ML20212L172
| ML20212L172 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/22/1987 |
| From: | Watson R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| HO-870336-(O), NUDOCS 8701290349 | |
| Download: ML20212L172 (3) | |
Text
rn Cp&L Carolina Power & Light Company HARRIS NUCLEAR PROJECT P. O. Box 165 New Hill, NC 27562 JAN 2 21981 File Number: SHF/10-13510C Letter Number: HO-870336 (0)
U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTN: NRC Document Control Desk SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-53 REPORT IN ACCORDANCE WITH 10CFR50.59 Gentlemen:
In accordance with Title 1G to the Code of Federal Regulations, Part 50.59, the enclosed report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a change to the Initial Test Program described in Section 14 of the FSAR as required by license condition 2.C.4.
This report'contains a brief description of procedures which s
change the description given in the FSAR. Each description also contains a brief summary of the safety evaluation which shows that the changes do not involve an unreviewed safety question or require a change to technical specifications.
Very truly yours, 2
R. A. Watson Vice President Harris Nuclear Project RAW:cge Enclosure cc:
Dr. J. N. Grace (NRC - RII)
Mr. C. Maxwell (NRC - SHNPP) 8701290349 870122 PDR ADOCK 05000400 P
PDR d
MEM/HO-8703360/ PACE 1/OS1 di
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CHANGE TO PROCEDURE DESCRIBED IN FSAR TITLE:
9100-S-01, Rev. 2, Advance Change 6, Power Ascension Test Program-Power Escalation APPROVAL DATE: 12/31/86 DESCRIPTION:
This procedure schedules the pr - iormance of_ 9101-S-09, Incore Movable Detector System Checkou. This procedure is performed to demonstrate that the Incore Nuclear Instrumentation System can remotely position the incore neutron detectors for the purpose of core flux mapping and to supply the appropriate digital and analog signals to the plant computer. This procedure was performed after initial criticality. This represents an exception to Regulatory Guide 1.68.
SAFETY
SUMMARY
Performing this procedure after initial criticality does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR. Thus no unreviewed safety question exists. The incore detectors are used to calibrate the excore neutron detectors at a power levei of at least 15% of RATED THERMAL POWER. The system is not required for safe shutdown of the unit or for accident mitigation.
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CHANGE TO PROCEDURE DESCRIBED IN FSAR TITLE:
9100-S-01, Rev. 2, Advance Change 8, Power Ascension Test Program -
Power Escalation APPROVAL DATE: 1/2/87 DESCRIPTION:
This procedure schedules the performance of 9102-S-04, RCS Flow Coastdown Test. This procedure is performed to measure the rate at which the reactor coolant flowrate changes subsequent to reactor coolant pump trips and to measure various delay times associated with the loss of coolant accident. This procedure was performed after initial criticality. This represents an exception to Regulatory Guide 1.68.
SAFETY
SUMMARY
Performing this test after initial criticality results in reactor operation in Mode 2 without verification that RCS flow coastdown satisfies the minimum requirements. There are no accidents in Modes 2 or 3 that require the low flow trips to be operable. Accidents analyzed in Chapter 15 of the FSAR which assume a flow coastdown are limiting at full power. The reactor will only be in Mode 2 (less than 5% power). Therefore, the conclusions of the FSAR will remain valid, and no unreviewed safety question exists.
Thisstest will be performed prior to Mode 1 operation.
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