ML20204B982
| ML20204B982 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/09/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM SL-2109, NUDOCS 8703250189 | |
| Download: ML20204B982 (6) | |
Text
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s Georgia Powir Company 333 Piedmont Avenue Atlanta Georgia 30308 Telephone 404 5264526 Maihng Address:
fbst Office Box 4545 Attanta, Georgia 30302 Georgia Power W sm/mern elerM sgrem Manager Nuclear Safety and Licensing SL-2109 0141m March 9, 1987-U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 NRC DOCKET NUMBER 50-424 NRC OPERATING LICENSE NPF-61 V0GTLE ELECTRIC GENERATING PLANT UNIT 1 RESULTS OF EXAMINATION FOR POTENTIAL LEAKAGE OUTSIDE CONTAIhMEN Gentlemen:
Georgia Power Company hereby submits a report regarding the results of an examination for potential leakage outside containment pursuant to item III.D.1.1 of NUREG 0737 and confirmatory item 43 of the Plant Vogtle
" Safety Evaluation Report".
Should you have questions regarding tnis submittal, please contact this office.
Sincerely, h-L. T. Gucwa WEB /1m Enclosure ok kDj32p g 05000424 870309 E
GeorgiaPower d l
U. S. Nuclear Regulatory Commission March 9,1987 Page Two c: Georgia Power Company Mr. R. E. ConwAy Mr. J. P._ O'Reilly Mr. G. Bockhold, Jr.
Mr. J. F. D' Amico GO-NORMS Southern Company Services Mr. J. A. Bailey Shaw, Pittman, Potts & Trowbridge Mr.. B. W. Churchill, Attorney-at-Law Troutman, Sanders, Lockerman & Ashmore Mr. J. E. Joiner, Attorney-at-Law U. S. Nuclear Regulatory Commission Dr. J. N. Grace, Regional Administrator Mr. H. H. Livermore, Senior Resident Inspector-Construction, Vogtle Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle Georgians Against Nuclear Energy Mr. D. Feig Ms. C. Stangler 0141m 700775 w
In accordance with requirements set forth-in Facility
)
Operating License NPF-61 and Technical Specifications, Vogtle Electric Generating Plant, Unit No.
1, the following data is presented to document leakage from primary coolant sources outside containment.
This requirement is delineated in paragraph 6.7.4.a of the Technical Specifications as modified by paragraph 2.C.8.a of the license.
For those systems listed below, leakage was quantitatively measured for each component identified as leaking, in accordance with VEGP. procedures 55010-1 through 55016-1.
For the liquid
- systems, the leakage survey was performed at or as near as practical to operating temperatures and pressures.
All leakage paths were identified visually.
Gaseous system leakage was measured using a leak rate monitor and a soap bubble solution used to identify leakage paths.
All identifiable gaseous leaks were eliminated.
The following systems were tested, with total system leakage noted:
A.
Resicaal Heat Removal System - 0.00202 gpm.
B.
Containment Spray System (excluding Na OH Subsystem) 0.000326 gpm.
C.
Safety Injection System (excluding Boron Injection and Accumulators) - 0 gpm.
D.
Chemical and Volume control System (Letdown, Boron Recycle and Charging Pumps) 0.00557 - gpm. (See below)
E.
Post Accident Sampling System -
Liquid Leakage - 0.001 gpa Gaseous Leakage - 22 SCCM (no leakage identified external to the system.)
F.
Gaseous Waste Processing System -
Liquid Leakage - 0.001 gpm Gaseous Leakage - 0 SCCM (external to the system.)
G.
Nuclear Sampling System (Pressurizer Steam and Liquid Sample
- lines, Reactor Coolant Sample lines, RHR Sample
- lines, CVCS Demineralizer and Letdown Heat Exchanger Sample lines only.)
Liquid Leakage - 0.001 gpm Gaseous Leakage (steam) - 0 gpm During the leakage assessment for the Post Accident Sampling
- System, it was noted that air operated valve 1-HV-3258 had an undersized actuator which prevented the valve from closing.
This valve is a drain line isolation valve on the Reactor Coolant Sample line.
This valve has been isolated using an upstream manual isolation valve and the system tested with this configuration.
1 Following resolution of this discrepancy, packing and seat leakage from this valve will be minimized and the leakage, if any, added to the total for the Post Accident Sampling System.
Because the Positive Displacement pump could not be placed into service, leakage for this pump and a minimum of associated components has not been determined.
The value shown for CVCS leakage is the system total excluding those items.
When the pump becomes available, the leakage assessment will be completed and a supplemental report issued to document the completion of this program.
This report satisfies reporting requirements delineated in OL-NPF-61 and the VEGP Unit 1 Technical Specifications.
The above leakage is considered acceptable although further efforts will be taken to reduce all known leakage to a level as low as practical.
5 %P:
In accordance with requirements set forth in Facility operating License NPF-61 and Technical 8pecifications, Vogtle Electric Generating Plant, Unit No.
1, the following data la presented to document leakage from primary coolant sources outside i
containment.
This requirement is delineated in paragraph 6.7.4.a of the Technical Specifications as modified by paragraph 2.C 8.a of the license.
For those systems listed below, leekage was quantitatively measured for each component identified as leaking, in accordance with VIGP procedures 55010-1 through 55016-1.
For the liquid
- systems, the leakage survey was performed at or as near as practical to operating temperatures and pressures.
All leakage paths were identified visually.
Gaseous system leakage was measured using a leak rate monitor and a soap bubble solution used to identify leakage paths.
All identifiable gaseous leaks were eliminated.
The following systems were tested, with total system leakage noted:
A.
Residual Heat Removal System - 0.00202 gpa.
B.
Containment Spray System (excluding Na OH Subsystem) 0.000326 gym.
C.
Safety Injection System (excluding Boron Injection and Accumulators) - O gps.
D.
Chemical and Volume control System (Letdown, Baron Recycle and Charging Pumps) 0.00557 - gpa. (See below)
E.
Post Accident Samplitig System -
Liquid Leakage - 0.001 gpu Gas eous Leakage - 22 SCCM (no leakage identified external to the system.)
F.
Gaseous Waste Processing System -
Liquid Leakage - 0.001 spa Gaseous Leakage - 0 SCCM (external to the system.)
G.
Nuclear Sampling System (Pressurizer Steam and Liquid Sample
- lines, Reactor Coolant Sample lines, RHR Sample
- lines, CVCS Domineralizer and Letdown Heat Exchanger Sample lines only.)
Liquid Leakage - 0.001 gpm Gaseous Leakage (steam) - O gpm During the leakage assessment for the Post Accident Sampling
- System, it was noted that air operated valve 1-HV-3258 had an undersized actuator which prevented the valve from closing.
This valve is a drain line isolation valve on the Reactor Coolant Sample line.
This valve has been isolated using an upstream manual isolation valve and the system tested with this configuration.
.. ~
>'c:
' ~
Following resolution of this discrepancy, packing and seat leakage from this valve will be minimized and the leakage, if any, added to the total for the Post Accident Sampling System.
Because the Positive Displacement pump could not be placed into service, leakage for this pump and a minimum of associated components has not been determined.
The value shown for CVCS leakage is the system total excluding those itema.
When the pump becomes available, the leakage assessment will be completed.
This report satisfies reporting requirements delineated in OL-NPF-61 and the VEGP Unit 1 Technical Specifications.
The above leakage is considered acceptable although further efforts will be taken to reduce all known leakage to a level as low as practical.
Following completion of leakage assessment testing on the Positive Displacement Pump and valve 1-HV-3258 of the Post Accident Sampling System, a supplemental report will be issued by April 15, 1987.
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