ML20035F560
| ML20035F560 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/05/1993 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20035F559 | List: |
| References | |
| PROC-930405, NUDOCS 9304220029 | |
| Download: ML20035F560 (23) | |
Text
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GEORGIA POWER COMPANY INSERVICE INSPECTION PLAN (ISI-P-014)
FOR VOGTLE ELECTRIC GENERATING PLANT UNIT 2 PREPARED BY SOUTHERN NUCLEAR OPERATING COMPANY INSPECTION AND TESTING SERVICES GROUP ShC G?C REY.
DATE DESCRIPTION PREP'O REr0 APPV, M-M-
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4 Vogtle Electric Generating Plant - Unit 2 (VEGP-2)
Inservice Inspection (ISI) Program (ISI-P-014)
Revision 5 Summary of Chanaes
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Affected ISI Plan Document Paa'es Chances 6-14 The word "No." was added for consistency and a typographical error was corrected.
t 6-16 The Item Number was added for consistency.
t 5
6-20 Due to surface conditioning and utilization of a more effective weld technique for dissimilar J
metal welds, the examination percentages i
changed.
j 6-94 Typographical error was corrected.
i 6-102 thru 6-105 Added RR-57 concerning scheduling of Category B-l D and B-F examinations.
j 7-7, 7-8, 7-11, 7-12 Revised ISI Line Designation List to reflect RTD i
i 7-13, and 7-14 Bypass Elimination.
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VEGP-2 ISI-P-014 l
l List of Effective Pages Distribution List, Rev. 4 Table of Contents, Rev. 0
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Introduction:==
Page 1-1, Rev. O Page 1-2, Rev. O Page 1-3, Rev. 0 Page 1-4, Rev. O Page 1-5, Rev. 0 Page 1-6, Rev. O Class 1:
Page 2-1, Rev. O Page 2-2, Rev. O Page 2-3, Rev. 0 l
Page 2-4, Rev. O Page 2-5, Rev. O Page 2-6, Rev. O Page 2-7, Rev. O Page 2-8, Rev. O Page 2-9, Rev. O Page 2-10, Rev. 0 Page 2-11, Rev. O Page 2-12, Rev. O Page 2-13, Rev. O Page 2-14, Rev. O Page 2-15, Rev. O Page 2-16, Rev. O Page 2-17, Rev. 0 l
Page 2-18, Rev. O Page 2-19, Rev. O j
Page 2-20, Rev. O Page 2-21, Rev. O Page 2-22, Rev. O f
Page 2-23, Rev. 1 Page 2-24, Rev. O Page 2-25, Rev. 0 Page 2-26, Rev. O Page 2-27, Rev. 0 1
Page 2-28 Rev. O Page 2-29, Rev. 0 Page 2-30, Rev. 0 Page 2-31, Rev. O Page 2-32, Rev. O Page 2-33, Rev. 3 Page 2-34, Rev. 3 Page 2-35, Rev. 0 Class 2:
Page 3-1, Rev. O Page 3-2, Rev. 0 002824 1 of 7 P014 Rev. 5
Class 2' continued:
Page 3-3, Rev. O Page 3-4, Rev. 2 Page 3-5, Rev. O Page 3-6, Rev. 0 Page 3-7, Rev. O Page 3-8, Rev. O Page 3-g, Rev. O Page 3-10, Rev. O Page 3-11, Rev. O Page 3-12, Rev. 0 Page 3-13 Rev. 0 Page 3-14, Rev. O Page 3-15, Rev. O Page 3-16, Rev. 3 Page 3-17 Rev. 3 Page 3-18, Rev. O Class 3:
Page 4-1, Rev. O Page 4-2, Rev. 3 Page 4-3, Rev. O Page 4-4, Rev. 3 Page 4-5, Rev. O Page 4-6, Rev. 3 Page 4-7, Rev. O Component Supports:
Page 5-1, Rev. O Page 5-2, Rev. O Page 5-3, Rev. 3 Page 5-4, Rev. 3 Page 5-5, Rev. O i
i Page 5-6, Rev. O Page 5-7, Rev. O Relief Requests:
Page 6-1, Rev. O Page 6-2, Rev. O Page 6-3, Rev. 4 Page 6-4, Rev. 3 Page 6-5, rev. O Page 6-6, Rev. O Page 6-7, Rev. 0 1
Page 6-8, Rev. 0 Page 6-9, Rev. O Psge 6-10, Rev. 0 Page 6-11, Rev. 0
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Page 6-12, Rev. O Page 6-13, Rev. O Page 6-14, Rev. 5 Page 6-15, Rev. O Page 6-16, Rev. 5 Page 6-17, Rev. 0 002824 2 of 7 P014 Rev. 5
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1 ReiiefRequestscontinued:
Page 6-18 Rev. O Page 6-19, Rev. 1 Page 6-20, Rev. 5 Page 6-21, Rev. 0 Page 6-22, Rev. O Page 6-23, Rev. 1 Page 6-24, Rev. O Page 6-25, Rev. O Page 6-26, Rev. O Page 6-27, Rev. O Page 6-28, Rev. O Page 6-29, Rev. O Page 6-30, Rev. O Page 6-31, Rev. 4 Page 6-32, Rev. 4 Page 6-33, Rev. 4 Page 6-34, Rev. O Page 6-35, Rev. O i
Page 6-36, Rev. O Page 6-37, Rev. O Page 6-38, Rev. O Page 3-39, Rev. O Page 3-40, Rev. O Page 3-41, Rev. O Page 3-42, Rev. 0 i
Page 3-43, Rev. 4 Page 3-44, Rev. 4 i
Page 3-45, Rev. O j
Page 6-46, Rev. I 1
Page 6-47, Rev. O Page 6-48, Rev. O Page 6-49, Rev. O Page 6-50, Rev. O Page 6-51, Rev. O Page 6-52, Rev. O Page 6-53, Rev. O Page 6-54, Rev. O Page 6-55, Rev. 0 l
Page 6-56, Rev. O Page 6-57, Rev. O Page 6-58, Rev. O Page 6-59, Rev. 3 Page 6-59a, Rev. 3 Page 6-60, Rev. 3 Page 6-61, Rev. O Page 6-62, Rev. O Page 6-63, Rev. 0 Page 6-64, Rev. 0 Page 6-65, Rev. O Page 6-66, Rev. 0 Page 6-67, Rev. O Page 6-68, Rev. O l
002824 3 of 7 P014 Rev. 5 f
Relief Request continued:
Page 6-69, Rev. O Page 6-70, Rev. O Page 6-71, Rev. 0 Page 6-72, Rev. 4 l
Page 6-73, Rev. O Page 6-74, Rev. 0 Page 6-75, Rev. O Page 6-76, Rev. O Page 6-77, Rev. 0 i
Page 6-78, Rev. O i
Page 6-79, Rev. 0 l
Page 6-80, Rev. O l
Page 6-81, Rev. 0 Page 6-82, Rev. 0 i
Page 6-83, Rev. O l
Page 6-84, Rev. O Page 6-85, Rev. O Page 6-86, Rev. O Page 6-87, Rev. O Page 6-88, Rev. 3 Page 6-89, Rev. O Page 6-90, Rev. 3 Page 6-91, Rev. 3 Page 6-92, Rev. 3 Page 6-93, Rev. O Page 6-94, Rev. 5 Page 6-95, Rev. 4 Page 6-96, Rev. 4 Page 6-97, Rev. 4 Page 6-98, Rev. O Page 6-99, Rev. 3 Page 6-100, Rev. 1 Page 6-101, Rev. 1 Page 6-102, Rev. 5 Page 6-103, Rev. 5 Page 6-104, Rev. 5 Page 6-105, Rev. 5 Line Designation List:
Page 7-1, Rev. 4 Page 7-2, rev. O Page 7-3, Rev. O Page 7-4, Rev. O Page 7-5, Rev. O Page 7-6, Rev. O Page 7-7, Rev. 5-Page 7-8, Rev. 5 Page 7-9, Rev. O Page 7-10, Rev. O
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Page 7-11, Rev. 5 Page 7-12, Rev. 5 Page 7-13, Rev. 5 Page 7-14, Rev. 5 002824 4 of 7 P014 Rev. 5
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Line Designation List continued:
Page 7-15, Rev. 0 Page 7-16, Rev. O Page 7-17, Rev. O Page 7-18, Rev. O Page 7-19 Rev. 0 Page 7-20, Rev. 0 Page 7-21, Rev. O Page 7-22, Rev. O Page 7-23, Rev. O Page 7-24, Rev. O l
Page 7-25, Rev. O Page 7-26, Rev. O Page 7-27, Rev. O Page 7-28, Rev. O Page 7-29 Rev. O Page 7-30, Rev. O i
Page 7-31, Rev. O Page 7-32, Rev. O Page 7-33, Rev. O Page 7-34, Rev. O Page 7-35, Rev. O Page 7-36, Rev. O Page 7-37, Rev. 0 l
Page 7-38, Rev. O Page 7-39, Rev. O Page 7-40, Rev. O Page 7-41, Rev. O Page 7-42, Rev. O Page 7-43, Rev. O Page 7-44, Rev. O Page 7-45, Rev. O Page 7-46, Rev. O Page 7-47, Rev. O Page 7-48, Rev. O Page 7-49, Rev. O Page 7-50, Rev. O Page 7-51, Rev. O Page 7-52, Rev. O Page 7-53, Rev. O Page 7-54, Rev. O Page 7-55, Rev. O Page 7-56, Rev. O Page 7-57, Rev. 0 Page 7-58, Rev. O Page 7-59, Rev. O Page 7-60, Rev. O Page 7-61, Rev. O Page 7-62, Rev. O Page 7-63, Rev. O Page 7-64, Rev. O Page 7-65, Rev. 0 002824 5 of 7 P014 Rev. 5
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1 Line Designation List continued:
Page 7-66, Rev. 0 Page 7-67, Rev. O Page 7-68, Rev. O Page 7 69 Rev. O Page 7-70, Rev. O Pago 1-71, Rev. 0 P ne 7-72 Rev. O Page 7-73, Rev. O Page 7-74, Rev. O Page 7-75, Rev. O Page 7-76, Rev. 0 Page 7-77, Rev. O Page 7-78, Rev. O Page 7-79, Rev. O Page 7-80, Rev. O Page 7 81, Rev. O Page 7-82, Rev. O Page 7-83, Rev. O Page 7-84, Rev. O Page 7-85, Rev. O Page 7-86, Rev. 0 Page 7-87, Rev. 0 Page 7-88, Rev. O Page 7-89, Rev. 0 Page 7-90, Rev. 0
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Page 7-91, Rev. 0 Page 7-92, Rev. O Page 7-93, Rev. O Page 7-94, Rev. O Page 7-95, Rev. O Page 7-96, Rev. O Page 7-97, Rev. O Page 7-98, Rev. O Page 7-99, Rev. O Page 7-100, Rev. O Page 7-101, Rev. O Page 7-102, Rev. O Page 7-103, Rev. O Page 7-104, Rev. O Page 7-105, Rev. O Page 7-106, Pev. O Page 7-107, Rev. O Page 7-103, Rev. O Page 7-109, Rev. O Pige 7-110, Rev. O Page 7-111, Rev. O Page 7-112, Rev. O Page 7-113, Rev. O Page 7-114 Rev. 0 Page 7-115, Rev. O Page 7-116, Rev. 0 Page 7-117, Rev. 0 002824 6 of 7 P014 Rev. 5
Line Designation List continued:
Page 7-118, Rev. 0 Page 7-119, Rev. O Page 7-120, Rev. O Page 7-121, Rev. O Page 7-122, Rev. 0 Page 7-123, Rev. O Page 7-124, Rev. 0 Page 7-125, Rev. 0 Page 7-126, Rev. 0 Page 7-127, Rev. O Page 7-128, Rev. O Page 7-129 Rev. O Page 7-130, Rev. O Page 7-131, Rev. 0 Page 7-132, Rev. O Page 7-133, Rev. O Page 7-134, Rev. O Page 7-135, Rev. O Page 7-136, Rev. O Page 7-137, Rev. O Page 7-138, Rev. O Page 7-139, Rev. O Page 7-140, Rev. 0 Equipment Designation List:
Page 8-1, Rev. 4 Page 8-2, Rev. O Page 8-3, Rev. O Page 8-4, Rev. O Page 8-5, Rev. O Page 8-6, Rev. O Page 8-7, Rev. 0 Page 8-8, Rev. O Page 8-9, Rev. O Page 8-10, Rev. O Page 8-11, Rev. 0 Page 8 5,2, Rev. O Page f,-13 Rev. O Page 8-14, Rev. O Page 8-15, Rev. O Page 8-16, Rev. O Patie 8-17, Rev. O Page 8-18, Rev. O Page 8-19, Rev. O Page 8-20, Rev. O Page 8-21, Rev. O Page 8-22, Rev. O Page 8-23, Rev. 0 Page 8-24, Rev. O Page 8-25 Rev. O Page 8-26, Rev. 0 002824 i of 7 P014 Rev. 5 miJ--%
P Rh
I VEGP-2 RB-1 Comoonent or Relief Area Pressure-Retaining Bolting, greater than 2-inch diameter, in Class 1. Reactor Pressure Vessel Studs ID Nos. 21201-V6-001-B01 through 21201-V6-001-854 and spare studs B05-1 and B05-2.
Recuirement from which Relief is Reauested Item No. 86.30, Category B-G-1, ASME Code, requires surface and volumetric l
examinations of Reactor Pressure Vessel studs when removed. Paragraph IMA-2232 (c) requires that the ultrasonic examination meet the requirements l
cf Article 5,Section V.
Basis for Relief A more sensitive examination, wherein a shear-wave transducer is lowered into the heater hole in the center of the stud, has been developed. The calibration block contains 3 notches which were Electrical Discharge Machined into the thread area with the following approximate dimensions:
Notch No.
Lenath Width Depth 1
0.942" 0.089" 0.060" 2
0.487" 0.089" 0.126" 3
0.357" 0.089" 0.148" This calibration technique will be used in lieu of the required bottom hole technique.
The Code required surface examination will be performed if the studs are removed.
Alternate Examination The more sensitive shear-wave examination, as described above, will be used.
001163 6-14 P014 Rev. 5
J VEGP-2 I
RR-ll I
E2mponent or Relief Area Visual VT-3 examination of inaccessible component supports for the reactor i
pressure vessel.
Reauirement from which Relief is Reauested 1
l Item No. F2.30, Category F-B, Table IWF-2500-1, of ASME Section XI requires a j
visual VT-3 examination of component supports and IWF-2200 (b) requires preservice examinations be performed following the initiation of hot functional tests. The support examination boundaries are defined in IWF-1300.1. Relief is requested from the visual YT-3 examination of the Reactor Pressure Vessel supports located underneath the nozzles.
j 4
21201-V6-001-RS1 21201-V6-001-RS2 21201-V6-001-RS3 21201-V6-001-RS4 s
Basis for Relief The reactor pressure vessel supports are encased in concrete which renders 1
them inaccessible for examination by ' the visual method. The' reactor vessel nozzles render them inaccessible from the top side. Removal of the examination barriers is impractical. See Attachment I for a sketch of the reactor pressure vessel supports.
l Alternate Examination None 001163 6-16 P014 Rev. 5
m... _ _ _ __.
VEGP-2. Re-12 ATTACHMENT 1 Percentsee Enemined Id etiffcetten No.
Code Catestry Descrfotion Duri m PSI Restriction 21201 V6-002-WO17 s-F 6* Safety worste to safe DX*
T5% Enem from notate side End Weld.
80% Emme from safe-end side 31201-v6-002-WO18 B-F 6" Safety Nortte to Sefe 5%*
5 % Emme from notate side End Weld.
801 Esse from safe-end elde 21201-V6-002-WO19 g-F 6" Safety Norste to safe MP F5% Exam from notate side End Weld.
80E Emme from safe-end olde 21201 V6-002-WO20 s-F 6" Retlef Nortte to safe T5F T5% Enem from notate side End Weld.
801 Emen from safe-end side 21201 V6 002-WD11 s-F 4= speJy notate to sefe 8TX 1001 Emen from not ie eIde End Weld.
75X Enem from safe end side 21201 V6-002-WO22 e-F 14" surge Nortte to Sefe 74%
90E Enem from notate side End Weld.
58% Enem frem safe-end elde
- surface conditioning and utilisetten of more effective technique for dise1 miter motel vetdo durtne the 2n2 outoge roeutted Ip differe* emeelnetlen percenteges then those recorded for the PSI. The Indicated percentosee end restrictione are current.
001163 6-20 P014 Rev. 5
I 4
VEGP-2
)
l RR-50
' Component or Relief Area System pressure test on Class 3 pressure-retaining components during system l
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functional or system inservice test.
I Reauirement From Which Relief is Reauested Item Number D1.10 of Examination Category D-A and Item Number D3.10 of Examination Category D-C, Table IWD-2500-1 of ASME Section XI requires a VT-2 l
visual examination during a system inservice test per IWD-5221.
Item Number l
D2.10, Examination Category D-B, Table IWD-2500-1 of ASME Section XI requires l
a VT-2 visual examination during a system functional test per IWD-5222.
Relief is requested to allow VT-2 visual examination of pressure-retaining components during conditions other than system functional or system inservice testing.
i Basis for Relief Portions of some systems are normally pressurized or can be pressurized to their normal operating pressures without the system being pressurized during j
a system functional test or a system inservice test. A typical example of the above is the portion of a systo from an atmospheric storage tank to the i
suction side of a pump.
Relief is requested to allow VT-2 visual examination I
of pressure-retaining components at any time as long as the portion of the system being examined is subjected to pressures which meet or exceed the requirements of IWD-5221 or IWD-5222.
Alternate Examination A VT-2 visual examination will be performed on pressure-retaining components at pressures which meet or exceed the requirements of IWD-5221 or IWD-5222.
001163 6-94 P014 Rev. 5
t 9
i VEGP-2 g_g i
Component or Relief Area Remote mechanized volumetric and/or surface examination of pressure-retaining Reactor Vessel Outlet Nozzle-to-Shell Welds, Inner Radius, and Reactor Vessel Outlet Nozzle-to-Safe End Welds. See Attachment i
1 for examination identification numbers.
i f
J Reauirement from which Relief is Reauested j
3 Table IWB-2500-1, Examination Category B-D, Item Nos. 83.90 and B3.100, Nozzle-to-Vessel (Shell) Welds and Nozzle Inside (Inner) Radius Section and i
Examination Category B-F, Item No. B5.10, Nozzle-to-Safe End Welds, require volumetric examination of all welds and their inside radius section once' i
each ten-year inspection interval.. Relief is requested from the 5
1 requirement to perform a volumetric examination of a minimum of 25 percent, but not more than 50 percent (credited) of the reactor vessel-to-shell welds, their inside radius sections, and associated nozzle-to-safe end I
welds by the end of the first inspection period and to perform thc'se required examinations during the second inspection period.
E Basis for Relief a
Historically, pressurized water reactors such as VEGP-2 examine the reactor vessel. outlet nozzle-to-shell welds, their inside radius sections, and associated nozzle-to-safe end welds during the first inspection period in l
order to comply with the requirements of the ASME Section XI Code. These examinations ere performed from the inside surfaces using submerged j
ultrasonic examination techniques with an automated reactor vessel inspection tool. These examinations are generally performed while defueled with water in the refueling canal, thus typically being a critical path activity. The similar reactor vessel inlet nozzles are accessible j
only when the core barrel is removed, as.during the Inservice Inspection (ISI) ten-year outage at which time they are examined.
In an effort to consolidate examination of the reactor vessel inlet and outlet nozzles such that they would be examined at one time, e.g., during the 151 ten-year outage, Georgia Power Company (GPC) notified the NRC of its plans to re-schedule the reactor vessel inlet and outlet nozzle examinations.
In its letter MSV-00821 dated March 17, 1992 to the NRC, GPC cited ASME Section XI Code Interpretation XI-1-86-74, whf ch relates to the general application of examination requirement, and NRC's approval of a similar re-scheduling plan for another utility as its basis for the planned i
re-scheduling of the reactor vessel nozzle examinations and those of associated components, i.e., safe end welds. The re-scheduling offered GPC 6-102 014 Rev. 5 3
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VEGP-2 RR-57 (Continued)
Basis for Relief (Continued) significant opportunities for savings in contractor cost, critical path time, radiation exposure, and internal manpower requirements while, in the opinion of GPC, still maintaining compliance with the ASME Section XI Code.
Verbal discussions between GPC, Southern Nuclear Operating Company, and NRC staff personnel ensued after the March 17, 1992 submittal by GPC.
It was indicated to NRC staff personnel that examination of the reactor vessel 1
outlet nozzles and their associated components could not be performed j
during VEGP-2 Maintenance / Refueling Outage 2R2, which was in progress at the time, because of logistical problems and was acknowledged. Subsequent review by the NRC indicated, as documented in its letter to GPC dated July 30, 1992, that the re-scheduling plans were unacceptable and should not be implemented. The examination schedules will be adjusted for the affected components during the next revision of the ISI examination plan document (ISI-P-013) in order to better comply with the scheduling requirements of the ASME Section XI Code. Since the reactor vessel outlet nozzles'and i
their associated components were not performed during VEGP-2 Outage 2R2, GPC committed to the NRC to perform the necessary examinations during the-next regularly scheduled maintenance / refueling outage at VEGP-2. Outage 2R3 is the first maintenance / refueling. outage in the second inspection period.
Alternate Examination
)
The reactor vessel outlet nozzle examinations, as identified in Attachment l
1, will be performed during the next regularly scheduled maintenance / refueling outage (Outage 2R3) at VEGP-2 as previously comitted to the NRC by Georgia Power Company in letter MSV-Oll84 dated November 20, 1992.
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VEGP-2. RH-il ATTACHMENT 1 2
Code Category /
Examination 4
Identification No.
Item No.
Descriotion Method (s) 21201-V6-001-IR01 B-D N1 Outlet Nozzle Remote J
B3.100 Inner Radius Mechanized UT 21201-V6-001-IR04 B-D N4 Outlet Nozzle Remote B3.100 Inner Radius Mechanized 2
UT I
21201-V6-001-IR05 B-D H5 Outlet Nozzle Remote B3.100 Inner Radius Mechanized UT 21201-V6-001-IR08 B-D N8 Outlet Nozzle Remote B3.100 Inner Radius Mechanized UT a
21201-V6-001-WO25 B-D N1 Outlet Nozzle Remote B3.90 to Shell Weld Mechanized UT 21201-V6-001-WO28 B-D N4 Outlet Nozzle Remote B3.90 to Shell Weld Mechanized UT 21201-V6-001-WO29 B-D N5 Outlet Nozzle Remote B3.90 to Shell Weld Mechanized UT 21201-V6-001-WO32 B-D N8 Outlet Nozzle Remote B3.90 to Shell Weld Mechanized UT 21201-V6-001-WO33 B-F N1 Outlet Nozzle Remote B5.10 to Safe End Weld Mechanized UT, PT 21201-V6-001-WO36 B-F N4 Outlet Nozzle Remote B5.10 to Safe End Weld Mechanized UT, PT 6-104 014 Rev. S
j VEGP-2. RR-57 ATTACHMENT 1 (Continued) 4 I
CodeCategory/
Examination Identification No.
Item No.
Description Method (s) d 21201-V6-001-WO37 B-F N5 Outlet Nozzle Remote B5.10 to Safe End Weld Mechanized 4
21201-V6-001-WO40 B-F N8 Outlet Nozzle Remote B5.10 to Safe End Weld Mechanized UT, PT j
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