ML20210E164
| ML20210E164 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/21/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM GN-842, NUDOCS 8603270238 | |
| Download: ML20210E164 (3) | |
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T Georgia Power Company -
Routs 2, Box 299A Waynesboro. Georgia 30830 Telephone 404 554-9961 404 724-8114 Southern Company Services, Inc.
Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Proj.ect March 21, 1986 Director of Nuclear Reactor Regulation File:
X7BC35 Attention: Mr. B. J. Youngblood Log:
GN-842 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 PIANT - UNITS 1 AND 2 i
SER CONFIRMATORY ITEMS 43 & 50: TMI ITEM III.D.l.1
Dear Mr. Denton:
Attached for your staff's review is the VEGP response to TMI Item III.D.l.1, i
Integrity of Systems Outside Containment Likely to Contain Radioactive Material for PWRs. The program referenced in the attachment is the program cited in paragraph 6.8.4(a) of the VEGP Technical Specifications.
If your staff requires any additional information, please do not hesitate to contact me.
S cerely, J. A. Bailey Project Licenaing Manager I
JAB /sm Attachment xc:
R. E. Conway G. Bockhold, Jr.
R. A. Thomas NRC Resident Inspector s
J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey l
M. A. Miller (2)
L. T. Gucwa B. Jones, Esquire Vogtle Project File 0053V k
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III.D.l.1 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT LIKELY TO CONTAIN RADIOACTIVE MATERIAL FOR PRESSURIZED-WATER REACTORS AND BOILING-WATER REACTORS NRC Position Applicants shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as-low-as-practical levels. The program shall include the following:
(1) Immediate leak reduction (a) Implement all practical leak reduction measures for all systems that could carry radioactive fluid outside of containment.
(b) Measure actual leakage rates with system in operation and report them to the NRC.
(2) Continuing Leak Reduction -- Establish and implement a program of preventive maintenance to reduce leakage to as-low-as-practical levels.
This program shall include periodic integrated leak tests at intervals not to exceed each refueling cycle.
Response
VEGP will implement a program to reduce leakage from systems outside containment which could carry highly contaminated fluids during a serious accident or transient. This program will be initiated prior to commercial operation and will be performed in accordance with NUREG-0737, III.D.1.1.
The Leakage Assessment program is designed to detect leakage from systems which would be used to bring the plant to a safe shutdown condition following a serious accident or transient. Baseline leakrate data will be acquired during the Power Ascention test phase and will be used when the Leakage Assessment program is initiated to reduce leak rates to as low as reasonably achievable.
The following systems were identified as having potential for the leakage of contaminated fluids outside containment, a) Residual Heat Removal System b) Containment Spray System (excluding NaOH Subsystem)'
c) Safety Injection (excluding Boron Injection & Accumulators) d) Chemical Volume and Control System (Letdown, Boron Recycle and Charging pumps) e) Post-Accident Processing System f) Gaseous Waste Processing System g) Nuclear Sampling System (Pressurizer stean and liquid sample lines, Reactor Coolant sample lines, RRR sample lines, CVCS Demineralizer and Letdown Heat Exchanger sample lines only)
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The Leakage Assessment program will utilize visual inspections of mechanical joints and seals-of liquid systems and local leak rate tests (LLRT) on gaseous systems..These inspections will be conducted during plant refueling outages.
The visual inspections will be conducted with the system pressurized to normal operating pressure using the system fluid as the test medium. The gaseous j
system will employ a LLRT test method, leakage will be identified by bubble testing of mechanical joints and seals. All leakage will be assessed and documented and compared against baseline data.
Corrective action will be taken promptly if the measured leakage is found to i
be unacceptable, but in all cases the criteria will be to reduce leakage to as-low-as-practical levels.
When the Leakage Assessment Program is implemented, it will be used in f
conjunction with'the VEGP's Preventive Maintenance Program to keep leakage rates below the acceptable limits.
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