ML20035F069
| ML20035F069 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/15/1993 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20035F070 | List: |
| References | |
| MSV-01376, MSV-1376, NUDOCS 9304200221 | |
| Download: ML20035F069 (3) | |
Text
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Georgia Power Company
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40 inverness Center Patway Post O"ce Box 1295 B+rm:ngnam. Alaoama 35201 Tecnone 205 877:7122 L
Georgia Power C. K. McCoy vece Presdent Nuclear Vog:ie Proicct
!!e soJhwn elecirc system MSV-01376
- 5131 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.
20555 Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT INSERVICE TESTING PROGRAM REVISIONS In accordance with the requirements of Technical Specification 4.0.5 concerning surveillance requirements, Georgia Power Company (GPC) submits the enclosed revisions to the Inservice Testing (IST) Programs for Vogtle Electric Generating Plant (VEGP), Units 1 and 2.
The IST programs were previously submitted to the NRC as documents ISI-P-008 and ISI-P-016 for VEGP-1 and 2, respectively. The enclosed IST program changes represent Revision 7 for VEGP-1 and Revision 4 for VEGP-2. The IST programs currently in effect for VEGP-1 and 2 were written in accordance with the requirements of the 1983 Edition of the ASME Section XI Code with Addenda through Summer 1983. The enclosed 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 enclosures l
and precedes the affected pages.
Changes resulting from Revision 7 and Revision 4 to the VEGP-1 and 2 IST Programs, respectively, include the following:
o Revision of existing Valve Relief Request RR-14, o Revision of existing Valve Relief Request RR-23,.
Revision of existing Valve Cold Shutdown Justification CS-31, o
o Addition of Valve Relief Request RR-28, and o Revision vf the Valve Test List.
Valve Relief Request RR-14 was revised to change the frequency of I
disassembly and inspection of Containment Spray System check valves 1/2-
-60J5and016. Justification for the extension of the I
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U. S. Nuclear Regulatory Commission MSV-01376 Page Two disassembly frequency was performed in accordance with the guidance contained in NRC Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs", dated April 3, 1989.
Valve Relief Request RR-23, Cold Shutdown Justification CS-31, and the Valve Test List were revised with respect to selected check valves in the Main Steam System, i.e., 1/2-1301-04-006, -008, and -404.
Specifically, the Valve Test List has been revised to change the safety function of check valves 006 and 404, Valve Relief Request RR-23 was revised to disassemble and inspect check valves 006 and 008 on a staggered basis, and Cold Shutdown Justification CS-31 was revised to delete check valve 006 and to make editorial changes.
Chemical and Volume Control System (CVCS) check valves 1/2-1208-U6-124 and Valve Relief Request RR-28 are being added to the VEGP-1 and 2 IST Programs pursuant to a recommendation by Westinghouse.
Their Nuclear Safety Advisory Letter NSAL-92-012 dated December 21, 1992 identified VEGP-1 and 2 and several other Westinghouse plants as having a potential leak path outside of containment during a loss of coolant accident (LOCA) due to overpressurization of the Charging / Safety Injection pump suction line.
Specifically, CVCS check valves 1/2-1208-U6-124 are located downstream of the Volume Control Tank (VCT), the two motor-operated isolation valves, and the seal return line.
If the plant is in the sump recirculation mode after an accident, and the Residual Heat Removal System (RHR) pumps are supplying flow to the charging pumps and if the subject check valves leak, flow will be diverted through the seal water heat exchanger and potentially lift a CVCS relief valve (1/2-PSV-8123) which would then relieve to the VCT.
If the VCT fills, overflow goes to the Liquid Hold-up Tanks outside containment resulting in a leakage of primary coolant outside containment.
Because of operational considerations, the check valves will be tested during maintenance / refueling outages since testing is impractical during normal plant operation, including cold shutdown. As a result, testing can not be performed quarterly in accordance with the requirements of the ASME Section XI Code nor during cold shutdown. Accordingly, relief from the testing frequency requirements of the Code is being requested from the NRC.
The Valve Test List was also revised to change valve types for selected valves as a result of plant modifications.
Specifically, Waste Processing System-Liquid valves 1/2-HV-8220 were changed from solenoid-operated globe valves to solenoid-operated gate valves.
In addition, the Valve Test List was revised to include the CVCS check valves referenced in Valve Relief Request RR-28, i.e., check valves 1/2-1208-U6-124.
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Georgia Power h U. S. Nuclear Regulatory Commission MSV-01376 Page Three Each of the enclosed changes were reviewed against NRC Generic Letter 89-04.
It is our belief that the enclosed changes fall within the provisions of NRC Generic Letter 89-04 for program revisions not requiring prior NRC review and approval. As such, we are submitting these changes to the NRC in order to maintain the accuracy of the VEGP-1 and 2 IST Program documents currently on file with the NRC.
Georgia Power Company is currently in the process of revising site surveillance procedures to comply with the changes included in this submittal.
For testing which can only be performed at cold shutdown or maintenance / refueling (i.e., RR-14, RR-23, RR-28, and CS-31), the testing will be performed during the VEGP-1 maintenance / refueling outage (Out age IR4) currently in progress and during the upcoming VEGP-2 maintenance / refueling outage (Outage 2R3) and any unplanned future shutdown that might occur.
The NRC is requested to grant interim approval for Valve P.elief Request RR-28 pending final NRC review and approval as allowed by 10 CFR 50.55a(g)(6)(i).
Since these changes affect testing scheduled during an outage currently in progress and during an upcoming outage, GPC is requesting this interim approval at the earliest convenience of the NRC.
Should there be any questions in this regard, please contact this office.
Sincerely, C. K. McCoy CKM/JAE/jae
Enclosures:
(1) Revision 7 to VEGP-1 IST Program, ISI-P-008 (2) Revision 4 to VEGP-2 IST Program, ISI-P-016 xc: Georaia Power Company Mr. S. H. Chesnut (w/o enclosures)
Mr. M. Sheibani (w/o enclosures)
Mr. W. B. Shipman (w/ enclosure)
NORMS (w/ enclosures)
- u U. S. Nuclear Reaulatory 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) 700775