L-76-151, Letter Regarding Preoperational Testing Per Regulatory Guide 1.68
| ML18098A047 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/01/1976 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| References | |
| L-76-151 | |
| Download: ML18098A047 (4) | |
Text
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P. i BOX 013100, MIAMI, FLORIDA 33101
+tter<Awi FLORIDA POWER & LIGHT COMPANY April 1, 1976 L-76-151 St. Lucie Unit 1 Docket No. 50-335 Preoperational Testing per Re ulator Guide 1.68 Director of Nuclear Reactor Regulatio Attention:
Mr. Roger S.
Boyd, Direct Division of Project dna ement U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
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Dear Mr. Boyd:
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To satisfy the requirements of item B.2 of Enclosure 1 to Facility Operating License DPR-67, Florida Power and Light Company (FPL) hereby submits a report which demonstrates that tests to be con-ducted during power ascension testing meet. the intent of sections D.l.c and D.l.d of Appendix A to Regulatory Guide 1.68.
Regulatory Guide 1.68 Appendix A Section D.l.c calls for a test demonstrating "plant response to load swings, including response to automatic dispatcher control, if applicable (50%, 100%)."
(Automatic dispatcher control is not applicable to St. Lucie Unit 1.)
Section D.l.d calls for a test demonstrating "auto-matic control system checkout steam generator level control, automatic rod control, turbine control (25%)."
We will satisfy the requirements of Sections D.l.c and D.l.d by performing tests in accordance with revised preoperational test procedure no.
1400084, entitled "Automatic Control System Check-
- out, Steam Generator Level Control, CEA Regulating
- System, Auto-matic Turbine Control, and Load Swing Test."
In addition, pre-operational test procedure no.
0110090, entitled "10% Load Reduction Turbine Runback Test," will provide further data demonstrating plant response during a load swing.
Our NSSS vendor has recommended
- that, due to fuel preconditioning considerations, the performance of these tests take place after the 100% test plateau has been reached..
Therefore, we do not plan to conduct the tests during the initial ascent to: 100% rated power.
It should b'e noted that, during the initial power ascension, data will be taken every four (4) hours in accordance with preoperational procedure no.
- 0010180, which is the Power Ascension Sequencing Document.
This; data will demonstrate plant response during tran-sients and normal maneuvering and reveal problems which may be occuring.
In addition, plant control systems are monitored during test trips scheduled for the initial ascent to 100% power.
HELPING BUILD FLORIDA
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Director of Nuclear Reactor Regulation Attention:
Mr. Roger S.
Boyd Page Two April 1, 1976 Preoperational test no.
1400084 is to be performed at 25%,
50%,
and 90% rated power.
The test demonstrates the automatic capabilities of the CEA regulating
- system, the steam generator feedwater control system, and the.turbine control system and documents that all three systems give adequate and stable responses during steady state and expected transient conditions.
Strip chart recorders are utilized on these and other systems so that the plant response to load swings of up to 10% can be analyzed.
Preoperational test no.
0110090 gives us an additional 10% load swing at 80% rated power where brush recorders are used to analyze plant response.
We consider these tests and the consequent data to satisfy Regulatory Guide 1.68 Appendix'A sections D.l.c and D.l.d.
Copies of preoperational test procedures
- 1400084, 0110090, and 0010180 are attached as Attachments 1, 2, and 3, respectively.
Very truly yours, Robert E. Uhrig Vice President REU:MAS:sb cc:
Mr. Norman C. Moseley (w/o attachments)
Jack R.
Newman, Esquire (w/o attachments)
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