemicals were also reviewed.
The inspectors used one or more of the following acceptance criteria for evaluating the above items in the chemistry control program:
Technical Specification Requirements
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RII Report Nos. 50-325/78-19 and 50-324/78-19 I-5 Quality Assurance Program
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Inspector Judgement
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Within the areas inspected no items of noncompliance or deviations were identifiec.
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Procurement Control Verification The inspector conducted a review of procurement documentation and inspected storage of safety-related equipment as follows:
PO-214-2 - Five Control Rods - General Electric
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PO 642157 #3 - 1 each - Rod Worth Minimizer - PCB S/N 6 -
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General Electric PO 645479 - Pump Parts - Pacific Pu=p Division
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PO 677537 - Strainer for CRD - General Electric
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PO 687402 - Rod and Tube - 3 Each Piston Tube - General F.lectric
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PO 686009 - 30# Welding Rods - Teledyne
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PO 681257 - One Target Rock Relief Valve - Wyle Laboratories
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PO 67982 - One Thermal Barrier - Bingham Williemette Company,
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Portland, Oregon Items Inspected in Storage:
CRD Cylinder
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CRD Connector
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Diesel Engine Connecting Rod
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The inspector used one or more of the following acceptance criteria for inspecting the above items:
Corporate Quality Assurance Program, Section 4.0
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ANSI N18.7 (1972) (5.2.13)
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l RII Report Nos. 50-325/78-19 and 50-324/78-19 I-6 ANSI N45.2 (1971) (5) (14)
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Regulatory Guide 1.38 (1973)
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Inspector Judgement
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The procurement documents and components were reviewed and inspected to verify:
Procutement documents had proper approvals.
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Quality Control inspection requirements were included in the
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procurement documents Quality control records, such as; Certificate of Compliance,
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Certificate of Test and Analysis, Results of Vendor Tests and Receipt Inspection records were available for equipment in storage.
Measures were in effect for properly controlled and separation of
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conforming and conconforming materials, parts and components.
Components and materials were supplied by an approved vendor.
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Within the areas inspected no items of noncompliance or deviations were identified.
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Design, Design Changes and Modifications Control Verification The inspector conducted a review of design change and modification documentation to insure:
Design changes were made in accordance with 10 CFR 50.59.
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Reviews and approvals were in accordar.ce with Technical Specifica-
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tions and established Quality Assurance program.
Design changes were conducted in accordance with formal procedures
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that included, identification of codes, inspection requirements and acceptance standards.
Procedures and drawings were revised to reflect modifications and
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design changes.
The inspector used one or more of the following acceptance criteria for inspecting the above items:
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RII Report Nos. 50-325/78-19 and 50-324/78-19 I-7 Corporate Quality Assurance Program, Part 3.0
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ANSI N45.2 (1971) (4.3) (4.4)
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Technical Specifications - Part 6.5
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ANSI N18.7 (1972) (5.2.7)
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Inspector Judgement
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Within the areas inspected no items of noncompliance or deviations were identified. In one area the inspector found design drawings were not being promptly stamped to reflect modifications to some systems and to reference the design changes made in the modification package.
The licensee agreed to investigate a method for more promptly getting these drawings stamped. This item will remain unresolved pending corrective action and verification by NRC at a subsequent inspection.
024/325-78/19-0D 9.
Inspection of Control Room Operations The inspector toured the control room to inspect the plant status and verify operations were in accordance with the license requirements.
The status of safety systems and calibration testing in progress were reviewed and discussed with the shift foreman.
During this tour of the control room and discussions with the shift foreman no items of noncompliance or deviations were idastified.
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