LR-N990112, Requests Approval of ASME Code Case N-567,allowing Use of Replacement Valve for Containment Atmosphere Control Sys Valve That Was Constructed to Earlier Version of ASME Code than Existing Valve

Requests Approval of ASME Code Case N-567,allowing Use of Replacement Valve for Containment Atmosphere Control Sys Valve That Was Constructed to Earlier Version of ASME Code than Existing Valve

ML20207K367
Person / Time
Site:	Hope Creek
Issue date:	03/05/1999
From:	Dawn Powell Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N990112, NUDOCS 9903170155
Download: ML20207K367 (9)

Text

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• OPSEG i l

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 051999 i I

LR-N990112 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REQUEST FOR APPROVAL OF CODE CASE N567 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Gentlemen:

Pursuant to 10 CFR 50.55a(a)(3) and 10CFR50.55a Footnote 6, Public Service Electric and Gas Company (PSE&G) requests approval of American Society of Mechanical Engineers (ASME) Code Case N-567, " Alternate Requirements for Class 1,2, and 3 Replacement Components,Section XI, Division 1" for a specific situation at Hope Creek.

Specifically, approval of the code case is required to allow use of a replacement valve for a Containment Atmosphere Control System valve that was constructed to an earlier version of the ASME Code than was the existing valve. The replacement valve is identical to the existing valve except that the replacement valve was constructed to an earlier version of the ASME Code. Attachment 1 provides justification for the approval of the code case for this situation. A copy of the code case is included in Attachment 2.

Attachment 3 includes a drawing that shows the valve of concern.

4 Expedited approval is requested by March 15,1999 since the valve replacement could delay the startup of Hope Creek from the current refueling outage.

Should you have any questions regarding this response, please contact Mr. C. Manges at 609-339-3234.

Sincerely, /

A 9903170155 990305 ' / O {i PDR ADOCK 05000354 David R. Powell PDR 2 Director- Licensing / Regulation and Fuels v

Attachments (3)

Timwerisinyurhnk 95-2168 REV 694

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Document Control Desk LR-N990112 l C Mr. H. Miller, Administrator - Region I 3 U. S. Nuclear Regulatory Commission j 475 Allendale Road )

King of Prussia, PA 19406 j Mr. R. Ennis Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 14E21 11555 Rockville Pike Rockville, MD 20852 Mr. S. Pindale (X24)

USNRC Senior Resident inspector - HC Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 1

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Attachmsnt 1 LR-N990112 RsquIct fer Apprcvel of Ced3 Crea N567 ATTACHMENT 1 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 ,

REQUEST FOR APPROVAL OF CODE CASE N567 {

INTRODUCTION Pursuant to 10 CFR 50.55a(a)(3) and 10CFR50.55a Footnote 6, Public Service Electric and Gas Company (PSE&G)is requesting approval to use American Society of Mechanical Engineers (ASME) Code Case N-567, " Alternate Requirements for Class 1, 2, and 3 Replacement Components,Section XI, Division 1" for Hope Creek. Approval i is required to allow use of a replacement valve for a Containment Atmosphere Control system valve (1GSV-138) that was constructed to an earlier version of the ASME Code than the existing valve.

BACKGROUND l i

During the current Hope Creek refueling outage, the 1GSV-138 piston check valve, I which is part of the Containment Atmosphere Control system, failed to satisfy its' Local '

Leak Rate Test, as required by 10CFR50 Appendix J.

The subject valve is a one inch /600# Edward Model 838YT piston check valve. The valve consists of an SA-105 body with an SA-105 bolted bonnet. The body to bonnet bolting is manufactured from SA-193 Grade B7. Edward Valves incorporated (EVI) manufactured the existing valve in accordance with Hope Creek (Bechtel) Specification PP303AQ. This valve was constructed and N stamped in accordance with ASME lil, 1974 Edition, Summer 1975 addenda, Class 1 (NB) requirements and Code Case 1791. The valve is being functionally used in a Class 2 application. The valve assembly is shown on the drawing that is included in Attachment 3. The valve design has an integral stellite seat that has historically been subject to lapping and refurbishment in order to have the valve meet seat leakage requirements. The remaining stellite surfacing on the valve is presently inadequate to permit additional lapping. Due to the small size of the valve, re-application of stellite is not a practical option and the only viable solution is to replace the existing valve. l The 1GSV-138 is required to establish containment integrity and would cause a significant delay to the restart of Hope Creek following scheduled refueling activities if a proper replacement cannot be expeditiously installed. A review of PSE&G's inventory l has identified that there are no duplicate replacement valves in stock in either a carbon l or stainless steel body configuration. Several replacement options are available and are described below.

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Attachm:nt 1 LR N990112 R:qu:ct fer Apprcv 1 cf Ccdm Ccco N567

1. Replacement With Valves of a Different Design The inventory review has identified two valves that could be alternately considered for use. These alternate valves consist of 1500# designs, one with a carbon steel body / bonnet and one with stainless steel. The following table identifies differences 3 between the existing valve and the possible replacements. l EXISTING VALVE REPLACEMENT VALVES MANuFACTuRERIMODEL EDWARD /838YT EDWARD /D-36274 AsME CODE EDITloN/ ADDENDA 1974/ SUMMER 1975 CARBON STEEL 1974/ SUMMER 1975 ADDENDA ADDENDA STAINLESS STEEL 1989/NO ADDENDA CODE CLASS 1 1 PRESSURE class 600# 1500#

WEIGHT Slbs 151bs.

Cv 12 12 END TO-END DIMENslON 4.25 in 6.0 in CENTER TO TOP DIMENslON 3.75 in 3.9 in BONNET STYLE Bolted Threaded with locking collar DP TO OPEN 0.7 - 0. 9 psi 1.0 - 1.5 psi The use of either of the alternately available valves would require a design Change, system re-analysis, and physical modificationo to accommodate their use.

2. Procurement of a New Valve The original equipment manufacturer, EVI, has identified that there would be a six to eight week lead-time to secure the new replacement valve. This delay would significantly extend the restart of the unit. 1 f

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o Attachm!nt 1 LR-N990112 RIqumt far Approval cf Ccda Ceae N567

3. Use of an Identical Valve Constructed to a Different Version of the Code A PSE&G search has identified Arkansas Nuclear One (ANO) as the only expeditiously available source for an identical replacement valve. The only difference between the existing Hope Creek valve and the ANO valve is that the ASME Construction Code that was used for the ANO valve is ASME Section ill,1971 Edition, Summer 1972 Addenda.

Other technical and design considerations are the same. The procurement and utilization of this valve from ANO is the preferred resolution.

JUSTIFICATION FOR APPROVAL OF CODE CASE FOR HOPE CREEK ASME Section XI 1989 Edition, no addenda, is applicable to Hope Creek for Inse',vice Inspections and Repair / Replacement activities for Class 1,2 and 3 component. The 1989 edition of ASME Section XI, specifically IWA-7210 (b)(1) and (c), permit the owner to secure replacement items which meet the original Construction Code or alternately, later editions of the Construction Code. The 1989 Edition of Section XI however does not permit earlier Construction Codes to be utilized in the procurement or installation of replacements.

ASME Section XI Code Case N-567, " Alternative Requirements for Class 1,2 and 3 Replacement Components"was approved and issued by ASME on August 14,1997. A copy of the Code Case is attached for information. This Code Case recognizes that components procured to earlier edition / addenda are technically comparable and that I the use of earlier Construction Codes for the manufacture of components does not reduce the margin of safety inherent to the component. This premise is further supported by the fact that the various ASME and ANSI Construction Code (s) editions / addenda that have been used by US plants, are or have historically been endorsed in regulations promulgated by the USNRC, as part of 10CFR50.55(a), " Code and Standards".

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The use of this Code Case allows for an alternative procurement path for an identical replacement, except for Edition / Addenda applicability, and affords an acceptable level )

of quality and safety consistent with the original design. Further, the use of this code l case provides an acceptable alternative to the present ASME Section XI specified requirements and avoids an undue hardship associated with the restart of Hope Creek  ;

without a compensating increase in the level of quality and safety.

Code Case N-567 is not presently endorsed by the USNRC for industry use through Regulatory Guide 1.147 Revision 11. Pursuant to 10CFR50.55(a)(3) and 10CFR50.55a Footnote 6, PSE&G requests that Code Case N-567 be considered for application at Hope Creek in this situation.

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Attachment 2 Code Case N567 I

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r CASE N-567 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: August 14, 1997 See Numericalindex for expiration and any reaffirmation dates.

Case N-567 and Addenda), a component used for replacement may Alternative Requirements for Class 1,2, and 3 be constructed to an earlier Edition or Addenda of Replacement Components the original Construction Code of the component being Section XI, Division I replaced, provided the following requirements are met:

(a) Any deviations from the Owner's Requirements' Inquiry: What alternative to the requirements of or the original Construction Code' of the component IWA 7210 (IWA-4170 in the 1991 Addenda through being replaced shall be reconciled; the 1995 Edition or IWA-4220 in the 1995 Addenda (b) A report of the reconciliation shall be prepared and later Editions and Addenda) may be used to ac- and made part of the record in accordance wi:h IWA-cept a replacement component constructed to an earlier 6340 (!WA-4910 in the 1991 Addenda through the Ed,ition or Addenda than that of the component being 1995 Edition or IWA-4180 in the 1995 Addenda and replaced? later Editions and Addenda);

(c) Use of this Case shall be shown on the NIS-2 Replyt it is the opinion of the Committee that, as Form documenting installation of the component; an alternati ve to the requirements of IWA-7210 (IWA-4170 in the 1991 Addenda through the 1995 Edition 'See the 1995 Edition or later IWA-9000 Glossary for definitions or IWA-4220 in the 1995 Addenda and later Editions of Owner's Requirements and Construction Code.

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