ML19281A581
| ML19281A581 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/14/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903210333 | |
| Download: ML19281A581 (7) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 500C Chestnut Street Tower II March 14, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
In the Matter of the
)
Docket No. 50-296 Tennessee Valley Authority
)
Enclosed is a summary report of the refueling test program conducted after the Browns Ferry unit 3 fall 1978 outage. This report is in accordance with the requirements of Browns Ferry Technical Specifiestion 6.7.1.a.
Very truly yours, b
$stf J. E. Gilleland Assistant Manager of Power Enclosure C 32(O M 3 sp g An Equal Opportunity Employer k
SUMMARY
REPORT REFUELING TEST PROGRAM BROWNS FERRY NUCLEAR PLANT UNIT 3 - CYCLE 2 ABSTRACT The initial Browns Ferry Nuclear Plant Unit 3 refueling outage was conducted from September 8, 1978, through November 25, 1978.'
This report summarizes those refueling tests performed during the outage and the subsequent Unit 3 startup to full power.
I.
INTRODUCTION On September 8, 1978, Browns Ferry Nuclear Plant Unit 3 was removed from service for its initial refueling outage. During this outage 208 fuel assemblies (8 x 8 design) were replaced by new assemblies (8 x 8R design). In addition, all 43 strings of power range incore detectors were replaced. The recirculation pump trip (RPT) feature was also installed.
The startup tests identified in the Final Safety Analysis Report (FSAR) were addressed, and those which involve areas affected by the outage and its activities were included in the refueling test program. The re-fueling test instructions were prepared by the Results Supervisor, reviewed and recommended by the Plant Operations Review Committee (PORC), and approved by the Plant Superintendent. The Master Refueling Test Instruction (MRTI) has and continues to coordinate and document all test activities from fuel loading to the completion of the program. This instruction provides guidance for the sequence of events, and control points for satisfactory test completion and review prior to pcwer ascension.
5 TABLE 3.1 i
MAJOR EVENTS OF UNIT 3 REFUELING TEST PROGRAM l
Date Event 9/8/78 Beginning of refueling outage 10/29/78 First cycle 2 fuel assembly loaded 11/9/78 Core fully loaded 11/20/78 Open vessel testing complete 11/22/78 Initial critical 11/23/78 Reached rated temperature and pressure 11/25/78 Initial generator synchronization 12/2/78 heatup to 55% power testing complete 12/17/78 Full power first attained
4 II.
REFUELING TEST SUM!ARY (Continued) i 7.
Recire Pump Trip RTI-27 Two-pump trip and turbine trip tests have both been performed.
i 1
Analyses indicate that the criteria have been met satisfactorily.
l f
a i
I i
e
3 II.
REFUELING TEST
SUMMARY
(Continued) f 3.
Control Rod Drive System RTI-5 The following control rod drive system tests were performed before l
t.d after completion of fuel loading:
I A functional test of each CRD to check rod position indication, a.
rod-to-dtive coupling, and insert / withdraw speed.
b.
A continuous-in friction test of each CRD to check for drive line friction.
I I
In addition, all Unit 3 control rods were scram timed at rated vessel
}
pressure. During RTI-5 testing, an LPRM hookup verification is also a
1 performed. During this test it was discovered that the LPRM's were not properly connected. The reactor was shutdown and the problem resolved.
All cri'eria for RTI-5 were satisfied.
4.
Process Computer and Core Performance RTI-13 l
j Verification of the process computer under plant operating conditions I
and an evaluation of the core performance parameters of core flow, core thermal power, core minimum critical power ratio, maximum average planar i
linear heat generation rate, and maximum heat generaticn rate was I
performed. All criteria were satisfied.
5.
Core Power Distribution RTI-18 Transverse in-core probes were rux. to check core power symmetry at 90% power. All criteria were satisfied.
6.
Relief Valves RTI-26 The by-pass valves were calibrated and the main steam relief valve capacities were measured during the heatup to 55% power plateau. All criteria were satisfied.
2 I.
INTRODUCTIE (Continued)
The successful implementation of this testing program insures that the Unit 3 refueling outage has created no conditiona or system characteristics which could adversely affect the safe operation of the plant.
Test documents and data referenced in this report are filed at the plant and are available for inspection.
4 I
II.
REFUELING TEST
SUMMARY
}
Table 3.1 presents the dates for significent events in the Unit 3 refuel test program.
1.
Fuel Loading RTI-3 During the outage the entire core was unloaded. Reloading began on October 29 1978, and was completed on November 9, 1978. Final core verification via video tape recording revealed that the fuel assemblies were in their proper location. All but one neutron source was removed from the core prior to reloading, however, no difficulty was encountered in maintaining the required three counts per second on the SRH's throughout the loading sequence.
2.
Full Core Shutdown Margin RTI-4 The-full core shutdown margin was determined during the initial reactor criticality following the outage. The shutdown margin determination was in close agreement with the predicted value of 3.52% Gk/k calculated by General Electric. The actual shutdown margin was 3.33% Ak/k compared to the Technical Specification minimum required value of 1.18% 4k/k.
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION
SUMMARY
REPORT REFUELING TEST PROGRAM BROWNS FERRY NUCLEAR PLANT UNIT 3 - CYCLE 2 SUBMITTED BY:
APPROVED BY:
)
ALUA
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/ Plant Superintencent
@ief, NuefeEr Lenfration Branch