ML20069L815

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Forwards Rev 8 to ISI-P-008 & Rev 5 to ISI-P-016, ISI Program for Vogtle...Units 1 & 2
ML20069L815
Person / Time
Site: Vogtle  
Issue date: 06/15/1994
From: Mccoy C
GEORGIA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20069L818 List:
References
LCV-0389, LCV-389, NUDOCS 9406200303
Download: ML20069L815 (5)


Text

,

.__ ____ y Georgia Power Compan/

j3 40 inverness Center Parbay Post 0%ce Box 1295 i

Benungham, Alabama 35201

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Teler, hone 205 877 7122

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L Georgia Power n

vice P e d Nuclear

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V gue Pro;ect June 15, 1994 i

i LCV-0389 i

Docket Nos. 50-424 50-425 i

I i

U. S. Nuclear Regulatory Commission ATTN.: Document Control Desk l

i Washington, D. C. 20555 l

Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT j

REVISIONSTO INSERVICE TESTING PROGRAMS i

In accordance with the requirements ofTechnical Specification 4.0.5 concerning surveillance requirements, Georgia Power Company submits the enclosed revisions to the -

j Inservice Testing (IST) Programs for Vogtle Electric Generating Plant, Units 1 and 2 (VEGP-1 and 2). The IST programs were previously submitted to the NRC as documents j

ISI-P-008 and ISI-P-016 for VEGP-1 and 2, respectively. The enclosed IST program '

l changes represent Revision 8 for VEGP-1 and Revision 5 for VEGP-2. The IST-4 programs currently in effect for VEGP-1 and 2 were written to the requirements of the 1983 Edition of the American Society ofMechanical Engineers (ASME) Boiler and '

j Pressure Vessel Code,Section XI with Addenda through Summer 1983. The enclosed i

documents supersede portions of the original IST programs previously submitted to the

]

NRC. A summary of changes resulting from each of the revisions is provided in the 1

enclosures and precedes the affected IST program document pages.

i i

j A brief discussion of the revisions to the IST programs for VEGP-1 and 2 follows:

VEGP-1 Changes resulting from Revision 8 of the VEGP-1 IST program include the following:

. 11 o Revision of the pump test circuit for the Centrifugal Charging Pumps, o New pump curves for the Centrifugal Charging Pumps, o Addition of Cold Shutdown Justification CS-41, o Withdrawal of Cold Shutdown Justification CS-35, and o Revision of existing Cold Shutdown Justification CS-36.

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k GeorgiaPower n U. S. Nuclear Regulatory Commission LCV-0389 Page Two Flow-limiting orifices were added to the discharge of Centrifugal Charging Pumps 1-1208-P6-002 and 1-1208-P6-003. The drawings showing the pump test circuits were revised to show the orifices.

The impellers for Centrifugal Charging Pumps 1-1208-P6-002 and 1-1208-P6-003 were replaced. As a result, new pump curves were inserted in the VEGP-1 IST Program document to reflect the characteristics of the new pump impellers.

i The testing frequency of Residual Heat Removal (RIIR) System valve 1-HV-8804B was changed from quarterly to cold shutdown. Cold Shutdown Justification CS-41 was added tojustify the change in test frequency.

Cold Shutdown Justification CS-35 was withdrawn. The affected valves,1-HV-8716A and 1 HV-8716B which are located in the RHR System, are tested quarterly rather than at cold shutdown. As a result, Cold Shutdown Justification CS-35 is no longer required.

Cold Shutdown Justification CS-36 was revised to show the RHR suction check valves 1-1205-U6-001 and 1-1205-U6-002 being partial stroke exercised quarterly and full stroke exercised at cold shutdown.

VEGP-2 Changes resulting from Revision 5 of the VEGP-2 IST Program include the following:

o Revision of the pump test circuit for the Centrifugal Charging Pumps, o Deletion of the Centrifugal Charging Pumps alternate mini-flow relief valves, l

o Revision of the valve test list, and j

o Addition of Cold Shutdown Justification CS-41.

i Test circuit drawings for Centrifugal Charging Pumps 2-1208-P6-002 and 2-1208-P6-003 were revised to show the new configuration of the alternate mini-flow lines.

The Centrifugal Charging Pumps alternate mini-flow relief valves 2-PSV-8510A and 2-PSV-8510B were deleted as a result of a plant design change. Accordingly, valves 2-PSV-8510A and 2-PSV-8510B have been deleted from the VEGP-2 IST Program.

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GeorgiaPower d U. S. Nuclear Regulatonj Commission LCV-0389 Page Three Containment isolation check valves 2-1411-U4-029,031,043, and 044 which are located in the Condensate Chemical Injection System were replaced with manual globe valves.

The new manual globe valves are identified as 2-1411-U4-676,677,678, and 679. The 1

valve list was revised to reflect the new valve types and tag numbers.

l Thc testing frequency of RHR System valve 2-HV-8804B was changed from quarterly to cold shutdown. Cold Shutdown Justification CS-41 was added to justify the change in test frequency.

l The enclosed revisions to the IST Programs for VEGP-1 and 2 were reviewed against i

NRC Generic Letter 89-04. It is our belief that the enclosed revisions fall within the provisions of the subject Generic Letter and, as such, do not require prior NRC review l

and approval. We are submitting these revisions to the NRC in order to maintain the l

accuracy of the VEGP-1 and 2 IST Program documents currently on file with the NRC.

Should there be any questions in this regard, please contact this office.

Sincerely, L

/ 7 C. K. McCoy f CKM/JAE/TMllfjae

Enclosures:

1. Revision 8 to VEGP-1 IST Program document ISI-P-008
2. Revision 5 to VEGP-2 IST Program document ISI-P-016 xc: (see next page) 700775

k Georgia Power n U. S. Nuclear Regulatory Commission LCV-0389 Page Four xc: Georgia Power Company Mr. J. B. Beasley, Jr. (w/o enclosures)

Mr. S. H. Chesnut (w/o enclosures)

Mr. M. Sheibani (w/o enclosures)

NORMS (w/ enclosures)

U. S. Nuclear Regulatory Commission Mr. S. D. Ebneter, Regional Administrator (w/ enclosures)

Mr. D. S. Hood, Licensing Project Manager, NRR (w/ enclosures)

Mr. B. R. Bonser, Senior Resident Inspector, Vogtle (w/ enclosures) l l

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ENCLOSURE 1 (REVISION 8 TO VEGP-1 IST PROGRAM DOCUMENT ISI-P-008)

TO GEORGIA POWER COMPANY LETTER LCV-0389,

" REVISIONS TO INSERVICE TESTING PROGRAMS" VOGTLE ELECTRIC GENERATING PLANT NRC DOCKET NOS. 50-424,50-425 1