ML17213B119
| ML17213B119 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/01/1983 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8303140609 | |
| Download: ML17213B119 (5) | |
Text
MAR 1 1983 Docket No. 50-335 Dr. Robert E. Uhrig Vice President Advanced Systems 8 Technology Florida Power 5 Light Company P. 0. Box 529100 I'liami, Florida 33152 A. DeAgazio L.
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Dear Or. Uhrig:
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SUBJECT:
ADDITIONAI. QUESTIONS REGARDING OVERPRESSURE NITIGATION SYSTEM AND CYCLE 6 RELOAD, ST.
LUCIE.
The staff, in conducting its review of the overpressure mitigation system and the application for cycle 6 reload for St. Lucie 1, has identified several areas where additional information is required in-order to complete the review.
Specifically, the Reactor Systems Branch requires responses to the two questions contained in Enclosure 1.
Adequate responses to these questions should enable the staff to complete its review of this multiplant action item. It is requested that you provide your response within 30 days of receipt of this letter.
In its review of your application for the cycle 6 reload, the Reactor Physics Section of the Core Performance Branch has identified two areas (Enclosure
- 2) where additional information is needed.
Since your outage for cycle 6 has already been started, an early response to'these two requests is needed in order to complete this aspect of the staff review in a timely fashion.
Your staff has been advised of the contents of the enclosures.
If you have any questions, contact D. Sells (301) 492-9735, the Project Manager.
Sincerely, Original signed by:
- 8303l40609 830301 I
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Enclosures:
As stated Robert A. Clark, Chief Operating Reactors Branch III3 Division of Licensing OFFICEI SURNAME/
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NRC FORM 318 (10.80) NRCM 0240 I
OFFiCIAL, RECORD COPY US0PO: 1981-33&960
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Florida Power 5 Light Company CC:
Harold F. Reis, Esquire Lowenstein,
- Newman, Reis 8 Alexrad 1025 Connecticut Avenue, N.W.
Washington, D. C.
20036 Norman A. Coll, Esquire McCarthy, Steel, Hector 8 Davis 14th Floor, First National<Bank Building Miami Florida 33131 Mr. Jack Schreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector c/o U.S.N.R.C.
7900 S. AIA Jensen Beach, Florida 33457 Administrator
-Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road'allahassee, Florida 32301 Mr. Weldon B. Lewis County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 U.S. Environmental Protection Agency Region IV Office ATTN:
Regional Radiation Representative 345 Courtland'treet, N.E.
Atlanta, Georgia 30308 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
7910 Hoodmont Avenue
- Bethesda, Maryland 20814 Regional Administrator Nuclear Regulatory Commission, Region II Office of Executive Director for Operations 101 Marietta Street; Suite 3100 Atlanta, Georgia 30303 State Planning and Develpment'learinghouse Office. of Planning and Budgeting Executive Office of the Governor The. Capitol Building Tallahassee, Florida 32301
Enclosure 1
RE UEST FOR ADDITIONAL INFORMATION ON THE LOl4 TEMPERATURE OVERPRESSURE PROTECTION SYSTEY FOR ST.
LUCIE, UNIT 1 REACTOR SYSTEMS BRANCH 1.
In the event of a failure of a D. C.
bus while a charging pump is operating, the reactor coolant system pressure could exceed its limit in less than 10 minutes after an alarm if the power operated relief valve is in Cstuck closed position.
Show by revised procedures modified alarm set points, or making other provisions that the operator will have the required 10 minutes to terminate this event before ex--
ceeding the pressure limit.
2.
The set point of the overpressure protection system at St. Lucie-1 can automatically vary according to information from wide range temperature detectors: in reactor coolant. loops.
- However, during transients these loop temperatures can be considerably different than the temperature of the reactor vessel.
Please show by analysis that this variable set point system will adequately protect the reactor vessel from a brittle fracture for all induced energy transients.
Enclosure 2
RE UEST FOR ADDITIONAL INFORMATION ON CYCLE 6 RELOAD REACTOR PHYSICS SECTION/CORE PERFORMANCE BRANCH II 1..
Provide the report Exxon Nuclear Analysis of Power Distribution Measurement'ncertainty for St.. Lucie-Unit 1"'XN-NF-83-01).
2.
Provide a descri ption of'he INPAX II incore monitoring code ifit is. to be used for Cycle 6.