IR 05000440/1985051

Insp Rept 50-440/85-51 on 850807-09.No Violations Identified.Major Areas Inspected:Licensee Action on Previously Identified Items Including RCPB Piping & Reactor Coolant Loop Piping Welds

ML20137G140
Person / Time
Site:	Perry
Issue date:	08/22/1985
From:	Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20137G120	List: IR 05000440/1985051 ML20137G114
References
50-440-85-51, NUDOCS 8508270186
Download: ML20137G140 (8)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-440/85051(DRS)

Docket No. 50-440 License No. CPPR-148 Licensee: Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, OH 44101 Facility Name: Perry Nuclear Power Plant, Unit 1 Inspection At: Perry Site, Perry, OH Inspection Conducted: August 7 - 9, 1985 bytti W Inspector:/AX. D. Ward ff2kW 4 Date

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Approved By: D. H. Danielson, Chief //22/E Materials and Processes Section Date Inspection Summary Inspection on August 7 - 9, 1985 (Report No. 50-440/85051(DRS))

Areas Inspected: Unannounced, routine safety inspection to review actions on a previous inspection finding; work activities on reactor coolant pressure boundary piping; visual examination (VT) of reactor coolant loop piping welds; and review radiographs and reports on piping welds. The inspection involved a total of 21 inspector-hours by one NRC inspector including 4 inspector-hours during off-shift Results: No violations or deviations were identifie PDR ADOCK 05000440 0 PDR

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DETAILS 1. Persons Contacted Cleveland Electric Illuminating Company (CEI)

• C. Shuster, Manager

• H. Walls, Senior NDE Administrator

• J. Bellack, General Supervisor Engineer

• Ferrell, Licensing Engineer D. Kissig, NDE Technician Raymond Kaiser Engineers (RKE)

• C. Thompson, Technical Aid J. Bowser, NDE Level II J. Ewing, NDE Technician The inspector also contacted and interviewed other licensee and *

contractor employee * Denotes those present at the exit meetin . Licensee Action on Previous Inspection Findings (Closed) Open item (440/85022-39): Determine that preservice and inservice inspection program are in accordance with SSER 5, Section 5.2.5 and 6. The NRC inspector reviewed the PSI program and determined that the program was in accordance with SSER 5, Section 5.2.5 and 6.6.3. The licensee still is in the process of developing portions of the ISI

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progra The scope of the examinations, procedures, and acceptance criteria meet the requirements of the 1977 ASME Code Section XI with Addenda through Summer 1978. The extent of examination was determined by the requirements of the 1974 ASME Code Section XI with Addenda through Summer 197 Approximately 99% of the required PSI examinations have been completed on the RHR, HPCS, LPCS, and the RR system To ensure that no deleterious defects develop during service, in ASME Code Class 2 system, 100% of the welds and weld-heat-affected zones I

will be examined before plant startup and periodically throughout the

, life of the plan In addition, Code Class 2 and 3 systems receive

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visual examinations; the systems are pressurized in order to detect leakage, signs of mechanical or structural distress, and corrosio J

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The licensee stated that the ISI program will comply with the rules published in 10 CFR 50.55a. The design of the reactor coolant system incorporates provisions for access for ISI, in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (1977 Edition, including the Summer 1978 Addenda). Suitable equipment has been developed and has been installed to facilitate the remote examination of these areas of the reactor coolant pressure boundary (RCPB) that are not readily accessible to inspection personne In the site Safety Evaluation Report, Supplement No. 5, Section 5.2.5.2, the NRC requested responses from the licensee on four items. The NRC inspector reviewed documentation relating to the following responses dated June 3, 1985, and found them to be acceptable: Address the degree of compliance with R.G. 1.15 Response PNPP conforms to the alternative method presented in Appendix A to R.G. 1.150, Revision 1. Details were provided in NES Document No. 85A267, Revision 0. The NRC inspector reviewed this document and had no questions, Revise the main steam system section of the PSI program to delete reference to the exclusion diameter of up to 4.72 in I.D. for steam service based on normal makeup for Class 1 system Response A controlled copy of the revised PSI program plan for the Main Steam System (NES Document No. 80A4427, Revision 3) was reviewed and the NRC inspector had no questions, Address the ultrasonic examination of welds with corrosion-resistant claddin Response The report entitled, " Baseline Examination of Reactor Recirculation System Corrosion Resistant Clad (CRC) Welds," addresses this ite The NRC inspector reviewed this document and had no questions, Submit all relief requests with a supporting technical justificatio Response The relief requests reviewed by the NRC inspector, comprised all the relief requests anticipated by the licensee. The inspector had no questions as a result of the revie The NRC inspector agreed with the licensee's actions and considers this item closed.

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3. Reactor Coolant Loop Piping - Visual Examination of Welds Most of the field welds in the reactor coolant loop piping system are covered with insulation. The NRC inspector visually examined the following welds for size, shape, surface finish, appearance, etc., and determined that the welds conform to applicable codes, standards, specifications and welding procedure requirement Weld N System Weld N System 0029 RHR Loop A 0056 RCIC 0034 RHR Loop A 0057 RCIC 0030 RHR Loop A 0058 RCIC 0108A RHR Loop A 0059 RCIC 0040 RHR Loop A 0075 RCIC 0039 RHR Loop A 0076 RCIC 0038 RHR Loop A 0076A RCIC 0077 RCIC The NRC inspector also reviewed quality records on the following welds including weld rod slips, NDE reports and field weld process sheets:

Weld N System Weld N System 10 RHR 37 RHR 38 RHR 05 RHR 09 RHR 01 RHR 02 RHR 03 RHR 04 RHR 06 RHR 07 RHR 08 RHR The NRC inspector determined that the specified inspections were completed, weld history records were satisfactory and that the records reflected adequate weld qualit No violations or deviations were identifie . Reactor Coolant Pressure Boundary Piping - Work Activities The NRC inspector reviewed pipe spools on ISO 1-E51-5, visually examined the spools and determined that applicable procedures including specified materials and qualified inspection personnel were utilize The NRC inspector located selected components in the RCIC System (auxiliary building), and determined that the piping runs were installed as required by applicable specifications.

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The NkC inspector compared piping drawings with actual Reactor Coolant

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Loop installations and found them to be acceptable.

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The NRC inspector also reviewed installation records of several pipe spools and determined that the required scope of the inspection was performed and that recorded data and records confirm that specification and installation procedures were me No violations or deviations were identifie . Review of Radiographs The NRC inspector reviewed radiographs and reports of selected field welds. These welds are required to conform to ASME Section III, 1974 Edition, Winter 1975 Addenda. The following welds were radiographed by Pullman Power Products and found to be acceptable:

System Weld N Diameter Thickness Date RT 1-E12-24-RHR FWO6 12" 0.687" 07/15/81

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FW05 0.812" 06/22/81

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FWO2

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0.749" 02/03/82

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FW01 0.531" 02/09/81

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FWO7 0.812" 01/07/81 1-B21-MS FW17 26" 1.581" 04/04/82

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FWO8 28" 2.352" 01/22/82

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FW01 4" 0.405" 02/05/84

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FWO9 28" 2.352" 02/10/82 1-C41-SLC FW44 1" 0.343" 09/06/83

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FW32 12"x3" 0.688" 10/11/82 1-C11-CRD FWO4 8" 0.655" 11/30/82

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FWO2 8" 0.655" 11/18/82

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FWO4 8" 0.593" 12/15/82

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FW13 8" 0.655" 12/02/82

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FW01 8" 0.655" 12/12/82 1-E12-29-RHR FWO9 20" 1.248" 08/18/81

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FW10 1.342" 10/23/82

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FWO8 1.248" 08/18/81

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FWO6 1.248" 08/20/81

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FWO4 12" 0.813" 12/29/80

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FWO3 0.813" 10/17/80

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FWO2 0.790" 11/11/80

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FW01 0.705" 05/02/82

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1-E12-42-RHR FW01 0.812" 04/10/81

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FWO7 0.812" 02/05/81 1-E21-1-LPCS FWO2 12" 0.749" 03/12/83

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FWO3 0.747" 01/29/83

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1-E12-42-RHR FW05 0.749" 04/02/83

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1-E21-1-LPCS FWO6 0.749" 04/02/83

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FW24 0.749" 03/07/83

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FW01 0.749" 07/15/81

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1-E21-2-LPCS FWO4 0.812" 07/13/81

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FW18 0.812" 09/23/81

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l FWO3 0.812" 09/23/81 l

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System Weld N Diameter Thickness Date RT

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FWO2 0.725" 03/19/81

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FW01 0.749" 11/04/81

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1-E21-7-LPCS FW10 0.812" 01/06/81

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1-E22-3-HPCS FW02 0.749" 07/12/83

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FWO3 0.843" 08/26/81

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FWO5 0.749" 02/25/83

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FW38 0.749" 04/09/83

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FWO7 0.749" 06/08/84

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FW31 0.812" 06/26/81

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1-E22-4-HPCS FWO9 0.719" 09/21/81

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FW33 0.843" 09/11/81 1-E51-9-RCIC FWO3 6" 0.494" 01/14/83

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FWO2 0.494" 01/14/83

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FW01 0.463" 09/11/82 1-E21-1-LPCS FWO4 12" 0.812" 07/23/81

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FWO5 12" 0.749" 03/30/83 1-E22-3-HPCS FW10 12" 0.812" 07/10/81

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FWO9 0.812" 07/10/81

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FWO6 0.749" 04/10/81

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FWO4 0.743" 01/28/83 1-E51-2-RCIC FWO7 6" 0.494" 06/22/84

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FWO9 6" 0.498" 10/03/81

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FWO4 0.494" 01/06/82

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FWO3 0.494" 06/06/83 1-G33-3-RWCU FW10 4" 0.450" 02/08/81

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FWO8 0.399" 04/13/81

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FWO7 0.337" 07/05/84

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FWO6 0.400" 03/19/81 1-N27-3-FW FW14 20" 1.156" 10/08/80

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FW71 12" 0.749" 02/18/82 1-N27-4-FW FW16 12" 0.749" 01/28/82

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FW17 0.718" 02/02/82

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1-E12-36-RHR FWO8 0.812" 04/06/81

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FWO9 0.800" 03/19/81

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FW11 0.747" 01/29/83

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FW13 0.812" 05/07/81

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1-E12-41-RHR FW38 0.812" 09/18/81

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FWO9 0.749" 09/14/81

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1-E12-42-RHR FWO2 0.749" 02/17/83

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1-E12-41-RHR FW37 0.718" 08/12/81

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FW10 0.875" 11/04/80

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1-E12-42-RHR FWO3 0.749" 03/03/83

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FW17 0.749" 03/03/83 The above F' ullman Power Products (PPP) welds and all the other PPP welds onsite were reviewed 100% by the following individuals:

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PPP - Level II and/or III ANI

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CEI - Level II and/or III The NRC inspector reviewed radiographs and reports of selected field welds. These welds were required to conform to ASME Section III, 1974 Edition, Winter 1975 Addenda. The following welds were radiographed by Magnaflux Quality Services and found to be acceptable:

System Weld N Diameter Thickness Date RT 1-833-RR TWA18 12" 0.626"-0.750" 09/14/82

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FWA2 22" 1.125" 03/02/81

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FWB8 24" 1.500" 12/19/80

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FWB17 12"

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0.626"-0.750" 03/05/83

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FWB12 0.626" 02/14/84 FWB10 24" 1.500" 07/06/81

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FWB8 1.500" 07/02/81 FWB5 22" 1.500"-1.375" 12/01/80

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FWB1 1.250" 01/20/83 1-B21-MS FWA4 26" 1.500" 09/05/82

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FWA5 1.196" 01/20/83

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FWA7 1.500" 09/08/82 1-B33-RR FWA1 22" 1.375" 10/15/82

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FWA3 1.500" 07/02/81 1-833-RR FWA5 22" 1.500"-1.375" 12/01/80

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FWA12 12" 0.625"-0.750" 08/04/81

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FWA13

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02/13/81

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FWA14

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07/03/82 FW19 05/29/82 1-B21-MS

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FWC4 , 26" 1.500" 02/06/82

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FWC5 1.196" 01/30/83

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FWC7 1.500" 11/22/81

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FWD 4 1.196" 01/08/83

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FWD 5

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01/08/83

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FWD 7 1.500" 11/14/81

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FWB4 1.196" 03/27/83

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FWB5

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08/21/82 FWB7 1.500" 11/15/81 The above General Electric (GE) welds and all the other GE welds onsite were reviewed 100% by the following individuals:

Magnaflux - Level II (Company that performed the RT)

Magnaflux - Level III

GE - Level III ANI

GEI - Level II and/or III No violations or deviations were identifie <

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6. Exit Interview

! The inspector met with site representatives (denoted in Persons Contacted paragraph) at the conclusion of the inspection. The inspectors summarized the scope and findings of the inspection noted in this report. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietar ,

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