IR 05000400/1986012

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Insp Rept 50-400/86-12 on 860221-24.No Violations or Deviations Noted.Major Areas Inspected:Reactor Containment Bldg Structural Integrity Test & Quality Records Pertaining to Pipe Vibration Tests
ML20140B624
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 03/10/1986
From: Jape F, Lenahan J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20140B600 List:
References
50-400-86-12, NUDOCS 8603240251
Download: ML20140B624 (5)


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UNITED STATES NUCLEAR REGULATORY COMMISSION

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Report No.:

50-400/86-12 Licensee: Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Docket No.: 50-400 License No: CPPR-158 Facility Name: Harris Inspection Conducted: Februar 21-24, 1986 Insp tor:,

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.J. Lenahan

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Date Signed Approved by:

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F. Jape, Section Thief, Test Program /

Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope:

This routine unannounced inspection involved 29 inspector-hours on site in the areas of observation of the reactor containment building structural integrity test and quality records pertaining to piping vibration tests.

Results: No violations or deviations were identified.

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REPORT DETAILS 1.

Persons Contacted i

Licensee Employees

  • N. J. Chiangi, Manager, Quality Assurance / Quality Control (QA/QC),

r Harris Project

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B. Clark, Start-Up Engineer

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  • C, S. Hinnart, Manager, Start-Up P. M. Inman, Design Specialist, Start-Up
  • R. A. Watson, Vice-President, Harris Nuclear Project
  • H. L. Williams, Project Engineer, Harris Project Engineering Section
  • J. L. Willis, Plant General Manager Other licensee employees contacted included two engineers and two techni-

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cians.

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Other Organizations EBASCO T. J. McCarthy, Civil Structural Design Supervisor J. Manchak, Civil Structural Design Supervisor

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M. Weber, Supervisory Civil Engineer

Wiss, Janney, Elestner and Associates (WJE)

T. Brown, Supervisory Engineer G. Hedien, Structural Engineer R. Krouse, Structural Engineer NRC Resident Inspectors

  • S. P. Burris
  • P. G. Humphrey
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on February 24, 1986, with those persons indicated in paragraph 1 above.

The inspector described the areas inspected and discussed in detail 'the inspection findings.

No dissenting comments were received from the licensee.

l The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspection.

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3.

Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.

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4.

Unresolved Items Unresolved items were not identified during the inspection.

5.

Containment Structural Integrity Test (63050)

The inspector examined the containment building Structural Integrity Test (SIT), observed portions of the SIT, and reviewed test data.

Acceptance criteria utilized by the inspector appear in Final Safety Analysis Report (FSAR) Sections 3.8.1.7, 14.2.12.1.42, and Regulatory Guide 1.18.

a.

Review of SIT Procedures The inspector examined the following procedures which control activi-ties for the SIT:

(1) EBASCO Specification CAR-SH-CH-22, Structural Integrity Test of Concrete Containment Structure, Instrumentation, Deflection Measurement, Crack Pattern Mapping, Strain Measurements, Tempera-ture Measurements, and Test Data Analysis.

(2) CP&L Procedure WP-59, Structural Integrity Test Procedure.

(3) WJE Procedure OP-2, Inspection, and Verifying the Accuracy of Testing Equipment, Devices, and Instruments used in Testing Operations.

(4) WJE procedure OP-37, Structural Integrity Test for Harris Nuclear Plant.

These procedures specified type, location, and accuracy of instrumenta-tion, pretest requirements, the test method, test pressure (1.15 times design pressure per RG 1.18), measurement of concrete deflections (including mapping of crack patterns) and analysis of test date.

b.

Witnessing of SIT The inspector witnessed approximately 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of the SIT from test pressure of 18.0 psig to maximum test pressure of 51.85 psig and depressurization to 35.0 psig, for start of the integrated leak rate test.

Crack patterns were mapped prior to pressurization and at the maximum test pressure.

The inspector observed mapping of cracks at several locations at maximum test pressure.

The inspector verified dimensions of several cracks and the accuracy of recording the crack locations.

Strain data and radial and vertical deflections were recorded at required locations and intervals. Test pressures were held at the specified increments for the required time periods.

Licensee

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and EBASCO structural engineers continuously monitored performance of the SIT crew and recording of test data during the SIT. Test data was reviewed by the structural engineers during the test to verify that deflections were within predicted value.

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c.

Review of Test Records The inspector examined the following records relating to the SIT:

(1) Pretest calibration of direct reading pressure gages, serial numbers 3308 and 25835 (2) Calibration records of extensometors, numbers 13, 19, 33, 74, 81, 2705, 2708, 2729, 2739, and 2749.

(3) Strain and deflection data collected at pressure of 0 psig, 20 psig, 40 psig and 51.85 psig.

Measured deflections and strains were generally less than two-thirds of those predicted by EBASCO design engineers in report

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titled, " Predicted Behavior of Containment Building During Structural Integrity Test".

(4) Crack pattern mapping at pressures of 0 psig and 51.85 psig.

Cracks sites were less than predicted.

Within the areas inspected, no violations or deviations were identi-fled.

6.

PipingVibrations(70370)

The inspector reviewed piping vibrations test procedures and test data.

Acceptance criteria utilized by the inspector appear in FSAR Sections 3.9.2.1 and 14.2.12.1.12.

a.

Review of Piping Vibration Procedures The inspector examined the following procedures:

(1) Procedures number 1-2005-P-05, Piping System Steady State Vibra-tion Test (2) Procedure number 1-2005-P-06, Piping System Transient Vibration Test These procedures provide instructions for verifying the acceptability of the response of piping to steady state and transient vibrations.

During review of the above procedures, the inspector verified that test prerequisites and acceptance criteria were specified and that test instructions and objectives were clearly stated.

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b.

Review of Test Results The inspector reviewed the following records pertaining to piping vibration tests:

(1) Results of steady state vibration tests performed on reactor coolant, residual heat removal, chemical and volume control, and sampling system piping.

(2) Results of transient vibration testing performed on reactor coolant piping, loops, A, B, and C, for reactor coolant pump trips and starts.

(3) Results of transient vibration testing performed on auxiliary feedwater piping for auxiliary feedwater pump trip and start.

Within the areas inspected, no violations or deviations were identified.

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