ML20034C106

Rev 4 to Inservice Insp Program First 10-Yr Interval

ML20034C106
Person / Time
Site:	Vogtle
Issue date:	04/26/1990
From:	GEORGIA POWER CO.
To:
Shared Package
ML20034C102	List: ML20034C101 ML20034C106
References
ISI-P-006, ISI-P-6, NUDOCS 9005020066
Download: ML20034C106 (20)

Text

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I Vogtle Electric Generating Plant - Unit 1 (VEGP-1) e Inservice Inspection (ISI) Program First 10-Year Interval (ISI-P-006)

Revision 4 Summary of Chanoes Affected ISI Program Document Paoes Chance i

2-23, 3-12, 4-2, Any reference to Relief Requests 4-3, and 4-4 RR 45, 47, 48, and 54, which were f

withdrawn by Georgia Power Company-letter MSV-00169 dated March 27, i

1990 to the NRC, have been deleted.

l 6-3, 6-4, 6-85 Adds notation as appropriate that 6 87, 6 BS, 6-89, Relief Requests RR 45, 47, 48, and and 6 96 54 were withdrawn, t

6-18 Reference to Relief Request RR-13 is deleted from the discussion

" Requirement from which relief is requested" in Relief Request RR-12.

Relief Request RR-13 was previously withdrawn in Revision 1 of the ISI program document, ISI-P-006. A statement has been added in the aforementioned discussion section indicating the specific reason why relief is being requested.

6 4, 6-97, and Relief. Request RR-55 and RR-56 are 6-98 being added to the ISI program document although the subject relief requests are intentionally being left blank. This is being done for administrative purposes in order that the relief request numbering sequence-and relief request content will be similar for the two Vogtle units; e.g.,

Relief Request RR ll pertains to visual examination of reactor vessel sup> orts for both Vogtle units in tieir respective ISI program documents.

9005020066 900426 PDR ADOCK 05000424 Q

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Revision 4 Summary of Chances (Cont'd) l 6 58, 6-18a, Relief Request RR 32 has been and 6-59 revised to include the surface examination of the reinforcing plate-to-vessel welds in the Residual Heat Removal System heat exchangers and to elaborate upon the relief requested.

In addition, the figure accompanying the relief request has been revised to better depict the configuration at VEGP 1.

The revised relief request is similar in content to RR-32 for VEGP-2.

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VogtIa Etectric Genersting Plent Unit No.1 Inservice Inspection Table tus-2500-1 Ensurinetton Categories 886 Dev. 4 S-P, COPTINUED Extent and Frequency of Emaninetton Test Exontination 1st 2nd, 3rd, 4th Retlef item No.

Ports Ensurined Reaut recents Method' Intervet intervets Request Comments Piping e15.50 Pressure Retelning System teek-WT-2 Each refuet-Each refuet-5 lI 5

ing autoge Soundery age test 5 ap outage (tus-5221) 6 one test 815.51 Pressure Retoining systeer VT-2 one test 2

6 somdery hydro test per inter-4 (199-5222) vet 6 Pues 315.60 Pressure Retelning System tesk-VT-2 Each refuet-Each refuel-Boundary eye test ing outoge5 ing outage 5 l7 (tus-5221) 6 One test 815.61 Pressure Retaining system v7-2 One test f

soundery hydro test per inter-2 (IWB-5222) vot' 4

vetves 315.79 Pressure Retelning System teek-VT-2 Each refuet-Each refuel-Somdery age test Ing outage 5 ing outage 5 l7 (tus-5221) j 6

one test I

315.71 Pressure Retelning System VT-2 One test 2

5 so m dery trydro test per inter-5 (tus-5222) vet 6 NOTES:

(1) The pressure retelning boundary dring the system teskoge test shett emh.,~..

to the reactor cootent systeur bomdery, with ett volves in 19 e nonnet positlen, dich le reepstred for nornet reactor operation stortup. The VT-2 eneminotion shett, however, entend to and include the second closed vetse et the beteidery autremity.

(2) The pressure retelnlap bomdery dring the systeer hydrostetic test shett include ett Ctess 1 %-.;s within the systemt bewatery.

(3) ' system preneure teste of the reactor cootent systear shett be contheted in w h with fun-5000. System pressure tests for repetred, reptoced, or ettered components shott be governed by IUR-5214(c).

(4).Visuet ensni wtlen of IUR-5240.

(5) The systeur teekege test (tus-5221) shett be conducted prior to plant stortigt fottowing each reactor refweting outove.

(6) The system hydrostetic test (tus-5222) shett be corubeted et or veer the end of each inspection intervet.

(7). A system hydrostatic test (tus-5222) and the accompanying VT-2 emenrinetton ore ecceptable in tieu of the system testeve test (tus-5221) and VT-2 enemination.

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Vogtse Electric Cenerating Plant Unit too. I anservice inspection 006 Rev. 4 Table IWC-2500-1 Examination Categories C-H, ALL PRESSURE RETAINI8eG COMPORENTS Extent and s

pggg,7 Test' Examination IJem. feo Parts Examined' Regtei red Nit'od Eacts Period

• tsch Interval

• Requ_est Cose_en_ts 2

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Ov ve;.e; ts test' retainig '

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C7.20 Presstere Re-IWC-5222 VT-2 Presstere taining Coe-test retainig

• ponents botenda ry UP ms 3

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ponents botenda ry CT.40 Pressiere Re-SWC-5222 VT-2 Pressiere RR-44 tairsing Com-test retainino8 '

ponents botendary DS C7.50 Presstere Re-IWC-5??1 VT-2 Prsassesee RR-%

taining Com-test' retainig '

ponents bowwf a ry C7.60 Pressiere Re-IWC-5222 VT-2 Pressiere taining Com-test retaini g '

ponents botendary Velves CF.70 Prweeure Re-IWC-5221 VT-2 Pressiere RR.%

telning Coe-test' retainig '

ponents bovenda ry C7.80 Pressere Re-IWC-5222 VT-2 Presstere RR-44 teining Com-test retainig #

botendary ponents 03301 3-12

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Vogtte Electric Generating Plant Unit too. 1 Inservice inspection 006 mev. 4 Table IWD-2500-1 Exeminotion Categories D-8, SYSTEMS III SUPPORT OF EPOERCE30CY CORE C00Lf teC, C00 ETAT 91MEffT HEAT REMOVAL, ATMOSPHERE CLEAMUF, A800 REACTOR RESIDUAL HE AT Rt990 VAL Extent and Frequency or txamination Test And twsmination Examination Refier new see.

Parts Examined Requirements Me tted Each Period Esch Intervet Reques3 Cosaments D2.10 Fressure Re-tWA-5000/

VT-2 Pressure RR-50,51 I

l trainig Com-IWD-5222' retaining botenda ry ponents g

IWA-5000/

Pressesre IWD-5223' VT-2 retaining

• boerndary D2.20 Integret figure VT-3 Integrat Attachment-IWD-2500-1 attachment Component Sup-ports and Re-straints:

D2.30 Integrai Figure VT-3 totegrai Attachment-IWD-2500-1 stischeent 99echenicsI and Hydrawl ic 8

Snubbers D2.40 Integrai Fegure VT-3 Iniegra1 Attscheent-IWD-2500-1 attachment Spring T y Supports D2.50 Integral Figure VT-3 Integral Attachment-IWO-2500-1 attachment Constant Load Type 8

Stepperts D2.60 Inte9rst Figure VT-3 Integ ra l Attechnent-IWD-2500-1 sttscheent Shock Ah-8 sorters fe0TES:

(1) The system botendary extends top to and including the first normet ty closed valve or valve espmble of setematic closure as required to perform the safety-relsted system function.

(2) The system hydrostatic test shstI be conducted at or near the end or each inspection interval or during the same -

Inspection period ol' each inspection interval for Inspection Program B.

(3)* In the case or multiple components within a system ol' similar design, function, and service, the integral attscheent or only one or the multiple cm.,w ts shall be examined.

ibe integral attscheents selected for examination sha f t correspond to those component stepports selected by IWF-2510(b).

There are no eremptions or exclusions from these requirements ewcept as specified in IWA-52t4(c).

(4)

(5) A system hydrostatic test (IWO-5223) and secompanying VT-2 examination are acceptable in Iicte or the system pressure test (IWD-5222) and VT-2 examination.

03308 as-3

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Vogtte Electric Generatirog Plant Unit 800 T Inservice Inspection 006 Rev. 4 Table IWD-2500-T Exceiftetton Categories D-C, SYSTEMS let SUPPORT Of RESIDUAL HEAT REMOYAL FROM SPEtti FUEt_ STORAGE POOt_

Extent and rreqtsency.or Examination Test And Ewamination Examinstion ReIler f_te_m 900, Parts EFamined Requirements

_ Method Each Period E_aCh Intervat RegtseM Comments D3.10 Presstere Retraining twA-500n/

VT-2 Pressiere RR-50.53 Components' IWD-5221' retaining bottnda ry IWA-5000/

Pressiere RR-53 l

IWD-5223' VT-2 retainig

• boomda ry D3.20 Integrat r igtsre VT-3 Integrat Attachment IWD-2500-1 attachment Component Stepports and 7

s Restraints D3.30 tniegrat rigure VT-3 IntegraI Attachment-IWD-2500-1 attachment Mechanical and Hyd ratet ics Sntebbers D3. 880 Integral r igstre VT-3 Integ ra l Attachment-IWD-2500-1 attachment Spring Tp Seerports D3.50 IntegraI t igtere VT-3 Integra8 Attachment-tWD-2500-1 attachment Constant toad Type 8

Sesppo rt s D3.60 Integral t igtsre VT-3 Integ ra i Attachment-IWD-2500-1 attachment Shock s

Abserk rs te0TES:

(1) itse system boundary extends top to and incitedirig the first normal ty closed valve or valve capable of' statomatic clostare as regist red to perform the safety-related system rtenction.

(2) The system hydrostatic test shatI be cenducted at or near the end or each inspection interva t or dtering the same inspection period or each inspection interva t for Inspection Program 8.

(3T In the case or multiple eneronents within a system or simitar design, remetion, and service, the integ ra l attachment or only one or the multiple enoponents shaft be examined. The integral attachments selected for examination sha f t cncrespond to those %.,..,..t suppnets selected by twf-2510tb).

( es) There are no eweeptions or ewelusions rrom these requirements except as specirled in tWA-52 se(c).

tie. or the system pressure (5) A system hydrostatic test ( tWO-5223) and accompanying VT-2 examination are acceptable in test (IWO-5221) and VI-2 enramination.

0330t as-as

Relief Recuest No.

Examination Area RR 32 Voluinetric exam of RHR heat exchanger nozzle inner radius RR-33 Relief request withdrawn RR-34 Volumetric exam of Class 2 piping welds RR-35 Technique for volumetric exam of thin wall piping RR-36 Volumetric exam of Class 2 thin wall piping RR-37 Volumetric exam of small-diameter Class 2 piping RR-38 Subsection IWE RR 39 Mechanized volumetric examination of 1

pressure-retaining shell and head welds in the reactor vessel outside the beltline region RR 40 Notch length in basic ultrasonic calibration blocks for examination of vessel welds RR-41 Calibration blocks for reactor vessel nozzle to safe end welds RR 42 Volumetric examination of nozzle inner radius section for steam generator inlet and outlet nozzles RR-43 VT 4 visual examination of snubbers RR-44 Class 2 piping hydrostatically tested to Class 1 requirements RR 45 Relief request withdrawn RR-46 System pressure test on Class 2 components RR 47 Relief request withdrawn RR-48 Relief request withdrawn 000851 63 006 Rev, 4

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Relief Recuest No.

Examination Area RR 49 System pressure test on Class 3 vertical pit type pumps RR-50 System pressure test on Class 3 components RR-51 Class 3 system functional test on systems subjected to Examination Category 0-B requirements RR-52 Reactor Vessel integrally welded attachments RR 53 Class 3 hydrostatic test on Spent Fuel Cooling and Purification RR-54 Relief request withdrawn conditionally RR 55 Intentionally blank RR-56 Intentionally blank 4

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000851 64 006 Rev 4

VEGP-1 E8..11 Comoonent or Relief Area Volumetric examination of pressure-retaining welds in pressurizer (Class 1).

Reauirement from which Relief is Recuested Item No. B2.11, Category B 8, requires a volumetric examination of the weld volume shown in Fig. IWB-25001.

Item No. B3.110, Category B-D, requires a volumetric examination of the weld volume shown in Fig. IWB-2500 7(b).

Item No. B5.40, Category B-F, requires a volumetric and surface examination of the volume and area shown in Fig. IWB-2500-8.

Each examination requires 100% of weld length be covered.

Relief is requested from performing a 100% ultrasonic examination of the weld length due to physical limitations which prevent complete examination coverage of the welds.

Basis for Relief Geometric configuration presents physical limitations which prevent complete coverage of welds by ultrasonic examination. The welds on which a complete Code examination cannot be accomplished are listed in Attachment 1.

Alternate Examination l

The required Code surface examination will be performed on the nozzle to safe-end welds. An ultrasonic examination will be performed on the affected welds to the extent shown in Attachment 1.

In addition, a surface examination will be performed on the head-to-nozzle welds to supplement the ultrasonic examinations.

000851 6-18 006 Rev. 4 1

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l RE12 Comoonent or Relief Area 1

Examination of (1) the nozzle inner radii and (2) the reinforcing plate-to-vessel welds of the Residual Heat Removal (RHR) heat exchangers, 11205-E6-001 and 002 (Class 2).

Examination Area Identification Numbers include IR01, IR02, WO9, W10, W0ll, and W012 for each of the subject heat exchangers.

Reauirement From Which Relief is Reauested (1) Item No. C2.22, Category C-B, Table IWC-2500-1 of ASME Section XI requires a volumetric examination of the inner radius section of pressure retaining nozzles (greater than 12-inch nominal pipe size) in vessels with nominal wall thickness greater than 1/2-inch.

(2) Item No. C2.31, Category C-B, Table IWC-2500-1 requires a surface examination of the reinforcing plate-to-vessel welds in vessels greater than 1/2 inch nominal wall thickness.

Relief is requested from the above examination requirements.

Basis for Relief (1) Figure No. IWC-2500-4(c) of ASME Section XI which constitutes the i

examination requirement for Examination Area Identification Numbers IR01 and IR02 does not illustrate the nozzle design of the VEGP-1 RHR Heat Exchangers. The configuration of the nozzles at VEGP-1 differs from the configuration depicted in the Code figure. Attachment I depicts the configuration at VEGP-1. Although the reinforcing plate welded to the vessel has a rounded configuration in the flow path,-it is not a true

" nozzle inner radius" when compared with the configuration in Figure No.

IWC-2500-4(c).

It is not practical to perform an inner radius ultrasonic examination since the interface between the reinforcing plate and the RHR Heat Exchanger vessel wall precludes an adequate volumetric examination.

000851 6-58 006 Rev. 4

i VEGP-1 M-ll Basis for Relief (Cont'd)

(2) Figure No. IWC-2500 4(c) of ASME Section XI which constitutes the examination requirement for Examination Area Identification Numbers WO9, W10. W0ll, and WO12 does not illustrate the reinforcing plate-to-vessel design of the VEGP-1 RHR Heat Exchangers.

Refer to Attachment I for the.

t VEGP-1 configuration. The reinforcing plate at VEGP-1 is welded to the inside diameter of the heat exchanger wall with no nozzle-to-reinforcing plate contact (welds). The reinforcing plate to-vessel welds are inaccessible. Therefore, it is impractical to perform a surface examination on the reinforcing plate-to-vessel welds WO9, W10, W0ll, and W012 due to their inaccessibility.

I For the reasons discussed above, GPC has determined that implementation of the Code requirements is impractical. Accordingly, relief from the Code requirements is sought from the NRC as allowed by 10 CFR 50.55a (g) (5) (iii).

1 Alternate Examination in Lieu of ASME Section XI Reauirements (1) As discussed above, due to the lack of true nozzle inner radii, an adequate ultrasonic examination cannot be performed for Examination Area Identification Numbers IR01 and IR02 for the VEGP-1 RHR Heat Exchangers due to the interface between the reinforcing plate and the RHR heat exchanger vessel wall. Those examination areas are to be deleted from the inservice inspection plan document since true nozzle inner radii do not exist.

(2) Due to their inaccessibility, no surface examination of the reinforcing plate-to-vessel welds WO9, W10, W0ll, and W012 can be performed. No alternate examination, e.g., volumetric examination, can be performed or is proposed due to the configuration involved.

The interface between the reinforcing plate and the RHR heat exchanger vessel-wall precludes an adequate volumetric examination from being performed for the.

aforementioned welds. No compensating increase in the level of quality and safety would be realized should an alternate examination, e.g.,

volumetric examination, be performed.

000851 6-58a 006 Rev 4

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