ML20150E737
| ML20150E737 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/25/1988 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GN-1442, NUDOCS 8804040065 | |
| Download: ML20150E737 (3) | |
Text
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Geored Fbwa Company Post Offic3 Box 282 Wayn;sboro, Georgia 30830 Telephens 404 554-9961 404 724 8114 southern Company Services, Inc.
Fbst Office Box 2625 Birmingham. Alabama 35202 Teregnone 205 8' "
Vogtle Project March 25,1988 U. S. Nuclear Regulatory Commission t
ATTN:
Document Control Desk File:
X7BC35 Washington, D. C.
20555 Log:
GN-1442 PLANT V0GTLE - UNIT 2 NRC DOCKET NUMBER 50-425 CONSTRUCTION PERMIT NUMBER CPPR-109 SER CONFIRMATORY ITEM 13: INSERVICE TESTING 0F PUMPS AND VALVES Enclosed for review and approval are ten (10) copies of the Inservice Test Program of pumps and valves for Vogtle Electric Generating Plant, Unit 2, ISI-P-016.
This program contains all known and anticipated relief requests.
There are no additional Relief Request on Unit 2 beyond what was requested on Unit 1.
Attachment A lists the differences from Revision 2 of the Unit 1 program which was approved by NRC letter dated September 22, 1987.
If any additional information is required, please do not hesitate to contact me.
Sincerely,
. k-J. A. Bailey Project Licensing Manager JAB /wkl Enclosure xc:
NRC Regional Administrator NkC Resident Inspector P. D. Rice (w/o anclosure)
L. T. Gucwa 1[d
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f R. A. Thomas (w/o enclosure)
B. W. Churchill, Esquire J. E. Joiner, Esquire l(O J. B. Hopkins (2)
G. Bockhold, Jr.
R. Goddard, Esqui-e (w/o enclosure)
R. W. McManus EWCLOSuRE PROCESS &O Vogtle Project File
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ATTACHENT A Differences Between VEGP-1 (Rev. 2) and VEGP-2 (Rev. 0)
Inservice Test Programs General Differences The Unit 2 Program incorporates the requirements for Inservice Test Plans (IkP-6230).
This adds paragraph 2.1 (page 2-1) and new sections 4 through 11 for each set of pumps.
These individual sections include hydraulic test circuits, pump characteristic curves, and pump test parameter tables which specify test instruments.
Other general differences between Unit I and Unit 2 Programs such as reference P&ID's and coordinate locations also exist.
These differences are considered insignificant and are not itemized.
Introduction Differences The last paragraph on page 1-2 was added to discuss relief requests RR-2 and RR-3.
Pump Relief Request Differences Relief Request PR-1 was modified to address the Boric Acid Transfer Pumps.
The Boric Acid Transfer Pumps are cooled by positive flow of pumped fluid. Therefore, temperature measurements are not required by IWP-4310.
Relief Request PR-2 is not necessary for Unit 2 and as such is not included.
Relief Request PR-3 was changed to reflect experience from Unit 1.
The pump suction pressure gages are indicating higher values than
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previously noted.
Relief Request PR-4 is not necessary for Unit 2 and as such is not included.
Valve Test List Differences The description of valves 1204-HV-8801A. 1204-HV-8801B, 1204-U4-026, 1204-U4-027, 1204-04-028, 1204-04-029, and 1204-U6-013 was modified to address a high head safety injection (HHSI) flow path instead of referring to the boron injection tank (BIT).
A boron injection tank is not included in the Unit 2 design.
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The description of valves 1205-HV-8716A and 1205-HV-8716B was modified to indicate quarterly testing instead of testing during cold shutdown.
This change was approved for Unit 1 in NRC letter dated November 5, 1987, from M. A.
Miller to J.
P. O'Reilly.
This also eliminates the need for Cold Shutdown Justification CS-35.
The description of valves 1205-U6-001 and 1205-U6-002 was modified to add partial stroke exercising on a quarterly frequency as a test requirement.
This partial stroke exercising is possible due to RHR recirculation through the RWST by closing valves 1205-HV-8716A or 1205-HV-87168 as discussed above.
This also required a modification to Cold Shutdown Justification CS-36.
The testing performed on valves 1205-U6-009 and 1205-U6-010 was modified in Cold Shutdown Justification CS-37 to also address RHR recirculation through the RWST as a test flow circuit.
The Unit 1 containment spray additive tank vacuum breakers were changed to indicate that they will be tested as safety relief valves instead of quarterly as check valves.
Relief Request RR-26 was consequently withdrawn.
This change was approved for Unit 1 in NRC letter dated September 22, 1987, from M. A. Miller to J.
P. O'Reilly.
The Unit 2 program also indicates that these vacuum breakers will be tested as safety relief valves and RR-26 is not applicable for Unit 2.
Valve 1208-HV-8100 is inadvertently shown as a gate (GA) valve in the Unit 1 program.
The Unit 2 program correctly identifies the valve as a globe (GL) valve.
Valves 1609-HV-12975 and 1609-HV-12976 are inadvertently shown as globe (GL) valves in the Unit 1 program.
The Unit 2 program correctly identifies these valves as gate (GA) valves.
The description of valves 1609-HV-12977 and 1609-HV-12978 in the Unit 1 program inadvertently describes these valves as "Containment Air Radiation Monitor Inlet".
The Unit 2 program correctly describes these valves as "Containment Air Radiation Monitor Outlet".
Valve 2401-04-211 is a one inch diameter gate valve in Unit 1.
The valve in Unit 2 is 1.50 inches in diameter.
Valve Relief Request Differences Relief Request RR-5 was modified to delete references to the boron injection tank.
A boron injection tank is not included in the Unit 2 design.
Relief Request RR-8 was expanded to address reverse flow closure of valves 1204-U6-098 and 1204-U6-099.
No additional relief is requested.