IR 05000498/1989005
| ML20235Y775 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/03/1989 |
| From: | Bundy H, Mckernon T, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20235Y765 | List: |
| References | |
| 50-498-89-05, 50-498-89-5, 50-499-89-05, 50-499-89-5, NUDOCS 8903140566 | |
| Download: ML20235Y775 (6) | |
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dPPENDIX
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y U.S. NUCLEAR REGULATORY COMMISSION.
' REGION IV
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.NRC Inspection Report: "50-498/89-05 Operating Licenses:
NPF-76-H-
50-499/89-05'
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NPF-.78
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g-Dockets:
50-498" 50-499 <
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Licensee:
Housto'n Lighting &- Power Company f
P.O. Box 1700
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Houston,-Texas 7700,11 Facility Name:
South Texas Project (STP),. Units' 1 and 2
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Inspection At: - STP, Matagorda County, Texas-Inspection Conducted:
February-13-17, 1989 Inspectors:'
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T'.' D. McKernon, Reactor Inspector, Test lDate Programs Section, Division of' Reactor Safety.
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Date 6.F.Bundy, Reactor. Inspector,TettPrograms Section, Division of Reactor Safety =
Accompanied By:
W._C. Seidle, Chief, Test Programs:Section Division of Reactor Safety'(February 16-17,1989)
Approved:
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M C. Seidle, Chief, Test ProgramqVSection Date C' ision'of Reactor Safety e
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8903140566 890303
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PDR ADOCK 05000498
O PDC
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-2-Inspection Summary Inspection Conducted February 13-17, 1989 (Report 50-498/89-05)
Areas Inspected:
Routine, unannounced inspection of STP,. Unit 1 including startup and core physics testing.
Results:
The licensee had complied with license commitments.in the areas of startup and low power physics testing reviewed by the NRC inspectors. Testing
- had been performed in accordance with the licensee's precedures to verify compliance with the Technical Specifications (TS) and vendor design criteria.
The reactor performance staff displayed extensive knowledge of core physics parameters and test procedure requirements during interviews with the NRC inspectors.
No violations or deviations were identified.
Inspection Conducted February 13-17, 1989 (Report 50-499/89-05)
Areas Inspected:
No inspection of STP, Unit 2, was conducted.
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DETAILS
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Persons Contacted
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- W. H. Kinsey, Plant Manager s g'
- S. L. Rosen, General Manager, Operations Support r.
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- S. M. Dew, Operations Support Manager
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- J.. E. Geiger, General Manager, Nuclear Assurance'
- J. W. Loesch,' Plant Operations Manager i
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- D. A. Leazar, Reactor Support Manager
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- S. M. Head,. Supervising Licensing Engineer
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- C. B. Thiele, Reactor Performance Supervisor K. Mulligan, Reactor Engineer
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City of Austin Electric Utility
- J. Neeley, Engineer NRC
- J. E. Bess, Senior Resident Inspector, Unit 1
- J. I. Tapia, Senior Resident Inspector, Unit 2 The NRC inspectors also interviewed other licensee employees during the inspection.
- Denotes those attending exit interview conducted on February 17, 1989.
2.
Startup Testing (72700)
The NRC inspectors reviewed the vendor core design report and the reactivity control systems, power distribution limits, and instrumentation sections l
of the.TS.
The NRC inspectors then reviewed licensee procedure and test l
results related to startup and core physics testing during Cycle l' operation.
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The review included verification of test results for control rod drive and control rod position indication checks, which included periodic control
. rod drop timing, and reactor thermocouple / resistance temperature detector (RTD) cross calibration.
Other procedure and test results evaluated and discussed in more detail in the following subparagraphs included surveillance of core power distribution limits, calibration of nuclear instrumentation (NI) systems, core thermal power evaluations, and determination.of reactor shutdown margin.
During the inspection, the NRC inspectors reviewed the following procedures:
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1 PEP 04-ZL-0024. Revision 2, " Rod Drop Time Measurement (Cold, Full.
Flow)," dated October 29, 1987
'1 PEP 04-ZL-0024, Revision 3, " Rod Drop Time Measurement (Hot', Full Flow)," dated October 22, 1988 1 PSP 03-RS-0001, Revision 2, " Monthly Control Rod Operability," dated February-September,,1988
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1 PSP 10-RC-0002, Revision 1, " Core Exit Thermocouple /RTD Cross Calibration," dated October 6,1988
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1 PSP 05-NI-0041A, Revision 0, "NIS Axial Flux Difference," dated July 2, 1988 OPSP-NI-0001, Revision 1, " Daily Power Range NI Channel Calibration,"
dated May-June,'1988 1 PSP 05-NI-0041, Revision'1, " Power Range Neutron Flux Channel Calibration," dated July.2, 1988 OPEP02-ZG-0010, Revision 5, " Calorimetric Calculation," dated October 2, 1988, During the review, the NRC inspectors verified that the stated procedural objectives were met, acceptance criteria for tests were met, changes to procedures and tests were satisfactorily approved, reviewed and incorporated, test results were adequately reviewed, and test deficiencies were satisfac-torily dispositioned.
Review of control rod drop time test results at both hot and cold, full' flow conditions indicated that all control rods satisfied the TS acceptance criteria (i.e., rod drop time <2.8 seconds).
Those control rods with drop times greater than two standard deviations from the group mean drop time were retested to verify data consistency and control rod operability.
Retest results were acceptable.
The licensee's
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control rod operability surveillance test (TS 4.1.3.1.2) indicated control rods were satisfactorily tested for the period sampled.
In addition, the NRC inspector reviewed test result evaluations for core exit thermocouple (CET)/RTD cross calibration.
The licensee correctly verified'
and calibrated CETs and RTDs to within the stated acceptarce' criteria, a.
Surveillance of Core Power Distribution Limits (61702)
The NRC inspector verified that the licensee was using approved data analysis codes for processing information obtained by the movable incore instrumentation.
These codes were discussed in the vendor, core analysis report.
Calculations of power distribution limits were performed in accordance with Procedure OP5P10-II-0003, " Determination of Limiting Hot Channel Factors and Axial Offset." This procedure l
accomplished the following:
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Verified that the heat flux hot channel factor was within the limits of TS L 2.2'
Verified that:the nuclear enthalpy rise hot channel factor was within limits'of TS 3.2.3 Compared _the incore axial flux. difference to excore axial flux difference in accordance with TS 4.3.1.1, Table 4.3-1, Item 2a, Note.(3)
The NRC inspector reviewed completed test result packages for Procedure OPSP10-II-0003 for the period April to September 1988.
All packages had been reviewed and approved by the licensee.
The procedure had been followed for each test.
In the few instances in which the limiting conditions for operation were_not satisfied, the correct actions were completed.
Calibrations required by TS 4.3.1.1 were satisfactorily completed.
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Calibration of Nuclear Instrumentation Systems (NIS) (61705)
The NRC inspector reviewed test results and procedures for NIS axial flux difference determination, daily power range NI channel calibration, and power range neutron flux' channel calibration.
The NRC inspector verified that the correct procedures-were approved and used.
Test results satisfied the stated acceptance criteria and, where necessary, accuracies of trip set points, alarms and signal processing equipment were reestablished.
Furthermore, test result evaluaM ons were sufficiently reviewed and deficiencies correctly dispositioned.
c.
Core Thermal Power Evaluation (61706)
During this portion of the inspection, the NRC inspector reviewed result evaluations for calorimetric calculations.
The NRC inspector reviewed a 2-month sampling of core thermal power calculations to verify that-nuclear instrumentation power range level compared to the secondary side heat balance calculations within a + 1 percent acceptance criteria.
Furthermore, the NRC inspector verified that
.the licensee completed required signoffs, satisfied stated prerequisites', and correctly reviewed and approved changes to the test procedure, d.
Determination of Reactor Shutdown Margin (61707)
The NRC inspector verified that the licensee had maintained the required shutdown margin in Modes 3, 4, and 5 during the period of i
February to October 1988.
The shutdown margin calculations were performed in accordance with Procedure OPSP10-ZG-0003, " Shutdown l
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-Margin Verification - Modes 3,'4',;and 5."
The'proceduretappeared to
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correctly consider.all required factors.. Tests results were. reviewed
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.and approved-in each instance.
There were no instances:in which shutdown margin' requirements were'not-' satisfied.
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Exit Interview.'-
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The NRC inspectors met with the licensee representatives denoted in paragraph 1 on February 17; 1989, and. summarized the scope and findings of-
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this inspection.
Proprietary materials prov.ided to the inspectors were.-
returned at'the conclusion of the inspection and none of their contents are reproduced in this report.
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