ML20097F887

Forwards Responses to Address Concerns Raised in 920128 SER Re VCSNS ISI Program.Util Reviewed Design & Installation Documents for Supports & Verified Supports Not Welded Attachments

ML20097F887
Person / Time
Site:	Summer
Issue date:	06/10/1992
From:	Skolds J SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9206160140
Download: ML20097F887 (9)

Text

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South Carolina Electric & Osa Company John L. Skolde P O Con 88 Vice Pr2sioInt Jinkinsvilts, Sc P906$

Hucle:r OportUons (803)34 440

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SCE&G j

t June 10,1992

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Document Control Desk j

U. S. Nuclear Regulatory Commission Washington, DC 20555 i

j Gentlement

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET.NO. 50/395

s OPERATING LICENSE NO. NPF-12 RESPONSETOISIPROGRAMSEP.'(NRR1421-1)

South Carolina Electric L Gas Comptttv-(SCE&G) is submitting the attached' responses to addre - ")e concerns raised in the January 28. 1992, Safety.

1 Evaluation Report (SER) regarding the. Virgil C. Summer Nuclear Stction's

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'(VCSNS)InserviceInspection:(ISI) Program.

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Attachment I resolves the four items identified in tN SL2 (3; preventing the ISI program from being. acceptable. Attachment'IILWitnoraws relief request 1

1-Press-4 and requests that' additional information be-substituted with a

respect to relief request 1-P.ipe-2, 2-Pipe-1, and 2. Pipe-2.

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Should you have any questions concerning this matter,please' contact Mr..

i David-Haileat(803)345-4322.

Very truly.yours,:

(.h John,L. Skolds3 DCH: led Attachment Et c:

0. W. Dixon-Jr.

General. Managers

~3 R.cR.-Mahan-.

NRC Resident: Inspector

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R. J. WhiteE

-J. D. Knotts Jr.-

L-S. D. Ebneter-

?RTS T(810 15j NRRc14RI).

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-G. F. Wunder~

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NUCLEAR EXCELLENCEi-A SulmER TRADITIONI-9 7

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Attachment I to Document Control Desk Letter NRR 1421 Page 1 of 4 4

The following is a restatement of the four SER items listed as a concern and requiring resolution in order to bring the ISI Program into full compliance with ASME Section T.I requirements. Each of these items is followed by a response which resolves the respective concern.

SER ltes 1:

1) Examinations scheduled for Class 1 and 2 Categories B-H, B-K-1, and C-C.

integrally welded suoports, do not include sone apparently integral supports shown in some FSAR drawings.

(a)

The pressurizer nas what appears to be welded pads for lateral support (FSAR, figure. 5.5-10).

(b)

-The reactor coolant pumps are shown to have three supports each welded to the pump casings (fSAR, Fig. 5.5-9).

(c)

The steam generators appear to have supports welded to the lower head and Class 2 lateral supports welded to the lower shell (FSAR, Fig. 5.5-8).

(d)

The pressurizer has two lifting trunions.

Some of these attachments may have been acluded from the program because they do not bear a load during normal opeation. Paragraphs IWB-2500 and TWC-2500 do not require the volu'netric or surf ace examination of integrally welded a'tachments not used for support or restraint of components. However, the ASME Code Conrnittee has indicated that the requirements of IWA-5000 and IWC-5000 apply to these kinds of supports. Therefore, these supports should be included in the program unless the licensee can demonstrate throvgh relief

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requests that such examinations are impractical.

Response: A review of the FSAR drawings indicates that the drawings lack sufficient detail to determine the actual configuration of the supports.

SCE&G has reviewed the design and installation documentation for the above supports and has verified.that the. supports are not welded attachments.

The following is a description of each support configuration:

(a)

Pressurizer support oads (FSAR Fig. 5.5-10) - These pads are non-integral supports (not attached to the pressurizer) but are support pads assembled in a proximity fit configuration to limit movement in the horizontal plane.

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Attachment I to Document Control Desk letter NRR 1421 Page 2 of 4 (b)

Reactor _ coolant pump supports (FSAR Fig. 5.5-9) - These supports are not welded attachments but rather are cast as an integral portion of the pump casing.

(c) iteam aenerator supports (FSAR Fig. 5.5-8) - The lateral supports are non-integral supports that are assembled in a proximity fit configuration to limit movement in the horizontal plane. Also, the support pads on the lower head are not welded attachments but rather are cast as an intergral portion of the lower head.

(d)

Pressurizer liftina trunions (FSAR Fig. 5.5-10) - These trunions are not welded attachments but rather are cast as an integral portion of the pressurizer.

Due to the verified configuration of the listed supports, SCEf,G considers VCSNS's ISI Program to be correct and does not intend to modify the program with regards to the listed supports.

SfR ltem 2; There are not examinations scheduled on the Class 2 steam generator tube sheet-to-shell welds (Category C-A, item C1.30).

The licensee 4

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states in the program tables that the S/G "A" Class 1 tube sheet-to-lower head weld examination (Category B-8, item B2.40) meets the requirements for examining the Class 2 tube sheet-to-shell welds. Unless the licensee can satisfactorily explain this statement and the examination plans (if any) for welds 5, 6, and 8 of isometric (GE-2-Il00), a Class 2 tube sheet-to-shell weld at a structural discontinuity should be scheduled for examination.

Response: The subject welds were incorrectly identified in the ISI Program as Class I welds. The correct classification is Class 2. Category C.A. Item C1.30 as stated above. These welds were inspected during VCSNS's first refueling outage as Class I welds. The code inspection requirements for these Class 2 welds were met by the Class 1 inspection therefore, there are no intentions to re-examine these welds in the first inspection interval.

However, VCSNS will revise the ISI Program to correctly identify these welds as Class 2 welds.

SER Item 3: The pressure test ~ program (GTP-304, Rev. 0)'contains a list of 14 Class 2 system relief requests. These same systems appear on a list of pressure tests to be conducted as part of Appendix J containment leak testing. The actual relief requests are not included, but earlier documents contain relief requests in which Appendix J. leak testing was to be an alternative to Code-required pressure testing. The' licensee's most recent I

position, however, has been to withdraw the 14 relief requests.

Instead, he

Attachment I to Document Control Desk tetter NRR 1421 Pa.ge 3 of 4 interprets that an exemption from eacn pressure test applies per Paragraph IWC-1220. This paragraph is not a valid basis-for excluding components from the required pressure tests.

Category C-H,. <hich governs Class 2 pressure testing, contains a note that "Therearenoesemptions(cc)exclusionsfromtheserequirementsexceptas specifiedinIWA5214(R6pairsandRepiscements)." The ASME Code Committee further clarified the definitiun of me terminology in IWC-1220 of the 1983 d

Code edition. Hence, it is SAIC 1 position that all Class 2 systems are subject to pressure testing pea Code requirements.

in reviewing his classification of Class 2 system, the licensee can use the following definitionfromExaminationCategoryC-H(1980 Edition):

"The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normallyclosedvalve(includingasafetyorreliefvalve)orvalvecapable of automatic closure when the safety function is required."

Response: SCEt,G agrees that, in light of the clarification inserted in the later editions of the ASME code, the 1977, Summer 78 version of IWC-1220 was misinterpreted and the 14 system hydrostatic tests were not eligible for exemption. However, the VCSNS ISI Program currently requires the performance of system pressure testing for the 14 systems. Therefore, the requirements of IWC-2500 will be satisfied by appling the provisions of Code Case N-498 in conjunction witn the system pressure testing of these systems.

This approach eliminates the need for an exemption or a relief request to comply with IWC-2500.

SD ltem 4: The component support program (GTP-305, Rev. 2) distinguishes between (a) visual examinations of supports not required to be examined by thetechnicalspecifications(componentsupports)and(b)functionaltestsof mechanical and hydraulic snubbers required by the Technical Specifications (tech. spec, snubbers). Tection 4.4.1 of GTP-305 clearly shows that all component supports requirtJ by the Code to be examined will be examined.

The examination scheduled for. tech spec, snubbers, given in Sections 4.4.2 and 4.4.3 of.GTP-305, are based on failure rates.

It is also stated that the technical' specific'ltions govern the examination frequency of these snubbers.

There is a code requirement to visually examir.o snubbers in addition to testing samples for functional adequacy. Since the functional testing of snubbers in the Technical Specifications.is based on sampling, all requirements in Tables IWB-2500 and IWC-2500 (77S78) may not be covered.

There is no statement that the extent of examination required by the Code will be met with regards to the additional visual regulrMents of Categories B-K-2 and C-C in 77S78 or Category F-C in 77579, it would, therefore, be

Attachment I to Document Control Desk letter NRR 1421 Page 4 of 4 appropriate for the licensee to insert a statement that indicates a commitment to examine all snubbers required by the applicable Code O'$79).

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Egiponse: SCELG agrees with item 4 and has included all snubbers required to be examined by Tables IWB-2500-1 and IWC-2500-1 in the inspection manual ISE.

2 which replaced GTP-305.

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. 1 to Document Control Desk letter NRR 1421 Page 1 of 1 The following are responses to the request for additional information associated with relief requests 1 Press-4, 1-Pipe-2, 2-Pipe-1, and 2-Pipe-2.

With more up-to-date inspection methods and by the appling Code Case N-460, the scope of welds needing relief has been reduced. As a result SCE&G no longer requires the 1-Press-4 relief request and therefore requests that it be withdrawn.

Also, with regards to relief requests 1-Pipe-2, 2-Pipe-1, and 2-Pipe-2, the safety evaluation report stated "...that relief be granted with the condition that a listing of welds for which relief is requested and a description of the extent of examination coverage that can-be obtained be provided by the Licensee." Accordingly, the following pages contain lists of welds sorted by relief request that cannot, by the application of Code Case N-460, be satisfactorily examined and thereby requiring relief.

Each weld has a description of the weld inspection limitatien and, were possible, describes the percentage of weld that was inspected.

For welds yet to be inspected in Refuel 7, the percentage of weld inspection cannot be determined by review of the preservice data. The Refuel 7 inspection data is needed to finalize the number of welds which are applicable to Code Case N-460.

The following list of welds supersedes any previous list of welds associated with the respective relief requests 1-Pipe-2, 2-Pipe-1, and 2-Pipe-2.

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153 FEttEt RtouEST (151 n of 03/h/92 for hELIEf RtQUEST T PIPE-2 CODE C&sE NDE u!5-1 PERCENT ISOMETQlC WELD CATEGORT ITEM utMBER TYPE COMPONE4T ConFIGUEAIION DATE NCE R1 PORT CD9 TETE LISTED LIMITATION CGE-1-4100 12 s-J 89.11 UT RC PIPE / PUMP thtET RF 1 PES n?$2-015 40 twSULATION SUPPORT.1/2 VEE ONE SIDE CGE-1-4100 13 s-J E9.11 UT RC PIPE 1Ptmp 58 1 kES O252-075 50 1/2 VEE CNE SIDE CGE-1-4200 12 IPJ B 9.11 UT PtMP/EL80u RF 4 VCSU-0452 40 CMsE SIDED Es AM. PUMP

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CGE-1-4203 12 8-J B 9.11 UT fIPE/BRANCN CONNEtit0W RF 6 VCSU-0911 76 CODE DATA PLATE. 1 1/2 WEE ONE SIDE CGE-1-4300 12 s-J s 9.11 UT RC swP/ ELBOW RF T PROJECTED USE N/A DCSIGN CD4FIGURAT10N,8E AM REDl8ECTION

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CGE-1-4300 13 8-J 8 9.11 UT RC PUMP / PIPE RF 7 PROJECTED USE N/A DESIGN CCAfIGURATICm,8EAM REDTRECTion

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CGE-1-4301 1

8-J B 9.11 UT PIPE /VAtVE RF 6 VCSu-0916 87 OsE SIDED ERAM, SUPPORT CESTRUCTION

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CGE-1-4303 14 8-J d 9.11 UT PIPE / VALVE RF 6 VCSU-0858 83 ONE SIDED ENAM, VALVE AND BRAECM

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CCE-1-6303 18 s-J B 9.11 UT GRAuCH CthmECTIOn/ PIPE sF 7 PROJECTED USE N/A DESIGN C0hFIGUR ATION/SRANCH WOZILE

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CGE-1-4500 13 8-J B 9.11 UT BRANCN COMwECTION/ PIPE RF 7 PROJECTED USE N/A DESIGN CDNFIGURATICS/84AwCW WCZILE "GE 4-4502 18 B-J B 9.11' UT PIPE / REDUCER RF 7 PROJECTED USE N/A LIMITED SCAM AREA / REDUCER

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CCE-1-4502 20 8-J B 9.11 UT PIPE / TEE RF T PROJECTED USE

1. /A DESIGu ConFtGU8Efton,8AAsCN/ SUPPORT

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CGE-1-4504 1

8-J 8 9.11 UT BRA *CH C0huECTION/ PIPE RF 7 FROJECTED USE N/A DESIGm C0h71GURATION/ssAmC# molILE

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CGE-1-4504

• O B-J B 9.11 UT P!PE.~ ELBOW RF 7 PROJECTED USE 4/A SUPPCRT OBSTRUCT!Cas

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CCE-1-4504 30 8-J 8 9.11 UT PIPE / TEE RF 7 PROJECTED USE m/A DESIGu ConFIGtRAf tow / TEE /RESTRAlmi

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we hUMBER OF ENTRIES ints PAGE: H-PROJECTED RELIEF FOR REFUEL 7 NAS BEEN FROM THE REVIEW OF PRE-SERVICE DATA Au& EWG1wEER1mG DRAWIhCS. ACTUAL DAT A PAY ADO OR DELETE WELDS FROM ints LIST.

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V.C. SUMMES NUCLEAR ST ATION ISI RELIEF REQUETI (IST

^C' 03/it h2 for EEL 3tf LEQUEST 2 PfPt-1 CODE CODE NDE NIS-1 PERCE NT l

ISOMETRIC WELD CATEGORY ITEM NUMBER TYPE COMPONENT CONFIGURAf!ON DATE NDE REPOET COMPLETE LISTED LIMITAftON

- CGE-2-2101 16 C-F C 5.21 UT PtPE/ VALVE RF 7 PROJECTED USE N/A DEstGN CONFIGURATIOh/ WELDED ATTACMMLui t

" CGE-2-2103 C-F C 5.21 UT PIPE / VALVE RF T PROJECTED USE N/A CESIGN CONFIGURATION / VALVE /ERANCH i

CGE-2 *05 87LS-12 C-F C 5.22 UT to=G SEAM /PLPE RF $

WCSu-OF01 48 SADOLE FLATE CWERS LONG SE AM CU *- w 0 1

C-F C 5.21 UT FIPE/ S/G OITLET RF 4 VCSU-0468 E8 SUPPORT ANGLE IROH ceSTRUCTtow CGE-2-2201 12 C-F

.c 5.21 UT PIPE / VALVE RF T PROJECTED USE N/A DESIGN CONF;GURAfl04/VALV"/gEAniCM CGE-2-2201 46LS-57 C-F C 5.22 UT PIPE / PIPE RF 4 VCSU-0296 41 WMIP RESTRAINT /3hSULATION OBSTEUCTION

- CCE-2-2202 19 C-F C 5.21 UT PIPE / ELBOW PSI VCSU-0017 68 sa*NCn CON =ECTION & WELD CROWN

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Ct.E-2-2302 3

C-F C 5.21 UT PIPE / ELBOW RF 7 'ROJECTED USE h/A DESIGN CONFIGURATION / WELDED ATTACMMENT 4...........................................................

' CCE-2-2302 4

C-F C 5.21 UT PIPE / ELBOW RF 7 PROJECTED USE N/A DESIGN CONFIGURATION / RESTRAINT CGE-2-2302 5

C-F C 5.21 UT PIFE/ ELBOW RF T PROJECTED USE N/A DESIGN FDsFIGURATION/BRANCN/RESTaAINT l

CGE-2-3302 2/

C-F-C 5.21 UT PIPE /RB PEhMETRATION RF 7 PROJECTED USE N/A DESIGN CONFIGURATION /ECSTRAINT CGE-2-2303 3

C-F C 5.21 UT PIPE / ELBOW RF 7 PROJECTED USE N/A DESIGN CONFIGURATION / JET SMIELD/ SORE I

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. NUMBER OF ENTRICS THis PAGE: R PROJECTED RELIEF FOR REFUEL 7 NAS BEEN FRCM THE REVIEW OF PRE-SERVICE DATA AND ENGINEERING DRAWINGS. ACTUAt DATA MAY ADD OR DELETE WELDS FROM THIS LIST.

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v.C. SUMMLR NUCLEAR STATION as of 03//o/92 ISI REL!EF REQUEST t tST for RELIE F REGUEST 2-P!7f-2 CODE COPE NDE NIS-3 PERCENT ISOMETRIC WELD (OEGORY ITEM WUM8ER TYPE COMPONENT CONFIGURATION DATE NDE REPORT CC M LETE LISTED LIMIT *T104 CGE-2-2500 36 C-F C 2.1 UT FLANGE / PIPE RF 2 VCW-0030 43 WELDED iTTACNMENT OBSTRUCTION CGE-2-2521 11 C-F C 2.1 UT ELBOW / PIPE aF 2 VCsu-0068 f4 WELDE7 ATTACMMENT OSSTRUCTION CGE-2-2521 23 C-F C 2.1 UT PIPE / VALVE RF 2 VCSu-0033 65 ONE SIDED ENAM, 1/2 VEE, WELD PREP AT T0E CGE-2-2523 89 C-F C 2.1 UT TEE / ELBOW RF T PROJECTED USE N/A DESIGN CONFIGURATION / TEE / ELBOW INTRADCSE CGE-2-2525 C-F C 2.1 UT PIPE /RB PENNETRATION RF T PROJECTED USE N/A DESIGN CONFt:URATION/ RESTRAINT CGE-2-2550 22 C-F C 2.1 UT EL8OW/ PIPE RF T PROJECTED USE '

N/A LIMITFD SCAN AREA / WELD / WELD CGE-2-2550 23 C-F r 2.1 UT PIPE /N0ZZLE RF 6 VCSU-0887 40 ONE SIDED ERAM,N0ZZLE, ADJACENT WELD CGE-2-2552 7

C-G C 2.1 UT PIPE / ELBOW RF 7 PROJECTED USE N/A DESIGN CONFIGURATION /RS PEh4ETRATION CCE 2-2553 14 C-G C 2.1 UT PUMP FLANGE / REDUCER RF 6 VCSU-0TT3 TO ONE $1DED EXAM, FLANGE CCE-2 M 5 18 C-G C 2.1 UT PIPE /RS PENNETRATTON RF 7 PROJECTED USE N/A CESIGN CONFIGURATION /R3 PENNETRAT10N CGE-2-2560 6

C-G C 2.1 UT PIPE / ELBOW RF 7 PROJECTED USE N/A DESIGN CONFIGURATION /LATROLET IN SCAN l

NUMBER OF ENTRIE" THIS PAGE: H PROJECTED RELIEF FOR REFUEL 7 NAS BEEN FROM 'HE REVIEW OF PRE-SERVICE DATA AND ENGINEERING DR# WINGS. ACTUAL DATA MAY ADD OR Df LETE WELDS FROM THIS

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