ML20087D412
| ML20087D412 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/08/1995 |
| From: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20087D414 | List: |
| References | |
| NUDOCS 9508100321 | |
| Download: ML20087D412 (10) | |
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Rostar E. DuroN Baltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Marytand 20657 410 586-2200 Ext.4455 local 410 260-4455 Baltimore August 8,1995 l
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U. S. Nuclear Regulatory Commission j
Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No.1; Docket No. 50-317 l
Supplemental Information; Request for Temporary Relief from ASME Boiler &
j E_rsssure Vessel Code Section XI Reauirement TAW-5250
REFERENCE:
Letter from Mr. R. E. Denton (BGE) to NRC Document Control Desk, dated March 23,1995, Request for Temporary Relief from ASME Boiler & Pressure Vessel Code Section XI Requirement IAW-5250 We are providing additional information to supplement our relief request (Reference). We have requested relief to delay the repair of a half-coupling located on the bottom of the common saltwater discharge header in the senice water pump room. As described in the referenced letter, repair of the half-coupling is impractical during plant operation. Therefore, we have proposed alternatives to the repair which would provide an acceptable level of quality and safety until the repair can be made. Those alternatives are described in the referenced letter.
The root cause of the leak will be determined when we remove the leaking half-coupling. Based on past experience, it appears that the leak may be due to corrosion at a point where the coal tar coating was insufficient. Therefore, there is no need for augmented inspections of other coupling locations.
We have not provided any leak mitigating measure, such as a clamp, based on the nature of the leak and the safety significance of the potential failure of the half-coupling. In addition, we have changed the schedule for ultrasonic examination from every six months to every three months.
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9500100321 950808 PDR ADOCK 05000317 il
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Document Control Desk July 00,1993 Page 2 Attached are the calculations described in our previous letter and additional information needed to assist the Staffs review of the code relief request. Should you have further questions regarding this nutter, we will bc pleased to discuss them with you.
Very truly yours, k
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Attachment:
As Stated cc:
D. A. Brune, Esquire J E. Silberg, Esquire L. B. Marsh, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R.1. McLean, DNR J. H. Walter, PSC i
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ATTACIIMENT SUPPLEMENTAL INFORMATION; REQUEST FOR TEMPORARY RELIEF, DATED MARCH 23, 1995 Saltwater Pine diameter = 30" nominal wall thickness =.375 inches at ends of T (middle oft is thicker) material = carbon steel - ASTM A-234, grade WPB lining = neoprene rubber (coal tar at the coupling threads)
Half Countine assumed opening = 1.75"(for 1" half coupling)
I enknoe Calculntion methodology - Crane Technical Paper 410 system pressure = design pressure = 50 psi (operating pressure at this location = 20 psi) temperature = 95'F fresh water assumed (less dense than saltwater)
Stress Annivsis methodology - ANSI B31,I credit taken for.25" cover fillet weld (conservative since a groove weld is also present) i linreinforced Onenine Evaluntinn methodology - ANSI B31,I required minimum wall thickness = 0.17"(introduced a 2.0 undertainty correction factor for calculation of A7 to account for UT measurement inaccuracy) service life = 13 months Non-Destructive Ernminntion ultrasonic examination methods used minimum measured wall thickness = 0.523" UT report and map attached
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.s EN-1-100 Revision 3 Engineering Service Process Overview.
Page 76 of 131 - -
ATTACHMENT 1, ENGINEERING SERVICE PACKAGE (ESP)
(Page 1 of 2) t Rev. No.:
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REASONS FOR ENGINEERING SERVICES REQUEST / PROPOSED CilANGES:
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SYSTEM ENGINEER:
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Assignment j
PROJECT MANAGER:
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O SPECIALTYINPtrr SCREEN (DS-020)
O NUC1 EAR SAFLTY S10NIFICANCE SCREEN (NS.2 101)
O ENVIRONMENTALIMPACT SCREEN PACKAGE (Check all that are completed)
O Configurution Document Change Evaluation O
Like-for Like Evaluation O
Modification Evaluation Ed Engineering Evaluation O
SSC Functional Evaluation O
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EN-1-100 Engin6: ring Service Process Overview _
Revision 3 Page 77 of131 1
ATTACHMENT 1, ENGINEERING SERVICE PACKAGE (ESP)
(Page 2 of 2)
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o Page -t of 7 Package (Continued):
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Analytical SoAware O
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O Design Instructions O
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Seismic Qualification Review Summary O
Electrical Device Setting Sheets O
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O Setpoint Change Transmittal Sheets O
Engineering Standard (ES)
O Specifications O
EnvironmentalImpact Statement O
Safety Parameters Display System (SPDS)
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ENGINEERING EVALUATION (Attachment 24) 1 ESP No.:
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0000 Page 3 of 7 REASONS FOR ENGINEERINc EVALUATION: PROVIDE TECl!NICAL JUSUFICATION FOR CONITNUED OPERATION OF TIIE UNIT 1 SALTWATER SYSTEM FOLIDWING TIIE DISCOVERY OF A TIIROUOlt WALL LEAK ON A 1" IIALF-COUPLINO IN TIIE SERVICEWATER ROOM. REFERENCE BGB CALCULATION CA00027 DESCR! MON OF Cl!ANCE(S): TIIIS EVALUATION PROVIDES TIIE DISPOSTI10N FOR ISSUE REPORT IR5028461 DETAILED EVALUATION OF CilANGE(S): CALCULABON CA00027 WAS PERFORMED TO DETERMINE DIE MAXIMUM l
FIDW BIROUOlt TlIE S ALTWATER SYSTEM IN TlIE EVENT TIIE LEAKING llALF-COUPUNO CATASTROPIIICALLY FAILED, AN OPENING EQUALTO Tile O.D. OF TIIE 1" IIALF-COUPUNO WAS ASSUMED TO BE 1.75" Wirit A MAXIMUM SALTWATER DESIGN PRESSURE AT TIIIS LOCATION OF 20 PSL SINCE Tile IIALF COUPUNO IS IDCATED ON Tile BOTTOM OF TIIE COMMON DISCI (ARGE PIPE IN Tile UNIT 1 SERVICE WATER ROOM TlIERE IS NO EFFECTIVE IDSS OF COOUNO WATER CAPACI1Y AS ARESULTOFTIIE LEAK. Tile SERVICE WATER ROOM IIAS BEEN ANALYZED FOR A FLOODING RATE OF 447 OPM BY TIIE FIDODING DESIGN OUIDEUNES MANUAL, DS-001. ANY FIDODING RATE LESS TIIAN 447 OPM IN Tile SERVICE WATER ROOM DOES NOT Cl!ALLENOE ANY OF TIIE SAFETY RELATED EQUIPMENT IN l
111E ROOM SUCII Til AT TIIE EQUIPMENT COULD DE PREVENTED FROM PERFORMING ITS S AFETY RELATED FUNCTION.
i SINCE Tile CALCULATED SALTWATER BLOWDOWN RATE IS SIGNIFICANTLY LEC TilAN 447 OPM, NO OPERABIIITY CONCERNS EXIST DUE TO POTENTIAL FLOODINO. AN UNREINFORCED OPENWO E VALUATION WAS PERFORMED AS PART OF CA00027, ASSUMING TIIE llALF-COUPUNO WAS COMPLETELY REMOVED. Tile METilODOLOGY DESCRIBED IN ANSIB31.1 WAS USED. TIIE RESULT OF Ti!IS EVALUATION DEMONSTRATED TIIAT SUFFICIENT REINFORCEMENT l
IS PROVIDED BY Tile EXCESS MATERIAL IN TIIE IIEADER Wall BASED ON TIIE MINIMUM READINO OF.523" DIE CALCULATED NUMBER OF MONTIIS UNTIL DIE UNREINFORCED OPENINO NO IDNGER MEETS Tile CODE l
REQUIREMENTS IS 13 MONrlIS. BASED ON Tile RECOMMENDATION CONTAINED IN NRC GENERIC LETTER 90-05 AN INSPECTION INTERVAL OF 3 MONrilS IS RECOMMENDED BY PDSU. FINALLY, Tite SEISMIC LOADS IN TIIE FIAWED WELD WERE EVALUATED. CREDIT WAS ONLY TAKEN FOR TI'E.25" COVER FILLET ON Ti!E IIALF-COUPUNO, TIUS IS EKrREMELY CONSERVATIVE SINCE A OROOVE WELD IS ALSO PRESENT. IT WAS DETERMINED TIIAT Ti!E WELD WAS LOADED TO LESS Til AN 5% OF TIIE ALIDWABLE. ALTi!OUGII Tile FLAW IN TIIE IIAIS COUPLINO CANNOT BE CllARACTERIZED, TilIS PROVIDES A LEVEL OF ASSURANCE TilAT CATASTROPillC WELD /f tALF-COUPUG FAILURE IS i
lilOllLY UNUKELY. IN
SUMMARY
PDSU CONSIDERS Ti!E SALTWATER llEADER TO DE OPERABLE. PURSUIT OF FORMAL SECTION XI CODE REUEF WITil Ti!E NRC IS IN PROGRESS, Ti(EREFORE, IN Tite INTERIM DECIARING Tite IIEADER INOPERAllII,IS NOT REQUIRED.
EN.I.100 Rev 3 ENOREVAL
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1 EN-1-100 Engineering Services Process Overview -
Revision 3 i
Page 91 of131 ATTACHMENT 6, ENGINEERING SERVICE INVENTORY TRANSMITTAL (Page 1 of 4)
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EN-1-100 Revision 3 Engineering Services Process Overview-s, Page 92 of131 --
ATTACIIMENT 6, ENGINEERING SERVICE INVENTORY TRANSMITTAL (Page 2 of 4)
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Revision 3 Engineering Services Process Overview Page 93 of131 ATTACHMENT 6, ENGINEERING SERVICE INVENTORY TRANSMITTAL (Page 3 of 4)
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