ML20199F804
| ML20199F804 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/13/1999 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20199F802 | List: |
| References | |
| NUDOCS 9901220065 | |
| Download: ML20199F804 (6) | |
Text
. .
. ENCLOSURE TO SOUTHERN NUCLEAR OPERATING COMPANY LETTER LCV-1222-A CORRECTED PAGES' FOR VEGP-2 ISI
SUMMARY
REPORT FOR SPRING 1998 MAINTENANCE / REFUELING OUTAGE
' Enclosure includes pages 2-6,2-7,6-6,6-8, and 6-9 only.
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9901220065 990113 PDR ADOCK 05000425 G- PDR
examinations as currently required by ASME Section XI. For this reason, the RPV '
examinations conducted during the 2R3 outage were performed again during the 2R6 outage in order to ",re-zero" the RPV examinations thus keeping an approximate 10 year ir.terval between examinations.
Details on the RPV examinations performed by WesDyne, procedures utilized, equipment, material and personnel certifications, etc., may be fmd in the WesDyne " Examination Report of the Reactor Vessel 10 Year inspection for Vogtle Electric Generating Plant Unit 2". The WesDyne report is available at the plant site for review upon request.
In addition to components already identified in current requests for relief, seven piping welds l had limited volumetric coverage during their ultrasonic examinations because of physical ,
lin lations due to the geometric configu ation of the welded areas. In order for adequate ASME !
Section XI Code-required examination coverage to be attained, more than 90% of the required volume must be examined as addressed in ASME Code Case N-460. The subject Code Case has !
been approved for use in NRC Regulatory Guide 1.147. It is impractical to achieve the ASME ;
Section XI Code-required coverage due to the geometric configuration of the welded areas.
Relief from the ASME Section XI Code requirements will be requested from the NRC for the affected welds during a future ISI program revision for VEGP-2 as allowed by 10 CFR 50.55a.
The applicable welds are indicated by " Relief Required" in the Class I weld tables. l The Eddy Current (ET) examinations of steam generator tubing, as required by VEGP Technical !
Specification 5.5.9, were performed by Westinghouse and are discussed in the " Class 3 and Augmented Examinations" portion of this document.
Class 1 Pressure Test ASME Section XI, Table IWB-2500-1, Examination Category B-P requires that a system !
hydrostatic test (IWB-5222) be performed at or near the end of each inspection interval. This test is identified as the Class I hydrostatic test (HT-1) and it extends to the Class I pressure boundary extremity (i.e., second isolation valve) and also includes selected adjacent Clas3 2 components which are typically isolated from the Class 1 boundary by check valves. As an alternative to ASME Section XI requirements, Code Case N-498-1 which has been approved by the NRC for use at VEGP was used. Code Case N-498-1 deleted the 10-year elevated pressure requirement for hydrostatic tests but retained the requirement to extend the boundary subject to test pressurization to include each of the Class 1 pressure-retaining components. To assure that all Class 1 pressure-retaining components and selected adjacent Class 2 pressure-retaining components are pressurized requires that valves be aligned to positions other than their normal position requirec. for normal reactor operatian startup and for some isolated boundaries requirec the use of a hydrostatic test pump to achieve pressure. These normally isolated Class 1 and 2 pressure-retaining components were pressurized and visually examined during 2R6. These visual examinations revealed minor leakage and boron residue at mechanical connections. These leaks were either corrected or evaluated and determined acceptable for continued system operation.
ASME Section XI, Subparagraph IWA-5242(a) requires removal ofinsulation from pressure-re'aining bolted connections for VT-2 examination during system pressure testing for systems borated for the purposes of controlling reactivity. Relief was requested (RR-26) from this Code requirement by SNC letter LCV-1016-A dated September 10,1997, to the NRC. By letter dated October 24,1997, the NRC granted approval from this Code requirement. The approved alternative was to remove the insulation from bolted connection:: while they are at either atmospheric or static pressures, perform a VT-2 examination of the bolted connections for evidence ofleakage. This approved alternative was implemented during 2R6.
2-6
Class 2 Examinations Selected ' Class 2 components were examined utilizing MT, PT, and UT, as applicable. Specific components and examination areas are itemized in the applicable portions of this report document. A summary of those components examined are listed below:
- Steam Generator 3 Shell Welds, e Residual Heat Removal Heat Exchanger Train "B" Nozzle Welds, e Centrifugal Charging Pump nozzle Weld, e Piping Welds, and
. Integral Attachment Support Welds.
During the scope of VEGP-2 manual examinations conducted, no Class 2 components were observed to have either reportable ultrasonic, liquid penetrant, or magnetic particle indications.
In addition to components already identified in current requests for relief, two equipment welds and five piping welds had limited volumetric and/or surface examination coverage during their l ultrasonic and/or surface examinations because of physical limitations due to the geometric configuration of the welded areas. It is impractical to achieve the ASME Section XI Code-required examination coverage of more than 90% due to the geometric configuration of the welded areas. Relief from the ASME Section XI Code requirements will be requested from the NRC for the affected welds durin3 a future ISI program revision for VEGP-2 as allowed by 10 j CFR 50.55a. The applicable welds are indicated by " Relief Required" in the Class 2 weld tables. l '
Class 2 Pressure Tests ASME Section XI, Table IWC-2500-1, Examination Category C-H requires system pressure i testing each inspection period. 'ine specific system pressure tests performed are itemized in the l
" System Pressure Tests" pcnion of this report document. The visual examinations performed during these system presrure tests found only minor leakage at mechanical joints such as valve stem packing and at flanged connections. These leaks were either corrected or evaluated and determined acceptable for continued system operation.
Class I and 2 Component Supports Visual examinations were performed on supports for the following Class 1 and 2 components :
. Steam Generator 1, e Reactor Coolant System Piping (1201),
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- Nuclear Service Cooling Water System Piping (1202),
e Safety Injection System Piping (1204),
e Residual Heat Removal System Piping (1205),
Containment Spray System Piping (1205),
. Chemical and Volume Control System Piping (1208),
- Main Steam System Piping (1301),
. Auxiliary Feedwater System Piping (1302),
e Containment Heat Removal System (1501), and
. Containment Heat Removal System (1515)
Visual examinations resulted ia one support having unacceptable conditions. The support is as follows:
2-7
VEGP-2 SIXTH MAINTENANCE REFUEUNG OUTAGE
- CLASS 1 PIPING EXAMINATIONS ,
AUG9ENTED COMPONENT OR EXAM EXAM -
EXAM PROCEDURE CAUBRATION SHEET ASMESECT XI EXAMINATION INELDNOl '
NO (S). RESULTS REMARKS ITEM NOICAT. REQUIREMENT DESCRIPTION METNOD NO. NtEV. St.OCM(S)
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VT-3 VT-V-T35 N/A - EXAMfMED VWHILE B12.50 - 21201PSV80108-IS ~ -
398V2V144 SAT DISASSEMBLED B-M-2 VALVE INTERNAL RESULTS - SAT.
SURFACES 21204-024-15 PT PT-V-805 304A S98V2P089 NRI UT RI1 GEOMETRY.
89.11 -
UT SCANS UMITED I RR-20 B,J 6* PIPE TO VALVE UT UT-V-404 S98V2U164 NRI S98V2U165 RI 21204-024-15 PT PT-V405 304A S98V2P090 NRI UT RIi GEOMETRY.
09.11 -
S98V2U186 NRI UT SCANS LIMtTEDI S.J 6* VALVE TO PIPE UT UT-V 404 RELIEF REQUIRED.
t S98V2U187 RI 21204-024-21 FT PT-V-605 304A S98V2P091 NRI HIA B9.11 -
6* PIPG TO BRANCH UT UT-V-404 898V2U168 NRI B-J CONNECTION 21204-025-21 PT PT-V-805 304A S98V2P086 NRI UT RII GEOMETRY.
99.11 -
UT-V-404 S98V2U152 NRI UT SCANS LIMITEDI C-J 6* PIPE TO VALVE UT Rt RN END.
S98V2U153 21204-025-22 PT PT-V-605 304A S98V2P075 NRI UT SCANS LIMITEDi 99.11 -
S98V2U150 NRI RELIEF REQUfRED.
B.J 0* VALVE TO PIPE UT UT-V-404 S98V2U151 NRI 21204-025-27 PT PT-V405 304A 598V2P070 NRI N/A B9.11 -
6" PIPE TO BRANCH UT UT-V-404 S98V2U149 NRI O.J CONNECTION SS
VEGP-2 SIXTH MAINTENANCE REFUELING OUTAGE CLASS 1 PIPING EXAleNATIONS ,
AUGMENTED COMPONENT OR EXAM EXAM ~ '
EXAM PROCEDURE CAU8 RATION SNEET ASME SECT XI EXAMINATION WELD NOJ NO(S). RESULTS REMARKS
- t ITEM NOfCAT. REQUWtEMENT DESCRIPTION METHOO NO. lREV. BLOCK (S) 212044C PT PT-V405 304A S98V2P128 NRI UT SCANS LIMi1ED1 B9.11 -
UT S90V2U221 NRI REUEF REQUIRED.
BJ 6" VALVE TO hPE UT-V-404 S98V2U222 NRI 21204-044-2 PT PT-V-605 - S98V2P129 RI PT RtiCODE ACCEPT.
B9.32 -
B4 6* PfPE TO 2" BRANCH CONNECTION ,
21204-044-12 PT PT-V-605 304A 595V2P076 NRI N/A B9.11 -
6" ELBOW TO PIPE UT UT V-404 S96V2U154 NRI B.J i
21204-044-13 PT PT-V405 304A S98V2P077 NRI UT SCANS UMITED 1 B9.11 - '
S98V2U155 NRI REUEF REQUIRED B4 6* PIPE TO TEE UT UT-V404
$98V2U156 NRI I
B9.11 - 21204445-1 PT PT-V405 304A S98V2P012 NRI UT RIIGEOMETRY.
UT-V-404 S98V2U120 NRI UT SCANS UMtTED /
B.J 6* VALVE TO PtPE UT REUEF REQUIRED.
S96V2U121 RI
- 21204-045-2 PT PT-V-605 - S96V2P013 NR! N/A B9.32 B.J 6* PIPE TO 2" BRANCH CONNECTION 21204-045-2T PT PT-V-605 304A S98V2P109 NFil N/A 99.11 -
6 ELBOWTO PIPE UT UT-V404 S96V2U178 NRI B.J 8-8
s
^
VEGP-2 SIXTH MAINTENANCE REFUEUNG OUTAGE ,.
CLASS 1 PIPING EXAMINATIONS , ;
~
- AUGMENTED COMPONENT OR EXAM EXAM EXAM PROCEDURE CAUBRATION SHEET .
ASMESECT XI EXAMINATION WELD NOJ NO (S). RESULTS REMARKS ITEM NOCAT. REQUIREMENT DESCRIP110N METHOO NO. #REV. St.OCK (S) ,
B9.11 - 21204-045-28 PT PT-V-605 304A S98V2P110 NRI UT SCANS UMITED i S98V2U179 NR1 REUEF REQUIRED B-J 6* PtPE TO TEE UT UT-V404 S98V2U180 NRI 99.11 - 21204-125-15 PT PT-V405 306A S98V2P088 NRI UT RIIGEOMETRY.
UT UT-V-404 S98V2U158 RI UT SCANS UMfTEDIRR-12.
BJ 10" PIPE TO VALVE S98V2U161 NRI 99.11 - 21204-125-16 PT PT-V405 306A S98V2P086 NRI UT RtiGEOMETRY.
S98V2U159 RI UT SCANS UMtTED IRR-12.
O.J 10" VALVE TO PIPE UT UT-V-404
' S 98 & ;52 NRI 21204-125-17 PT PT-V-605 306A S98V2P087 NRI UT RI1 GEOMETRY.
B9.11 -
S98V20160 RI N 10" PtPE TO ELBOW UT UT-V-404 S98V2U163 RI B9.11 - 21204-125-18 PT PT-V405 306A S98V2P096 NRI UT R1/ GEOMETRY.
10" ELBOW TO BRANCH UT UT-V-404 S98V2U191 RI B.J CONNECTION S98V2U195 RI 21204-126-9 PT PT-V405 306A $98V2P111 NRI N/A B9.11 -
10" PtPE TO ELBOW UT UT-V-404 S98V20188 NRI B.J S98V2U192 NRI 21204-126-11 PT PT-V405 306A S96V2P034 NRI PNA B9.11 -
10" PIPE TO TEE UT UT-V-404 S98V2U189 NRI BJ S98V2U193 NRI l
t 6-9
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