ML20207K021
| ML20207K021 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/24/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-1011, NUDOCS 8607290318 | |
| Download: ML20207K021 (3) | |
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Georgia Pbwer Company Pbst Offica Box 282 C,7
'+4 Georgia 30830 Telephone 404 554 9961 404 724 4114 Southem Company Services,Inc.
Pbst Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 Vogtle Proj.ect July 24, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention:
Mr. B. J. Youngblood Log:
GN-1011 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 SER LICENSE CONDITION 12: REACTOR VESSEL LEVEL INSTRUMENTATION SYSTEM (RVLIS) IMPLEMENTATION REPORT
Dear Mr. Denton:
The subject license condition restricts operation of Units 1 & 2 to less than 5% rated thermal power (RTP) until RVLIS is fully operational. There is a potential schedule impact caused by this requirement on VEGP. In researching RVLIS testing, it was determined that several other power plants experienced difficulties in meeting the fully operable status of RVLIS prior to exceeding
'5% RTP. Thus to ensure the NRC's requirements are not violated the following resolution is being proposed.
.RVLIS testing will be performed post fuel load due to the inability to develop the required conditions in the RCS prior to fuel load. The dynamic channel tccting.:111 he cenducted in =+= 5 through 3 as required to obtain the i
necessary data for computing the pump head curves. Once the final information is obtained in Mode 3 the data must be analyzed by Westinghouse and a report l
written. This report must be approved by the NRC and any required equipment or procedural changes must be implemented before the system could be I:
considered operational, i
j The static functions of RVLIS (full range and upper range) will be operable l.
prior to exceeding 5% RTP.
The dynamic functions of RVLIS will be operational prior to completion of the
[
100% Startup Test Plateau because of reasons discussed above.
8607290318 860724 PDR ADOCK 05000424 E
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l Director of Nuclear Reactor Regulation File: X7BC35 f
July 24, 1986 Log:
GN-1011 Page 2 I
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The implementation letter report required for RVLIS will be submitted to the NRC within 90 days of receipt of the Westinghouse analysis report of RVLIS testing. This report will include the following items from Appendix L of the VEGP SSER-1:
A.
Notification that the system installation, functional testing (testing performed during systen checkout, startup test results will be presented in the Startup Reports), and calibration is complete and test results are available for inspection.
B.
Summary of licensee conclusions based on test results.
C.
If required by test results data analysis, identify any proposed changes in plant equipment or procedures and schedules for work completion.
These changes in License Condition 12 will not cause a decrease in plant safety for the following reasons:
A.
Prior to criticality, during the period of plant operation in which the system is being tested, there is no decay heat load to cause core damage.
B.
After criticality there are two possible situations that could occur:
1.
Loss of Forced Flow - the static portions of RVLIS will be calibrated and available for use. Also, thermocouples and other instrumentation as required by Technical Specifications will be operable.
2.
Forced Flow Available - in this case there are alternate methods to verify reactor vessel level such as' loop flow, pressurizer level, incore thermocouples, excore nuclear detectors, wide range HOT, and the subcooling monitor. These indications provide varied methods for verifying that the core is covered during normal and off-normal avanta until RVT,TR in fully onerable.
I The Emergency Operating Procedures (EOP's) were reviewed for potential problems that could be caused by not having full RVLIS operability. It was determined that there is no impact on the E0P's due to the redundant instrumentation available to the operators.
. If your staff requires any additional information, please do not hesitate to j
contact me.
Sincerely, l
.&. E' 1
l J. A. Bailey Project Licensing Manager JAB /sm i
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Director of Nuclear Reactor Regulation File: X7BC35 July 24, 1986 Log:
GN-1011 Page 3 xc:
R. E. Conway R. A. Thomas.
J. E. Joiner, Esquire B. W. Churchill, Esquire M. A. Miller (2)
B. Jones, Esquire G. Bockhold, Jr.
NRC Regional Administrator NRC Resident Inspector D. C. Teper W. C. Ramsey (w/o att.)
L. T. Cucwa Vogtle Project File 0614V 1
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