ML20206T576
| ML20206T576 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/02/1986 |
| 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 0513V, 513V, 513V8, GN-978, NUDOCS 8607080181 | |
| Download: ML20206T576 (3) | |
Text
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Georgia Fbuer Comparf Fbst Office Box 282 a
Waynesborg Georgia 30830 Telephone 404 554 9961 404 724-8114 Southem Company Services, Inc.
Fbst Office Box 2625 b
Birmingham, Alabama 35202 Telephone 205 870-6011 VOgtie Project July 2, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention:
Mr. B. J. Youngblood Log:
GN-978 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555 REF: MILLER TO CONWAY DATED 4/24/86 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 CONFIRMATORY ITEM 43: TMI ITEM III.D.l.1 4
Dear Mr. Denton:
In Enclosure 2 to the referenced letter additional information was requested for TMI Item III.D.l.1, Primary Coolant Outside Containment. Attached is the GPC response to your staff's information request.
If your staff requires any additional information, please do not hesitate to contact me.
Sincerely, k-J. A. Bailey Project Licensing Manager JAB /caa Attachment xc:
R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey M. A. Miller (2)
L. T. Cucwa B. Jones, Esquire Vogtle Project File G. Bockhold, Jr.
0513V 0g 0
l i i 86070gogg 60702 PDR ADOCK 05000424 E
RESPONSES TO NRC REQUESTS FOR ADDITIONAL INFORMATION REGARDING
~ CONFIRMATORY ITEM 43: " COMPLIANCE WITH NUREG 0737, ITEM 111.D.1.1" ITEM 1:
Provide a list of systems outside containment which might contain radioactive materials and which -are excluded from the program.
ITEM 2:
A justification for the exclusion of each system on the list in Item 1 above.
RESPONSE
A list of these systems and justification for their exclusion from the program are presented as follows:
1.) Boric Acid Transfer System The Boric Acid Transfer System could be used during an accident; however, it is not in a recirculation path with the RCS and system check valves will protect against any backflow from the RCS.
2.) Boron Recycle System The Doron Recycle System will not be used during an accident and is _ isolated by check valves and normally closed valves.
3.) Filter Backwash System Filters which are involved with systems included in the Leakage Assessment Program will be included in the program.
The back flushing portions are operated 1
manually and will not operate -during an accident or transient.
ITEM 3:
A description of the efforts to reduce potential leakage paths due to design and operator deficiencies.
RESPONSE
Design changes will be implemented when the need is identified prior to fuel load to eliminate and reduce potential leakage release paths due to design deficiencies.
After commercial operation, the Leakage Assessment Program will require the review of Plant Deficiency Reports prior to each refueling outage to identify any potential release paths due to operator and/or design deficiencies that were not identified earlier.
Once these are identified, corrective action will be implemented during a refueling outage.
ITEM 4:
A justification for believing that the proposed test method for gaseous systems is equivalent to helium leak testing.
RESPONSE
Leakage Assessment Testing should be performed to closely simulate the conditions that would be present during an accident.
In an LLRT method for gaseous systems, air is i
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Page 2 used at 50 psi to measure. any leakage.
This is the same pressure that is postulated to be encountered in an accident situation.
This method would. be used along with bubble
' testing of components to identify any leakage. All components-in gaseous systems that.are id!ntified as leaking will be repaired and then retested.
It is for these. reasons that we feel the proposed test method is equivalent to the helium leak test.
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ITEM 5:
A plan-for reporting leak rate testing results to the NRC.
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RESPONSE
A copy of the leakage assessment test results will be forwarded to the NRC as a Special Report.
This report would be sent at the end of the. refueling outage in which the testing takes place.
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