IR 05000327/1979050
| ML19256E736 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/04/1979 |
| From: | Burnett P, Sauer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19256E734 | List: |
| References | |
| 50-327-79-50, NUDOCS 7911150109 | |
| Download: ML19256E736 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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REGION il 0,
101 MARIETTA sT., N.W SUITE 3100
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ATLANTA. GEORGIA 303o3 g*****
s Report No. 50-327/79-50 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name: Sequoyah Docket No. 50-327 License No. CPPR-72 Inspected at Sequoyah Site ne-f Chattanooga, Tennessee
/0!V/7 C Inspected by:
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R. C. Sauer Date Signed
Approved by:
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P. T! Bu'r'netC," Acf.ing Section Chief, RONS Branch Date Sifned SUte!ARY Inspected on September 19-21, 1979 Areas Inspected This routine, unannounced inspection involved 21 inspector-hours onsite in the
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areas of startup procedure review and health physics and security training for badging.
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j Results Of the two areas inspected, no items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted Licensee Employees
- J. Ballentine, Plant Superintendent
- W. Andrews, Site QA Staff Supervisor R. Fortenberry, Reactor Engineer
- W. Kinsey, Jr., Assistant Power Plant Results Superintendent
- S. Wilburn, Assistant Pre-op Test Supervisor (Exit only)
NRC Inspectors
- W. Cottle, Resident Inspector
- T. Donat, USNRC, Region II
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- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 21, 1979 with those persons indicated in Paragraph I above. Regarding the selection of a range of chi-squared values to evaluate source range counter behavior during initial fuel loading and initial criticality the licensee representa-
- i'e agreed to revise procedures SU-6.1 and SU-7.2 as discussed in paragraph 5
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'79-5 0-01).
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m on Previous Inspection Findings
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.ved Item (327/79-16-04): Revision of procedure SU-7.2 to is r,c c e.1. in o the calibration of the reactivity computer negative reacti-u..r. io i Revision 2 to SU-7.2 was reviewed by the inspector and a :eptab: a.
olt-1 Items
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is. esolted items were not identified during this inspection.
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Startup Procedure Review
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The inspector reviewed the following startup procedure as to technical content and
.nsure Technical Specification requirements and other commit-ments were met.
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SU-6.2, Rev 4 " Core Loading Prerequisites" SU-6.3, Rev 2 " Reactor Syst. ems Sampling Prior to and During Core Loading" SU-7.2, Rev 2 " Initial Criticality"
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SU-8.1, Rev 2 " Power Coefficients and Integral Power Defect Measurement"
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SU-8,5.1, Rev 1 "Statepoint Data Collection and Thermal Power Measurement" SU-8.6B, Rev 2 " Axial Xenon Oscillation" In addition, the inspector reviewed licensee action on items of concern involving SU-7.2, previously identified in inspection report number 327/79-16.
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(Closed) Open Item (327/79-16-01): Revision of procedure SU-7.2 to reduce the boron dilution rate during initial approach to critical, and to further reduce the dilution rate once an inverse multiplication of.1 is obtained. Revision 2 to SU-7.2 was reviewed by the inspector and found to adequately address these concerns.
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(Closed) Open Item (327/79-16-02): Revision of SU-7.2 to include signature spaces for completion of major action steps and to require that data sheets and plotted graphs have signature spaces to identify the persons taking or plotting the data. Revision 2 to SU-7.2 added additional signature : paces and deleted attached graphing figures once required by the procedure to eliminate the noted discrepancies.
In noting the graph figure deletion the inspector requested the licensee to incorporate a statement in the procedure to ensure handplots required by the procedure are attached to the completed procedure.
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(Closed) Open Item (327/79-16-03): Revision of SU-7.2 to provide for the determination of source and intermediate nuc1rar instrument range overlap as soon as practical after obtaining initial criticality.
Revision 2 to SU-7.2 was reviewed by the inspector and found acceptable.
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(Resolved) Resolution to inspector identified item (327/79-16 paragraph 7.b): The need for quantitative acceptance criterion on boron concen-tration for initial criticality with D bank at a nominal 160 steps.
Revision 2 to SU-7.2 added an additional step to Section 6.0, Acceptance Criteria, specifying an acceptable range of critical boron concentration with bank D at 160 steps.
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(Resolved) Resolution to inspector identified item (327/79-16 paragraph 7.c): Licensee identification of a method to satisy the requirement of the Operational Quality Assurance Manual that the signal-to-noise ratio of the start-up neutron detectors will be greater than two during the initial approach to criticality.
In order to meet this commitment, the licensee has elected to perform a Chi-square test to cvaluate source range counter behavior.
Inspector review of the Chi-square test presented in SU-7.2 and SU-6.1
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Rev 5 " Initial Core Loading" identified that the licensee had selected
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only an upper limit to the measured Chi-square distribution. The purpose in performing a Chi-squared test is to check the consistency of counting data, or, inversely to check the reliability of the counter. Thus, a range of Chi-square values should be selected and those values which
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fall outside this range should be rejected since the measured count rates are inconsistent.
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_3-The licensee representative indicated the procedures would be revised to incorporate a range of acceptable Chi-square values. This item is identi-fled for future inspector review (327/79-50-01).
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Security and Health Physics Training the inspector underwent the extensive security and health physics training program which all personnel entering the Sequoyah Nuclear Power Station for permanent badge status must receive. The inspector had no questions in this area.
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