ML20094K960
| ML20094K960 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/17/1992 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MSV-00821, MSV-821, NUDOCS 9203230340 | |
| Download: ML20094K960 (13) | |
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s March 17,1992 MSV-00821
- 2909 Docket Nos.
50-424 50-425 U. S. Nuclear Regulatory Commission ATTH:
Document Control Desk Washington, D. C.
20555 Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT ASME SECTION XI CATEGORY B-D E G INATIONS Georgia Power Company (GPC) hereby submits the enclosed information regarding a revision to the examination schedule for the inservice inspection (ISI) of Class 1 vessel nozzles (ASME Section XI Code, Examination Category B-D) at Vogtle Electric Generating Plant, Unit 2 (VEGP-2). Affected plant components include the reactor pressure vessel, steam generators, and the pressurizer. Our basis and justification for revising the ISI inspection plans for VEGP-2 are presented in the enclosure to this letter.
The revisions are not applicable to Unit 1 (VEGP-1) at Vogtle since Category B-D examinations for certain vessels have already commenced.
No relief is being requested from either the NRC or the ASME Section XI Code requirements regarding the revision to the VEGP-2 Ten-Year ISI Plan.
This submittal is being made to the NRC solely for informational purposes.
The revision differs from the inspection schedule contained in the docketed VEGP-1 Ten-Year ISI Plan.
A similar Ten-Year ISI Plan, although not docketed, exists for VEGP-2.
In lieu of formally submitting a Ten-Year ISI Plan for VEGP-2, the NRC requested that GPC identify the differences between the plan documents for VEGP-1 and 2.
The differences between the VEGP-1 and 2 Ten-Year ISI Plan documents were identified to the NRC by GPC letter MSV-00318 dated Scptember 13, 1990. With regard to Category B-D, the Ten-Year ISI Plan documents for VEGP-1 and 2 were similar.
Except as noted in this letter, the remaining ASME examination categories remain unchanged.
Similar changes to those discussed in the enclosure have been made by at least one other utility.
Concurrence with the changes in the examination schedule for Category B-D was given by the NRC in a November 6, 1990 letter to the utility in question, GPC acknowledges the comrents in the aforementioned NRC letter that the use of ASME Section XI Code Interpretation XI-1-86-74 cannot be applied generically to all examination I
categories.
That code interpretation is being used by GPC as its basis for rescheduling ASME Section XI Code, Category B-D examinations at VEGP-2.
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O. S. Nuclear Regulatory Commission MSV-00821 Page 2 It is the intention of GPC to implement its revised inspection schedule for ASME Section XI Code, Category 0-0 vessel nozzles during the VEGP-2 maintenance / refueling outage which began on March 9, 1992.
1he revised inspection schedule as discussed in the enclosure offers GPC significant opportunities for savings in contractor cost, critical path time, and internal manpower requirements while still maintaining compilance with the ASME Section XI Codo.
Should there be any questions in this regard, please contact this office at your earliest convenience.
Sincerely, j
0 / 0 11 '
C. K. McCoy CKM/JAE/gb
Enclosure:
Discuss;on on rescheduling of VEGP-2 ASME Section XI Category
^
B-D Examinations t
xc: k ongi_a Power Com.P.ADX Hr. S. H. Chesnut (w/o encl.)
Mr. M. Sheibani (w/o encl.)
Mr. W. B. Shipman (w/ encl.)
NORMS (w/ encl.)
- 9. S. Nuclear Reaulttory Commisil2D Mr. S. D. Ebneter, Regional Administrator (w/ encl.)
Mr. D. S. Hood, l.icensing Project Manager, NRR (w/ encl.)
Mr. B. R. Bonser, Senior Resident inspector, Vogtle (w/ encl.)
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1 ENCLOSURE TO GPC LETTER MSV-00821 BASES AND Q1LSURCWON FOR REYlifD CATEG9HLQ-J ELMULALIDRlCMIMLE V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 NRC DOCKET 50-425 e
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1NTRODVCTION I
Georgia Power Company (GPC) hereby notifies the NRC of a revision to the examination schedule for the inservice inspection (ISI) of Class 1 Examination 4
. Category B-D vessel nozzles for the Vogtle Electric Generating Plant, Unit 2 i
(VEGP-2).
The revision applies to the inspection schedule for the twenty-two (22) Category B-D vessel nozzles during the first ten year inspection interval for VEGP-2. Affected plant components include the reactor pressure vessel (RPV), pressurizer, and the steam generators (primary side). The inspection schedule for VEGP-2 Category B-D vessel nozzles for subsequent inspection intervals will be specified in the Ten-Year ISI Plans for those intervals submitted in accordance with 10CFR$0.55a requirements. The revision is not applicable to Unit I at VEGP since Category B-D examinations for certain i
vessels, e,g., the RPV, have already commenced.
This notification is not a request for relief from NRC or ASME Section XI Code requirements. GPC considers its revised inspection schedule to be in compliance with ASME Section XI Code rules.
However, the revised examination schedule differs from the schedule contained in the Ten-Year ISI Plan for the first inspection interval previously filed with the NRC for VEGP-1.
A similar Ten-Year ISI Plan, although not docketed, exists for VEGP-2.
In lieu of formally submitting a Ten-Year 151 Plan for VEGP-2, the NRC requested that GPC
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identify the differences between the Plan documents for VEGP-1 and 2. The differences between the VEGP-1 and 2 Ten-Year ISI Plan documents were identified to the NRC by GPC letter MSV-00318 dated Sentember 13, 1990. With regard to Category B-D, the Ten-Year ISI Plan documents for VEGP-1 and 2 were similar.
In accordance with our docketed VEGP-1 ISI Plan, examinations of all four (4) RPV outlet nozzles were scheduled to be parformed during the first inspection period.
This is consistent for each unit at VEGP.
For VEGP-2, these RPV nozzle examinations would be performed during the second maintenance / refueling outage, 2R2, in order tn comply with the 151 plan as originally written. GPC has elected to reschedule the ISI examinations of the RPV outlet nozzles for VEGP-2 from the first inspection period to the third inspection period of the first intpection interval.
1 Unless directed otherwise by the NRC, it is the intention of GPC to implement its revised examination schedule for ASME Section XI Code, Category B-D vessel i
nozzles during the VEGP-2 maintenance / refueling outage which began on March 9, 1992. -The revised schedule offers GPC significant opportunities for savings l
in contractor cost, critical path time, radiation exposure, and internal manpower requirements while still maintaining compliance with the ASME Section XI Code.
BACKGROUND The Ten-Year ISI Plan for VEGP-2 for the first ten year inspection interval was prepared in accordance with the 1983 Edition of the 'SME Code,Section XI (Code) with the Summer 1983 Addenda and other project commitments.
VEGP-2 entered commercial operation on May 20, 1989.
The ISI examination requirements for Class 1 vessel nozzles are found in code Table IWB-2500-1, Examination Category B-D (Exhibit I to this enclosure) for
" Full Penetration Welds of Nozzles in Vessels". GPC elected to adopt I
Inspection Program "B" (i.e., four, ten year inspection intervals) for the (1)
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i VEGP-2 151 Program.
Examination Category B-D applies to the twenty-two (22) nozzles associated with the VEGP-2 RPV, pressurizer, and steam generators (prin ary side).
During the preparation of the VEGP-2 151 Plan, GPC interpreted Category B-D to require exarination of at least 25% of the RPV nozzles (i.e., two nozzles) during the first inspectioli seriod (i.e., within three calendar years af ter commercial operation) as vecified by footnote No.
2 to Table IWB-2500-1, Examination Category B-0.
This viterpretation is reflected in the RPV nozzle inspection schedule included in the len-Year ISI Plan.
GPC scheduled all four of the RPV outlet nozzles for examination durini the first inspection period, as allowed by footnote No. 2 N the aforementioned table in order to minimize the 151 costs of these nozzles and to keep radiation exposuie As low As Reasonably Achievable (ALARA).
The other four (4) RPV nozzles (inlets) were scheduled for examination in the third inspection period while the core barrel is removed for the 10 year 151.
The eight (8) steam generator primary head nonles and the six (6) pressurizer nozzles were scheduled for 151 examinations throughout the three inspection periods in accordance with Code lable IWB-2412-1 because these examinations are not deferrable in accordance with footnote No. 3 to Code Table IWB-2500-1, Examination Category B-D. Therefore, the Category B-D inspections were originally scheduled in the VEGP-2 len-Year 151 Plan on an item number basis and not on an examination category basis.
Table 1 to this enclosure reflects the original schedule for Category B-D inspections at VEGP-2.
Discussed below is a description of specific examination requirements and examination techniques:
Reattor PressurLVfitel The Code requires volumetric examination of the " Nozzle-to-Vessel Welds" and " Nozzle Inside Radius Section" on the four inlet and four outlet nozzles.
These examinations are performed from the nozzle inside surfaces using submerged ultrasonic 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.
Inlet nozzles are accessible only when the core barrel is removed, as during the 151 10 year nutage.
Pressurizer The Code requires volumetric examination of the " Nozzle-to-Vessel Welds" and " Nozzle Inside Radius Section" on the six pressurizer
- nozzles, These examinations are performed from the outside surfaces using manual contact ultrasonic techniques. Request for relief RR-15 was submitted to the NRC on the pressurizer surge nozzle inside radius examination (Exam ID No. 21201-V6-002-IR-06) because of interference with the heater well couplings.
These inspections are not a critical path activity.
(2)
4 4
Elgam_Qgnerators The Code requires volumetric cr...ination of the " Nozzle-to-Vessel Welds" and " Nozzle inside Radius Section" on the primary inlet and outlet nozzles of all four steam generators.
By design, VEGP does not have nozzle-to-vessel welds on either unit.
The nozzles are integrally cast as part of the channel head.
Component geometry l
prohibits meaningful ultrasonic examination of the nozzle inside radius section.
Relief request RR-42 was submitted to the NRC in order to perform a visual examination en the internal surface of the inside radius section in lieu of volumetric examination.
When scheduled, these visual examinations are performed in parallel with channel head cleanliness verifications prior to reinstalling the steam generator manway covers.
These inspections are not a critical path
- activity, dt$11FICAT10N FOR REVISED SCHEDULI ASME Section XI Code Interpretation Na, XI-1-86-74 (Exhibit 2 to this enclosure), issued May 6,1988, allows 151 examinations to be scheduled by examination category rather than-by item numbers within each category.
This interpretation was subsequently incorporated into the Code as revisions to IWB-2411 and IWB-2412 in the 1986 Addenda.
If applied to Examination Category B-D, this logic would allow the RPV, 3ressurizer, and steam generator (primary side) nozzles to be grouped togetier for scheduling purposes.
This modified approach to scheduling allows the _first inspection period RPV nozzle examinations to be deferred to the 10 year ISI outage during the third inspection period. To meet the Code percentage requirements per inspection period, the other Examination Cater.ory B-D nozzle examinations (i.e., pressurizer and steam generators) required rescheduling such as-indicated by Table 2 to this enclosure.
The RPV oozzle-to-safe end weld examinations (Examination Category B-f) have been rescheduled to be pu, /ormed coincident with the RPV nozzle inspections during the 10 year outage. This was done for twu reasons; first, Note 2 to code Table IWB-2500-1, Examination Category B-f allows the safe end weld examinations to be performed coincident with the Category B-D nozzie examinations; second, the safe end examinations are normally performed at the same time'as the Category B-D examinations using the automated RPV inspection tool. This rescheduling of the RPV nozzle safe end weld examinations is necessary to achieve the full benefit of critical path and budgetary savings. Table 3 to this enclosure provides the original examination schedule for the affected Category B-f welds. Table 4 provides the revised examination schedule for_the Category B-f welds to accommodate the rescheduling of the Category D-D RPV nozzle examinations.
The advantages of performing the RPV nozzle examinations during the 10 year ISI are as follows:
l (3)
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1.
The total critical path time should be reduced due to the deletion of duplicated tasks such as setup and teardown time of the RPV automated examination tool.
The actual examination time will not be reduced.
2.
A significant reduction in total contractor cost should be realized.
RPV examinations generally take a significant amount of off-site preparation tool calibration, maintenance, training, etc.
To add the RPV outlet nozzles to the 10 year ISI outage requirements should cost significantly less (only examination time) than mot,ilizing a contractor for an additional outage.
3.
A reduction in GPC and Southern Nuclear Operating Company manpower Muld be realized.
The support required to perform an RPV examination involves engineers, non destructive examination personnel, Quality Assurance / Quality Control personnel, planers, schedulers, electricians, crane operators, etc. To combine the examination of the RPV nozzles into a single outage vice two outages as originally scheduled optimizes manpower resources.
lHW:MR1 Georgia I u]r Company has rescheduled the ISI examination of VEGP-2 RPV outlet nozzles for the first inspection period to the third inspection period of the first inspection interval.
This rescheduling of ISI examinations is consistent with the Code, including Section XI Interpretation XI-1-86-74, requirements for distribt. tion of examinations within the inspection interval.
The requirements of this Code interpretation are now incorporated in the Code beginning with the 1986 Addenda.
The revised ISI examination schedule allows GPC to minimize overall ISI examination costs and supports ALARA objectives by performing the required automated examinations of RPV nozzler during or,e maintenance / refueling outage (i.e., the 10 year I. outage) in tha third inspection period.
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Y TABLE IWB-2500-1 (CONT'D)
E EXAMINATION CATEGORIES 5
EXAMINATION CATEGORY B-0, FULL PENETRATION WELDS OF N0ZZLES IN VESSELS -INSPECTION PROGRAM B
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E= tent and Frequency of Enammaten Examinatron Ist 0 8er al of item Parts Re6 as Examination Acceptance Ierspecten successe e Inspection
!aspecten to i
No.
Exammed Fig. No.
M ahad Standard IntervaF Inte% 2nd,3rd,4th' Emf of Interval Reactor Vessel
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B3 90 Nerz4to Vewc! Weids IWB-2500-7*
Volumetric IWB-3512 All norries' AP norrVs' Partist' a>
83 100 Norrie f aside Radws Section TWB 2500-7*
Volumetnc l IWB-3512 All nerries' n!! notries' deferral
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Pressuriier E
B3.110 Norste-to.Vesset W4h IWB 2500-T Volumetnc IWB-3512 All norries*
A4 nctries' Pa taF S
u, B3.120 Nori e Ins
- Radius Sectron IWB-2500-P Vo8umetric IWB 3512 A!! norries' Aft norries*
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Steam Generators (Primary Side)
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- 83. 30 Norrie to-Vessel W* ids f WB-2500-7*
Vo8umetric IWB-3512 A!! norrics' All norries' Partsa?
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83.140 Norrie Inside Rasus Saction IWB-2500-7*
Volume +ric IWB-3512 Ai!nort W Alf norries' d,sg,-al d
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a fleat Exchangers (Primary Side)
- -4 B3.150 Norrie-to-Vessal Welds IWB-2500- 7*
Vo8umetric IW B-3512 Aff norries' All norries*
Part#
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83.160 Norrie insiac Rad 4us Section IWB-25ao-y*
Volumetnc IWB-3512 Att norries' Att norries' def=eest 5
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i NOTES:
(1) Inct:a$es norries veth futi pmetration wids to wasset uff (or head) and interapy cast nori es, but escludes maw and hand 5*s evthar t
needed to or integrally cast in vessel.
f2) At least 25% but not more than 50% (c-arf ed) of the n ~ * ~ shall be esamined by the emi of the first inscettion period, and the remamdw "h
by the erw1 of the inspacteon intwwaf.
Of If esaminations are conduciad frern insida the compen cirla weid is cuarmnad by straight beam ul rasonic rW from the nerrie t
bor* the ramammg esaminahons rerpered te be conrt a the shell may be ser'ormad at or rear the W of each in pettke intMval.
th to) T*ne exammation volomas shall app 8y to the aplicable Ftgure shw in Figs. iWB-2500-7ta) thrcuch td).
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1NTI:RI'll1:iEYl'UUTiA -flfi-74 1
Section XI - Interpretatkins No. 23 kl.1-4473, XI.14474 Interpretation: XI.186 73
Subject:
Section XI, Division 1, IWA.2300!aM1); Nondestructhe (umination Personnel Certification - Final Date (1977 (dation Wuh Addenda Through Wm!er 1979) 2 Date Isived:
January 28,1988 File:
IN87 029 i
Question (1): 1611 a requirement of Section )ci, iWA 2300 that qualification requirements such as visual acuity, color vision, and sufficient work experience be completed before the dates of the written and practical examinations!
Reply (1): No.Section XI, IWA 2300 does not specify a sequence for completing the various qualtfication requirements.
Question (2): Is it a requirement of Section XI, IWA 2300 that the latest dete of the written or practical examinations be used as the certification or recertihcation datet Reply (2): No. The certification or recertification dates are not adrfressed in $cction XI, IWA.
2300. Requirements for certification shall be included in a written procedure prepared in accordance with IWA.2300(at 3
interpretation: XI.186-74
Subject:
Section XI, Division 1, IWB/lWC.2412 and Table IWB/lWC 2$001; Examination Schedule Requirements (1977 [dition With Addenda Through Summer 1978 and Subsequent Addenda Through Winter 1981)
Date issred:
May 6,1988 file:
IN86-003A Question: It is a requirement of Section XI, Division 1, to apply the schedule requirements of IWB 2412 and IWC.2412 to each examination category or to each item number listed in Tables lWB.
25001 and IWa25001f Reply: Schedule requirements are applied by category.
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TAllt.E 1 VEGP-2 EXAMINATION CATEG02Y H-D SCllEDlit.E (typical for both unttu)
COMPONENT EEAMINATION ID 1BT PERIOD.
2ND PERIOD 3RD PERIOD (SEE NOTES 1 & 2)
REACTOR YESSEL RIAMB 21201 16 001 It01 x
21201 v6 001 It02 x'
21201 V6 001*It03 x
21201 V6 001 It04 x
21201 V6 001 It05 x
21201 V6 001 It06 x
21201 v6 001 It07 x
21201 v6 001 IROS X
21201 V6 001 WO25 x
21201 v6 001 WO26 x
21201 v6 001 WO27 x
21201 V6 001 WO28 x
21201 V6 001 WC29 x
21201*V6 001 WO30 x
21201 V6 001 WO31 x
21201 V6 001 Wo32 x
TOTAL 8
0 8
PRE 880RIIER EIAMS 2 1201 v6 002 It01 x
2 1201 V6 002 lR02 x
i 2 1201 vt,002 It03 x
2 1201 v6 002 It04 x
2 1201 V6 002*It05 x
2 1201 n6 002 It06 tit 15)
N/A 2 1201*V6 002 WO10 x
2 1201 V6 002 WO11 x
2 1201 V6 002 WO12 x
2 1201 V6 002 V013 x
2 1201 v6 002 WD14 x
2 1201 V6 002 WO16 x
I TOTAL 4
4 3
STRAM CENERATOR XIAME 2*201*66*D01 it 01 x
21201 86 001*1t 0-2 x
21201 E6 002 It 01 x
21201 66 002 It 02 x
212f1166 003 Ia 01 x
.1201 66 003 It 02 x
21201 86 004 It 01 x
2120166 004 It 02 x
TOTAL 2
2 4
_ _ = _
unw CATEGORY B-D TOTAL 14 6
15 ACCUMLATIVE PERCENTAGE 40%
57%
100%
PERCENTAGE PER PERIOD 40%
17%
43%
NOTES:
1.
"lR" in component examination ID no. refers to inside Radius Section for affectes nozzles.
2.-
"W" in component examination ID no. refers to the nozzle-to-vessel welds associated with the af fected u nsels, e.g., RPV, pressurizer.
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VEGl'-2 EXAMINATION"CATECORY ll-D REVISED ScilEDtil.E 7
COMPONENT ERAMINATION ID 1ST PERIOD 2ND PERIOD r3RD PERIOD (2R1 & 2R2]
(2R3 & 2R4)
.(2R5 & 2R6)
ERACTOR YES8EL IIAMS 21201*V6 001*lt01 x
21201 V6 001*lt02 x
21201*V6 001 It03 x
21201 V6 001 It04 x
21201*V6 001*lt05
' 21201*V6 001 It06 x
x 21201*V6 001 Ie07 x
21201*V6 001 It08 x
21201*W6 001 m25 x
21201*V6 001*WO26 x
21201*V6 001.WO22 x
21201.Y6 001 WO28 x
21201*V6 001.WO29 x
21201*V6 001*Wo30 x
21201*V4 001 WO31 x
21201*V6 001*WO32 x
TOTAL 0
0 16 PRE 85URIBER REAMS 2 1201 v6 002*lt01 x
2*1201 V6 002 8802 x
2 1201*V4 002 It03 x
2 1201 V6 002*It04 x
2 1201*V6 002*lt05 x
2 1201 V6 002*lt06 (tt 15) 2 1201*V6 002 WO10 x
2+1201 V6*S02 WD11 x
2 1201*V6*002*WO12 x
2 1201*V6 002 WO13 x
2 1201 V6 002 WQ14 x
2 1201*V6 002.Wo16 x
TOTAL 5
6 0
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STEAM GENERATOR EZAMS 21201 86 001 18 01 x
21201* M 001*lt 02 x
21201 M 002*It*01 x
21201 H 002*lt 02 x
21201* M 003 It*01 x
21201* M 003 It*L?
x 21201* M 004*lt 01 x
21201 B6 004*Ie 02 x
TOTAL 4
4 0
GRAM CATEGORY E-D TOTAL 9
10 16 ACCUMLRTIVE PERCENTAGE 25%
54%
100%
PERCINTAGE PER PERIOD 25%
28%
46%
NOTE 1: Ei.fer to Notes 1 and 2 on Enclosura par,e 7.
(8)
TAllt E 3 VEGP-2 EXAMINATION CATEGORY ll-It SCllEDill.E (typical for both unitn)
I COMPONENT XEAMINATION ID iST PERIOD 2ND PERIOD 3RD PERIOD
(
(
(
2RQ (SEE NOTE 1)
REACTOR YE8SEL RIAME 21201*W 001*WO33 x
21?01 V6*001*WO34 x
21201 v6 001.WO35 x
21201 Y6 001.WO36 x
21201*V6 001*WO37 x
i 21201 V6 001 WO3B x
21201*v6 001*WO39 x
21201*V6 001 WO40 x
TOTAL 4
0 4
PRES 5UR.IEER REAMR 2 1201 v6 002 WO17 x
2 1201 V6 002 WD18 x
2 1201*V6 002.WO19 x
2 1201 V6 002.WO20.
x 2 1201*V6 002 WO21 x
2 1201 v6 002 WO p x
TOTAL-2 2
2 EXAM CATEGORY B-P TOTAL 6
2 6
ACCUMLATIVE PERCENTAGE 43%
57%
100%
PERCENTAGE PER PERIOD 43%
14%
43%
NOTE 3:
"W" in conoponent exarninat ion ID no. refers to the safe end-to-nozzle weld associated with the affected vennels.
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TABl.E 4 VECP-2 l'.XAMINATION CATEGORY li-l' REVISED SCilEDill E a
COMPONENT EXAMINA' TION ID 18T PERIOD 2ND FERIOD 3RD PERIOD (2R1 & 2R2)
(2R3 & 2R4)
(2R5 & 2R6)
RE&CTOR YESSEL EXAMS 2120i+W+001*WO33 a
21201*W 001*WO34 g
21201*W 001*WO35 g
21201 W 001.WOS6 x
21201*W 001 WCST g
2120l* W+ 001* WO38 g
21201* W 001*WO39 g
21201*W 001*WO40 g
TOTAL 0
0 3
FRESSURIJER EXAMS 21201 W 002 WO17 g
2 1201 N 002.WO18 x
2 1201*W 002*WO19 x
2 1201* W 002.WO20 x
2 1201 V6 002 WO21 x
2 1201* H 002 WC22 x
TOTAL 3
3 o
EXAM CATEGORY E-P TOTAL 3
3 3
ACCUMLATIVE PERCENTAGE 21%
4 31k 100%
PERCENTAGE PER PERIOD 211b 21%
57%
NOTES:
1.
The Category B-F RPV nozzle-to-safe end welds are scheduled for examination coincident with the RPV nozzle examinations conducted from the nozzle bore (Footnote 2 to Ce+egory li-F. Table IWii-2500-1),
2.
Refer to Note 1 on Enclosure page 8.
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