ML20044F154

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LER 93-007-00:on 930423,discoverd That Original Piping Did Not Conform to Design Code Requirement.Caused by Design Deficiency.Headers Fitted W/Code Approved End Caps & Tested & Now Conform to Design requirements.W/930521 Ltr
ML20044F154
Person / Time
Site: Beaver Valley
Issue date: 05/21/1993
From: Freeland L
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-007-01, LER-93-7-1, ND3MNO-3456, NUDOCS 9305260504
Download: ML20044F154 (7)
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i I ik 7T j 4b  ! Telephone (412) 393 EK10 Noctear Group f P O Don 4  ; Stuppsr.gport. PA 15077-(KkW t f i May 21,1993 'l ND3MNO:3456  ! Beaver Valley Power Station, Unit No.1 l Docket No. 50-334, Licensee No. DPR-66  ! LER 93-007-00  ! United States Nuclear Regulatory Commission  : Document Control Desk .; Washington, DC 20555  ! i I Li Gentlemen: l 5 In accordance with Appendix A,. Beaver Valley Technical Specifications, the '! following Licensee Event Report is submitted: j 

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LER 93-007-00,10 CFR 50.73.a.2.ii.B, " Condition Outside Design Basis -  ! Original Piping Did Not Conform to Design Code."  ! 

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h @ L. R. Freeland - -l General Manager l Nuclear Operations  ! DJM/sl f I Attachment  : 

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PDR ADOCK 05000344' s pon i 

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i . s May 21,1993 , ND3MNO:3456 Page 2 i cc: Mr. T. T. Martin, Regional Administrator United States Nuclear Regulatory Commission , Region 1 , 475 Allendale Road King of Prussia, PA 19406 Mr. G. E. Edison, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 i Larry Rossbach, Nuclear Regulatory Commission, BVPS Senior Resident Inspector J. A. Holtz, Ohio Edison , 76 S. Main Street Akron, OH 44308 h Larry Beck Centerior Energy 6200 Oak Tree Blvd. , Independence, OH 44101-4661 a INPO Records Center . 700 Galleria Parkway Atlanta, GA 30339-5957 Mr. Robert Barkanic Department of Environmental Resources P.O. Box 2063 16th Floor, Fulton Building - Harrisburg, PA 17120 Director, Safety Evaluation & Control Virginia Electric & Power Co.  : P.O. Box 26666 One James River Plaza  ; Richmond, VA 232.61  ! W. Hartley 4 Virginia Power Company l 5000 Dominion Blvd.  ! 2SW Glenn Allen, VA 23060 , i r L 

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May 21,1993 ]  ; ND3MNO:3456 Page 3 i J. M. Riddle Halliburton NUS  : Foster Plaza 7  ! 661 Anderson Drive i Pittsburgh, PA 15220 -l Bill Wegner, Consultant  ; 23 Woodlawn Terrace l Fredricksburg, VA 22405 i 

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1 l 4 NRC FORY 366 U.S. NUCLEAR REGULATORY COfsirAISSION APPROVED BY OfAB NO. 3150-0104 Np EXPIRES 5/31/95 E STiMATED BTHDEN MA DESPOMT TO COUR V W.T H T43 NrORMA*10N COLLE CTrON RE QUE ET 50 0 hrs ronwArts

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AND nEcoADS MANAGEVENT BRANCH [MNHB mdh O $_ NJCQ AR 4EGULATOW CoVMSSICM A ATMNGTC% DC 20'.% Ixm AND 10 THE F APERNDRK HiDUCTICN PRD.lf CT Q @ CEA, OffCE t 03 , (See reverse for requ red number of cgrts; characters for each block) MANAGEVE NT AND BJDGET. W'amNGTON. fr PE3 t i Actun Naut m DDCKE I NUMBE R p) PAGE p) i 1 OF Beaver Valley Power Station Unit 1 05000 334 03 TITLt (4p Condition Outside Design Basis-Original Piping Did Not Conform to Design Code EVENT DATE (5) LER NUPABER (6 REPORT NUfABER (7) OTHER F ACILITIES INVOLVED (8) stoJm.AL ni essoN 

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MODE (9) 6 20 402ib) 20 405 tc) 50 73(aH2)0v) 73 71(b) POWER 20 405(a't1)h) 50.3SicH1) 50.73(a H2Hv) 73.71(c) LEVEL (10) 0 20 405taH1H,o 50 36(cH2) . 50 73taH2)tvni oTHER  ; 20 405;a H1 Hun 50 73(aH2H.; 50 73saH2)(em)(A) wcw en Absnan  ; om anc m Tee, tac 20 405(aH1)D<> X 50.73(aH2 ion 50 73:aH2 Hem >(ei r ,.n 3sy 

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LICENSEE CONTACT FOR THIS LER (12) Nun namust Naumo.- u.. um , L R. Freeland, Ganeral Manager Nuclear Operations 41 2 64 3-1258 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) I " cas e, cce rwm . T unor Ac,unt a "$ c.AurE svsiru CcanoNENT VANur AcTu% , B BS XXXX XXXX N I SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED M^* * "^" yt s SUBMISSION 

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ABSTRACT (Lmt to 1400 spaces. i e., appfcomatey 15 singte-spaced typewr:t en hnes) (16) On 4/23/93, the plant was in a shutdown condition, Mode 6 (Refueling). During corrective maintenance on piping associated . with the Reactor Plant Component Cooling Water System (CCR) Heat Exchangers, it was discovered that the original design and , fabrication of the piping did not meet design code requirements applicable to the construction of Unit 1 (ANSI B31.1). The installed end plates on three piping headers did not have adequate thickness. When it was determined that these headers , did not meet design code, an engineering evaluation was , performed based on plant conditions (Refueling, Mode 6). This ' evaluation concluded that the headers would maintain system integrity. Since the piping did not meet design code, this  ; event is being reported as a condition outside design basis. wc m n en

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  • 1 REQUIRED NUMBER OF DIGITS / CHARACTERS j
FOR E.ACH BLOCK l t

BLOCK NUMBER OF ITLE NUMBER DIGITS / CHARACTERS , 1 UP TO AS FACiUTY NAME  ! i 2 DOCKET NUMBER 3 IN ADDITION O 05000 3 VARIES PAGE NUMBER 4 UP TO 76 TITLE 6 TOTAL M DATE 2 PER BLOCK 7 TOTAL y 2 FOR YEAR LER NUMBER  ; 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMEER  ; 61OT AL 7 REPORT DATE . 2 PER BLOCK UP TO 18 - FACILITY NAME 8 8 TOTAL - DOCKET NUMBER 

                                                            ^                           I 3 IN ADDITION TO 05000 9                  1                    OPERATING MODE 10                 3                     POWER LEVEL                                ,
    "    CHECK BOX THAT APPLIES EOGREtAEMS OF 10 UR                      i 12                                       LICENSEE CONTACT 14 FOR TELEPHONE                                                           g CAUSE VARIES                                                            ;

2 FOR SYSTEM l 13 4 FOR CCMPONENT EACH COMPONENT FAILURE  ; 4 FOR MANUFACTURER ' NPRDS VARIES 

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              .                                                                                                                                  l NQC f ORM 366A                              U.S. NUCLEAR REGULATORY COMMISSION              APPROVED BY OMB NO. 3150-0104                    ,

e to EXPlRES 5/31/95 [ ES'lVA'ED BsRDEN PER SESPONSE TO CDuriv W'N TH.S > LICENSEE EVENT REPORT (LER) SEES $',52RE"EuS oZ"Ms l TEXT CONTINUATION lEjM'e"J' '3"fa!7s ",7$ i ",d'A$'e,"M l THE FAPERWORK RED;CTION PrCJECT PS0104u OFFCE 08 > MANA3EME A" AND BJDGET. E ASHINGTON, DC 2:E:3 i ACILITY NAME ft) DOCAE~f NUMBER (2) 11H NUMBE R lt) j PAGEg3) > 

                                                                                         ,          u am ,A.         < w as NJVBE A         NUMBER 05000                                                               or       l Beaver Va!!ey Power Station Unit 1                                   334       '

93 - 007- 00 02 03 na o, m., ,&.=. v.v.w. mw. n, e umor, xm o n I DESCRIPTION OF EVENT On 4/23/93, with the plant shutdown for the ninth refueling l outage, a design deficiency was discovered on the 30 inch outlet i header on the Reactor Plant River System (RW) side of the  ; Reactor Plant Component Cooling Waters System (CCR) Heat Exchangers. During fabrication of a replacement header which 1 was to be a duplicate of the in-service header, it was  ! discovered that the installed 0.5 inch thick end plates did not have adequate thickness. The design code applicable to Unit 1, i ANSI B31.1 (1967,S71), required the end plate to be 1.26 inches ' thick. When it was determined that this header did not meet - design code, an inspection of similarly constructed piping headers was performed. This inspection revealed that the RW  ; inlet header and one end of the CCR outlet header were also constructed of 0.5 inch plate and did not meet the ANSI B31.1  ! code requirements. The CCR and RW systems are required to provide cooling for the Residual Heat Removal System and Fuel Pool heat exchangers during refueling operations. Since refueling was in progress at , the time of discovery, an engineering analysis was performed. It was determined that although the as-built conditions did not . neet ANSI B31.1 design requirements, the headers would maintain  ! system integrity and accomplish these functions. In order to correct the code non-conformance, new end caps were fabricated and installed. CAUSE OF EVENT  ! The cause of this event is categorized as an original design l deficiency. l CORRECTIVE ACTIONS i The affected headers were fitted with code approved end caps, pressure tested, and now conform to design requirements. , i  ! 1 s b E N Mkik kNb

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NUMBER NJMFIER 05000 oF Beaver Valley Power Station Unit 1 334 93 - 007- 00 03 03 , TtKT fn moe spe:e a repen .ne enatorm copes of N% Fan 3F1A> (171 s REPORTABILITY ' h' This event is being reported as a condition outside the design basis of the plant in accordance with 10CFR50.73.a.2.ii.B. f i SAFETY IMPLICATIONS  : t i There were minimal safety implications due to this event. It was determined through analysis that the involved systems would  ! be able to maintain system integrity during the current plant  : conditions. In addition, the affected headers had been in i service since 1976 with no indication of end plate leakage or i deformation. Both of the involved systems, CCR and RW, passed , original installation pressure testing, and also passed [ inservice inspection Technical Specification surveillance requirements during plant operation. 6 i SIMILAR EVENTS Review of station documents showed no similar reportable events  ! involving piping thickness deficiencies caused by improper l design specification.  ; r i h ( i f 

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