ML20107F230

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Forwards Response to 841023 Request for Addl Info on SER Open Item 3 Re Preservice Insp Program,Based on 841126 Meeting W/Matls Engineering Branch.Relief Requests Will Be Submitted by 851101
ML20107F230
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 02/14/1985
From: Mittl R
Public Service Enterprise Group
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8502260023
Download: ML20107F230 (11)
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Text

wa O PS G Company PutAc Sennce Ekectnc and Gas 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newar', NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation February 14, 1985 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attn:

Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:

RESPONSE TO HCGS SER OPEN ITEM 3 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 The Hope Creek Generating Station Safety Evaluation Report (SER), Sections 5.2.4.3 and 6.6.3, identify a requirement for Public Service Electric and Gas Company (PSE&G) to provide for NRC staff review acceptable resolutions to three (3) concerns associated with the Hope Creek Pre-Service Inspection (PSI) program.

These concerns were

-previously' identified to PSE&G in Request for Additlonal Information-Number - 1 ( RAI-1), dated October 23, 1984, as RAI-1-' Items 1, 2, and 3.

The SER identifies these same concerns as part of SER Open Item 3.

By PSE&G. request, a meeting was held on November 26, 1984, with.NRC Materials Engineering Branch (MTEB) personnel to discuss the staff's concerns with the PSI program.

Based on information obtained at this meeting, PSE&G has prepared responses to-Items 1, 2, and 3 of RAI-1., and hereby submits these-responses as the attached.

This portion of 'SER Open

' Item 3, therefore, is. considered closed unless PSE&G is notified otherwise.

The remaining portion of SER Open Item 3 requires PSE&G to submit relief requests, with supporting justifications, for all components' that will not be examined to the requirements ofLthe ASME code, as specified in Sections 5.2.4.3 and 6.6.3 of the SER.

As acknowledged in the referenced SER sections, 85022g0d0 hQ54 "

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The Energy People

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Director of Nuclear Reactor Regulation 2

2/14/85 the specific areas where code requirements for pre-service and/or in-service inspection cannot be met will be identi-fied after the pre-service examinations are performed.

Based on the current pre-service examination schedule, all PSI relief requests will be submitted by November 1, 1985.

Should you have any questions in this regard, please contact us.

Very truly yours, JCfl Attachments-I C

D. H. Wagner USNRC Licensing Project. Manager A. R. Blough

-USNRC Senior-Resident-Inspector.

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ATTACHMENT A PSE&G RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION NUMBER 1 (RAI-1)

REGARDING THE HOPE CREEK GENERATING STATION 4

PRE-SERVICE INSPECTION PROGRAM J

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NRC RAI-1,' Item 1:

- Paragraph 10 CFR 50.55a(b)(2)(iv) requires that ASME Code Class 2 piping welds in the RHR systems, ECCS systems, and CHR systems _shall be examined.

The staff review of the Hope Creek PSI program shows extensive numbers of surface-only examinations-for piping welds in such systems.

In addition, these. systems should not be completely exempted from pre-service volumetric examination based on Section XI exclusion criteria 1 contained in IWC-1220. 'To satisfy the inspection requirements of General Design Criteria 36, 39, 42, and 45, the PSI must include volumetric examination of a representa-

.tive sample of welds in the RHR, ECCS, and CHR systems.

The

.PSILprogram should be revised to include a volumetric exami-nation of a representative sample of.the welds in these systems.. At' other BWR's, the selection of welds and exami-nation methods contained in Code Section XI Winter.1983 Addenda Paragraph IWC-1220 and-Tables IWC-2500 has' been determined 'to be acceptable. -This should make the PSI examination methods more compatible with. future ' ISI require-

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ments.

PSEEG Response:

- The Hope Creek Pre-Service Examination plan _(PSI).is being Jaugmented to' include additional welds selected in accordance:

with the 1983 Edition-of.ASME Section XI,-Winter 1983

' Addenda.

These! additional welds are identifed in

Attachment:

l '..-The PSI-plan submitted April 13, 1984, is'being; revised

/to tincorporate -these. augmented Linspections..The revised' plan will be submitted by March 18, 1985.

NRC RAI-l',1 Item?22:

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?The-staff review of the. PSI plan'indicat'es-that the'use'of?

cladding ;on s pipi'ng welds 1may. interfere with ef fective ultrasonic. examination. : Plansifor qualification of the volumetric examination procedure to : be: used ~ on -the,:, subject t

weldsishould be discussed.

Standard, minimum code radio-graphy may not 'be capable Lof detecting: service-induced degradation because the, detection ofieracks isistrongly,

- - i dependent 'on the ' anglef of the : central axis f of ;the l radiation-

, ; beam ~with1 respect;to the predominant crack plane.n..If

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radiography;isiplanned," provide the. technical; justification,-

including qualifications f and _ procedureT requirementsito-Ldemonstrate that theyradiography procedure is effective 1for l volumetric' examinations?? ~

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9 LThe' Applicant should also1provideidetaile'd information-describing the specificiwelds with ^ corrocion resistant -

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, cladding.land utypical dimensions of(the cladding.

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PSE&G Response:

In addition to the information presented by PSE&G on Novem-ber 26,1984 -(see NRC meeting summary dated December 18, i

1984, for details),7 the NRC requested more detailed informa-tion.on typical cladding dimensions of CRC weld joints. shows. sketches of the Reactor. Recirculation Loop piping Loop A and B and cladding dimensions for various

. nominal pipe. sizes.

NRC RAI-1, Item 3:

The staff review of the PSI plan has not identified any

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' pre-service examinations scheduled for the Scram Discharge 7

. Volume"(SDV) system.

NUREG-0803, " Generic Safety Evaluation j'.

Report Regarding Integrity of BWR Scram System Piping,"

< recommended that periodic ISI - of thel-SDV system ' be performed that meets the -requirements ' for ASME Code - Class 2 piping.

  • This document was implemented by Generic Letter 81-35. dated August 31,.1981, and was addressed to all BWR holders'of CP.'s and; Applicants for OL's..

Therefore, the' PSI plan should be revised to reflect the appropriate pre-service examinations ofq the SDV system'. required by Section. XI ~ of the

- ASME Code-and recommended by NUREG-0803.

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.PSE&G Responses-

[The'SDV--system at Hope Creek ^is' designed and fabricated to E

Nuclear: Class :2 requirements:and will be visually examined during pressure : tests (VT-2) :in accordance-with the.1977:

Edition of L Section lXI as; a Nuclear Class,2-System.

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In

.accordance'with IWC-1220 (b),:this? system lin exempt:from s

. otherL ~ examination -requirenients,.. The PSI;planisubmitted 1 April 13,:1984,. has.been revised identifying the above'..

11nformat' ion.and'will.be submitted (to the: NRC"by March 18

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i Augmented Class 2 Preservice Weld Inspections 1

Residual Heat Removal System Piping Line Number weld Number 1-BC-18GBB-0048 8

Pipe to Elbow 11 Pipe to Tee f

l-BC-18GBB-004C 2

Pipe to Elbow l

3 Elbow to Pipe 1-BC-12GBB-004B 3

Elbow to Pipe 1-BC-18GBB-019A 3

Pipe to Valve 10 Pipe to Elbow

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1-BC-12GBB-019 2

Pipe to Elbow 3

Elbow to Pipe

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1-BC-18GBB-027 3

Elbow to-Pipe 7

Pipe to Valve 1-BC-30HBB-044 1

Reducer to Flange 1-BC-24HBB-044 4

Elbow to Pipe 1-BC-30HBB-046 3

Pipe to Flange 1-BC-24HBB-046 2

Elbow to Pipe l

l-BC-18GBR-050A_

6 Pipe to Tee l

l-BC-18GBB-050B 1

Tee to Pipe

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. Elbow to Pipe 6-Pipe ~to Elbow j,

8 Pipe to Elbow.

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1-BC-18GBB-063A-8' Pipe to Elbow 12.

Pipe to E1 bow l

, Pipe to Tee-

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.Pipo to: Tee 21 Pipe'to Elbow 1-BC-12GBB-063A

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Pipe'to 81 bow L1-BC-12GBB-0638 1

Reducer to Pipe ~

3 Bibew to Pipe ~

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2-i 1-BC-18GBB-066A 3

Pipe to Valve 7

Pipe to Elbow i

20 Elbow to Pipe 1-BC-18GBB-072 6

Pipe to Tee 12 Pipe to Valve 14 Pipe to Elbow 15 Elbow to Pipe 1-BC-18GBB-075 3

Elbow to Pipe 5

Elbow to Valve 1-BC-30HBB-087 3

Pipe to Flange 1-BC-24HBB-087 1

Nozzle to Elbow Flange to Pipe l-BC-30HBB-088 2

1-BC-24HBB-088 3

Pipe to Elbow i

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i-Reactor Core Spray System Piping l

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Pipe to Elbow 8

Elbow to Pipe 11.

Piya to Elbow 13 Pipe to Elbow t

16 Elbow to Pipe Pipe to Elbow

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Elbow to Elbow.

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19 Elbow to Pipe l

20 Pipe to Elbow 21 Elbow to Pipe 4

22 Pipe to Tee p

23 Tee to Pipe 24 Flange-to Reducer l-BE-14GBB-009 6'

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Elbow to Pipe-11 Pipe to Elbow.

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'14 Pipe to Elbow 15' Elbow to Pipe.

18 Pipe _to-Elbow 19 Elbow-to Elbow

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Elbow'to Pipo 21-Pipe to-Elbow.

3' 22-(Elbow to Pipe 24 Tee'to Pipe, t

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Reducer to pipe 4

Valve to Pipe 1-BE-12GBB-016 1

Reducer to Elbow 4

Valve to Pipe 1-BE-12GBB-017 4

Valve to Pipe 5

Pipe to Elbow 1-BE-12GBB-018 2

Elbow to Pipe 3

Pipe to Valve 1-BE-16HBB-044 16 Pipe to Flange 1-BE-16HBB-045 15 Tee to Pipe 1-BE-16HBB-046 17 Flange to Pipe 1-BE-16HBB-047 14 Pipe to Tee D-LFL-5 e

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