ML20081C038

Final Deficiency Rept DER 83-32 Re Socket Welds in Steam Generator Process Piping in Violation of Requirements. Initially Reported on 830525.Condition Determined Not Reportable Per 10CFR50.55(e)

ML20081C038
Person / Time
Site:	Palo Verde
Issue date:	02/29/1984
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
ANPP-28935-BSK, DER-83-32, NUDOCS 8403120113
Download: ML20081C038 (5)

Text

s Arizona Public Service Company P O BOX 21666 e PHOENIX. AFUZONA 85036 February 29, 1984 ANPP-23935 -BSK/TkB U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director Division of Resident Reactor Projects and Engineering Programs

Subject:

Final Report - DER 83-32 A 50.55(e) Reportable Condition Relating to Socket Welds In Unit 1 Steam Generator Process Piping Are In Violation of Requirements File: 84-019-026; D.4.33.2

Reference:

A) Telephone Conversation between T. Yourg and R. Tucker on

!!ay 25, 1983.

B) ANPP-24171, dated June 24, 1983 (Interim Report)

C) ANPP-27522, dated August 5, 1983 (Time Extension)

D) ANPP-28094, dated October 26, 1983 (Time Extension)

E) ANPP-28392, dated December 8,1983 (Time Extension)

F) ANPP-28582, dated January 9, 1984 (Time Extension)

Dear Sir:

Attached is our final written report of the deficiency referenced above, which has been determined to be Not Reportable under the requirements of 10CFR50.55(e).

Very truly yours, N hm cAum rq E. E. Van Brunt, Jr.

APS Vice President, Nuclear ANPD Project Director EEVB/TRB:pt Attaciments q gg cc: See Page Two

!.E 21:M 9- Eni G5 8403120113 840229 PDR ADOCK 05000528 LL S PDR g3Ag33.; ~

/6-27 1 1l

Mr. T. W. . Bishop DER 83a32 Page Two cci- ,

Richard DeYoung, Director . ,

Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. C. Woods, Jr.

W. E. Ide +

D. B. Fasnacht A.' C. Rogers B.'S, Kaplan L. A. Souza J. Vorees J. R. Bynum P. P. Klute A. C. Gehr M. J. Stubblefield W. C. Bingham R. L. Patterson R. W. Welcher ,

H. D. Foster D. R. Hawkinson L. E. Vorderbrueggen G. A. Florelli S. R. Frost J. Self D. Canady Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 "

Atlanta, CA.30339

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FINAL REPORT - DER 83-32 DEFICIENCY EVALUATION 50.55(e)

ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNITS 1 I. DESCRIPTION OF DEFICIENCY Specification 13-PM-204, Revision 11, Paragraph 5.8.5 prohibits dissimilar metal socket weld connections in P8 to P1, P8 to P4 or P8 to P5 materials in ASME III Class 2 and 3 process piping when the operating temperature is 250*F or greater. During preparation for installation of Unit 2 valves 2PSGEV026 and 2PSGEV032, Field Engineering determined that the above requirements would be violated. :An inspection of Unit 1 revealed that valves IPSGEV026 and IPSCEV032 had already been installed in violation of this requirement. Field Engineering issued a Field Change Request to correct this condition, and APS Quality Assurance subsequently issued APS CAR C83-72N to document this ccndition as a noncompliance.

The subject valves, located in the Steam Generator Wet Layup

-Recirculation lines (in containment), are Kerotest Model 329 2" globe stainless steel. (P8 material) valves socket welded to 2" diameter carbon steel (P1 material) and alloy steel (P5 material) process piping. They are closed during normal plant operation, isolating the Quality Class S, Seismic Category 'III Wet Layup Recirculation pumps from the high temperature and pressures of the Steam Generator blowdown lines (oce valve and pump per blowdown line, i.e., per Steam Generator). These valves are otherwise used in conjunction with the Wet Layup Recirculation pumps to perform the following functions: 1) to furnish a continuous flow of water through the Steam Generators during shutdown periods; 2) to add chemicals during wet layup; 3) to assist in draining the Steam Generators.

The subject condition is attributed to a failere to make the necessary changes in design drawings subsequent to agreement be tween Bechtel and Kerotest-to substitute stainless steel valves for the originally specified Kerotest Model 327 alloy steel valves.

Kerotest failed to qualify the seat veld for the Model 327 alloy steel valves and requested to supply stainless steel valves as a substitute. Bechtel Engineering authorized the substitution of stainless steel valves and, to comply with dissimilar metal socket weld requrlements, indicated that the necessary transition pieces would be provided by Bechtel. This valve substitution was subsequently incorporated in the Material Requisition for

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Speci!Ication 13-PM-221C (Revision 4, issued 1/6/82) and the Valve

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Designation List (Revision 6, issued 3/29/82). However, the related piping f racetric drawings, which are used by Construction, were never revised to show the required transition pieces or that the valves were stainless steel.

Report No. 83-32 Page Two II. ANALYSIS OF SAFETY IMPLICATIONS The subject valves are approximately 3'-9" f rom the Steam Generator blowdown lines (located between the Steam Generator 31owdown lines and the Wet Layup Recirculation pumps) and will thus be subjected to temperatures exceeding 250*F during normal operation. The socket welds could therefore potentially fail due te the difference in thermal expansion and contraction of the dissimilar metals.

Consequently, a pipe break at the valve could occur. However, an engineering evaluation, as documented by calculation 13-NC-PB-010 of this postulated pipe break (i.e., in the Wet Layup Recirculation line, a 2" diameter high energy line) has shown that no mechanistic (pipe break or jet impingement) problems would result nor would the operation of the steam generators be impaired. Though water would accumulate in the Containment sump and Containment environmental conditions (temperature and humidity) would change, these conditions result in no adverse safety implications. The function of the Wet Layup Recirculation pump would also be precluded; however, the functions of the pump (a Quality Class S, Seismic Category III component) are maintenance type operations not required for performing safe shutdown or for maintaining safe shutdown conditions. This postulated pipe break can further be isolated from the Steam Generator by closing the motor operated blowdown valve.

Though this would require termination fo the Steam Generator blowdown line, the blowdown line is not safety-related. Thus, if left uncorrected, the subject condition would not adversely affect the safety of operations of the plant during the lifetime of the plant; consequently, this condition is evaluated as not reportable under the requirements of 10CFR50.55(e).

III. _ CORRECTIVE ACTION A. Field Change Requests (FCRs) 59,606-P have been issued ar.d approved by Engineering to install the necessary transition pieces for valves. SGEV026 and V032, respectively, for Units 1, 2 and 3.

B. Drawing Change Notice (DCN) 13 has been issued against Bechtel

-Drawing 13-P-SGF-122 (for valve V026) and DCN 18 has been issued against Bechtel Drawing 13-P-SGF-140 (for valve V032) to show the conforming configurations and material transitions for the 2" Steam Generator Wet Layup Recirculation lines.

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Report No. 83-32 Page Three III. CORRECTIVE ACTION (cont'd)

C. Bechtel Engineering has performed a review of all SDDRs against the following valve purchase order specifications. This review included 333 SDDRs and represents a comprehensive review of all suppliers who could possibly have submitted a material substitiution request fo the type identified by this DER.

13-JM-605 13-PM-403B 13-JM-600 13-PM-403C 13-JM-601A 13-PM-222B 13-JM-601B 13-PM-222C 13-JM-603 13-PM-224 13-JM-604 13-PM-231 13-JM-705 13-PM-242 13-JM-691 13-PM-221A i 13-JM-698 13-PM-221B 13-JM-696. 13-PM-221C 13-JM-710A 13-EM-222A 13-JH-710B The results of the review determined that six (6) SDDRs dealt with material substitutions and are listed below:

Specification No. SDDR No.

13-FM-403C 1921 13-FM-242 2705 13-PN-242 1793 13-JM-604 717 13-JM-705 2727 13-JM-705J 2728 Based on the review of the above SDDRs against the associated specification purchase order, it has been determined that none of the SDDRs were related to the dissimilar metal weld problem and that this. condition is verified as an isolated case.

D. In addition, 60 randomly selected SDDRs issued against (13-PM-XXX identit.ied) specifications were selected and reviewed to deterwine if any changes to Bechtel specifications or drawings were required and if the changes were implemented. The review-indicated that 8. specification changes and 1 drawing change was required and that the changes were completed as committed by the engineering disposition.

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