ML18041A132

Confirms 860417 Telcon Agreements Re SER (NUREG-1057) Open Item 4 Concerning Preservice Insp Program,Including Exam of Component Supports & Break Exclusion Zone (Augmented Inservice Insp) Exam of 2-inch Welds & Smaller

ML18041A132
Person / Time
Site:	Beaver Valley
Issue date:	05/13/1986
From:	Carey J DUQUESNE LIGHT CO.
To:	Harold Denton, Tam P Office of Nuclear Reactor Regulation
References
RTR-NUREG-1057 2NRC-6-047, 2NRC-6-47, TAC-62873, NUDOCS 8605190099
Download: ML18041A132 (8)

Text

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ACCESSION NBR: 8b0519009'9 DOC. DATE: 8b/05/13 NOTARIZED: YES DOCKET I FAC IL: 50-412 Beaver Valleg Power Station. Unit 2> Duquesne Light C 05000412 AUTH. NAME AUTHOR AFFILIATION CAREY'S J. J. Duquesne Light Co.

I REC P. NAME RECIPIENT AFFILIATION DENTONp H, R. Off'ice of Nuclear Reactor Regulationi Director (past 851125 TAMi P. Divisian of Pressurized Water Reactor Licensing A (post 8

SUBJECT:

Confirms Sb0417 telcon agreements BER (NUREC-1057) Open Item 4 cancerning preservice insp programs including (augmented inservice insp) exam of 2-inch toelds Sc smaller.

DISTRIBUTION CODE: B001D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: Licensing Submittal: PBAR/FSAR Amdts 5 Related Correspondence NOTES:LPDR 2cgs Transcripts. LPDR 2cgs PDR Documents. 05000412 Application for permit renetual filed.

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR EN CL ID CODE/NAME LTTR ENCL PMR-A ADTS 1 PWR-A EB PMR-A EICBB 2 PWR-A FOB PMR-A PD2 LA 1 PMR-A PD2 PD TAMi P 01 2 PWR-A PSB PWR-A RBB 1 INTERNAL: ACRS 41 6 ADM/LFMB 1 ELD/HDBS IE FILE 1 IE/DEPER/EPB Sb 1 1 IE/DGAVT/GAB 21 1 NRR BWR ADTS 1 NRR PWR-A ADTS 1 NRR PWR-B ADTB 1 NRR ROEi M. L 1 HFIB 1 NRR/DHFT/MTB 1 EQ FIL 04 1 RQN1 3

/D I/MIB EXTERNAL: 24X 1 1 BNL(AMDTB ONLY)

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2NRC-6-047 Duqumne Ut t412) 787-5141 (412) 923-1950 Nuclear Construction DivisIon Telecopy (412) 787-2829 Robinson Plaza, Building 2, Suite 210 Pittsburgh, PA 15205 May 13,, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Peter Tam, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 SER Open Item (4)

REFERENCE:

1) BVPS-2 Safety Evaluation Report, NUREG-1057, October 1985

2) DLC Letter 2NRC-5-154, dated December 26, 1985

3) NRC Letter to DLC, dated January 24, 1986

4) DLC Letter 2NRC-6-034, dated April 9, 1986 GENTLEMEN:

As a follow-on to submittal of the BVPS-2 Preservice Inspection Program (reference 2), Duquesne Light Company (DLC) held a telecon with your staff (Messrs. P. Tam, G. Johnson and S. Lee) on April 17, 1986 relative to PSI examination of component supports and Break Exclusion Zone (Augmented ISI) examination of welds 2 inch and smaller size. Agreements reached on the examinations relative to the above are as follows:

1. Preservice Inspection of Com onent Su orts ica e to Wl- - 00 The ASME Section XI Code, 1980 Edition through Winter 1980 Addenda (BVPS-2 PSI Program Baseline) states in IWF-2200(b): nAll examinations shall be performed following the initiation of hot functional tests."

In the DLC submittal PSI Program Document No. NCDP 2. 13, paragraph 6.7.3, the following was stated as a clarification: nDLC applies the IWF-2200(b) criteria to nHotn ()200'F) systems."

The discussion with your staff estabished and clarified that the concern for application of IWF-2200(b) was for component supports subject to thermal stresses and/or movements, and was therefor e Sb051't)00's)ts) Sb05i3 PDR ADOCK '

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Page 2 applicable to those systems which are subjected to "Hot" temperatures.

The establishment of a system operating temperature of ")200'F" as being "Hot" was agreed upon. Therfore no change to NCDP 2.13 is necessary.

2. Preservice Ins ection Examination Re uirements of Com onent u orts a p scab e to IWF-2200 a vs. IWF-25 0 a and b The ASME Section XI Code, 1980 Edition through Winter 1980 Addenda (BVPS-2 PSI Baseline) states in IWF-2200(a): "All examinations listed in IWF-2500-2 shall be performed completely, once, as preservice examination."

In the DLC PSI Program procedures for component supports (not includ-ing snubbers, which are examined 100K in PSI) and in DLC Program Pro-cedure NCDP 2.13. 6, paragraph 6. 1. 2 (submitted with BVPS-2 PSI Program, reference 2), selection of component supports utilizes IWF-2510(a) and IWF-2510(b) .

The di scussi on wi th your staff establ i shed and cl arif i ed that the selection of components supports for PSI utilizing IWF-2510(a) and (b) will meet the intent of providing an examination baseline for In-service Inspection. DLC also indicated that in addition to utilizing multiple stream (train) and multiple components criteria for establishment of "all in one train" of component supports, all Class 1 component (piping) supports applicable to Class 1 i ntegraT (piping) attachments, which were selected from any of the multiple trains, would also be included in the examination requirements. Pro-cedure 2.13.7 will be changed to reflect the above.

3. Preservice Ins ection of 2 inch and Smaller Welds in Brea xc usion one u mente Ins ection The BVPS-2 FSAR (section 6.6.8) and DLC submitted PSI Procedure NCDP

2. 13, paragraph 6.5.5 identified Break Exclusion Zone (Augmented ISI) and extent of examinations. DLC submitted PSI Procedure NCDP 2. 13.5, step 6.2.2.5, "Limitations/Clarifications", further indicated that:

"Miscellaneous branch connections and socket welds (1 1/2 inch. and 2 inch. sizes) are not included in the PSI examination."

The agreement reached is based on the folowi ng:

(a) The specific requirements for Break Exclusion Zone piping welds is for a "volumetric only" examination (ultrasonic methods at BVPS-2).

(b) Obtaining meaningful results by ultrasonic methods for miscel-laneous branch connections and socket welds (1 1/2 inch and 2 inch sizes) is highly improbable.

(c) The intent of PSI examination as a baseline for ISI is to provide for trending service-induced degradation.

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uaited States Nuclea gul atory Commission Beaver Valley Power ation-'Unit 2 SER Open Item (4)

Page 3 The agreement reached is to perform surface examinati'on with sampling criteria compatible with Class 2 weld selection criteria for PSI (i.e.

1 0 X sampling, prorated).

An FSAR Amendment to paragraph 6.6.8 and revision to NCDP 2.13.5 will be forthcoming to incorporate the above clarifications. In-process examination of Break Exclusion Zone piping welds will also incorporate this criteria.

The above items should be considered part of the PSI Program submittal which is presently under staff review and for which a confirmatory status of the part of SER Open Item (4) concerning PSI has been requested by July 1, 1986 (reference 4).

DUQUESNE LIGHT COMPANY By J. J. Ca y Vice President

/jdw AR NAR cc: Mr. P. Tam, Project Manager Mr. J. M. Taylor, Director (3)

Mr. M. Troskoski, Sr. Resident Inspector Mr. L. Prividy NRC Resident Inspector INPO Records Center NRC Document Control Desk CRIBED AN ORN TO BEFORE ME THIS DAY OF , 1986.

Notary Public SHEILA 0. FATTORE, IIOTARY PUBLIC SIIIPPIIlGPORT BORO, BEAVER COUIITV MY COtHl5ISSIOIc ESP IRES OCT, 23, 198) uev'cc, p" >>~gt~."nb Assoc!artist et Itotot4-

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