IR 05000358/1978019

IE Inspec Repts 50-358/78-19 on 780828-30 During Which No Items of Noncompliance Were Noted. Major Areas Inspected Incl:Examination of ISI Plan & Procedure for Presvc Inspec & Observation of NDE Activities

ML20148R053
Person / Time
Site:	Zimmer
Issue date:	09/26/1978
From:	Erb C, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20148R056	List: IR 05000358/1978019
References
50-358-78-19, NUDOCS 7811300221
Download: ML20148R053 (9)

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

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REGION III

Report No. 50-358/78-19 Docket No. 50-356 License No. CPPR-88 Licensee: Cincinnati Gas and Electric Company 138 East 4th Street Cincinnati, OH 45201 Facility Name: (lilliam H. Zimmer Nuclear Power Plant Inspection At: W . H. Zimme r S i te , Mo s c ow , OH Inspection Conducted: August 28-30. 1978

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Inspectors: ig C. M. Erb

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Approved By: Chief -

Engineering Support Section 2

1 Inspection Summary j Inspection on August 28-30, 1978 (Report No. 50-358/78-19)  ;

Areas Inspected

Examination of ISI plan and procedures for preservice i

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inspection; observation of NDE activities; qualification of personnel, I observation of welds and records, safety related components, exami-nation of records for RPV internals and safety related modification 'This inspection involved 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of inspection time by two NRC inspec- j tor l Results: No items of poucc.apliance ar deviations were identifie I

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I DETAILS Persons Contacted Cincinnati Cas and Electric Company (CG&E) ,

• B. Culver, Project Manager

• W. Schwiers, Principal QA and Standards Engineer

• R. L. Wood, QA and Standards Engineer

• J. F. Weissenberg, QA and Standards Engineer penere.1 Electric (CE)

, T. E. Bloom, Site Manager - NED ,

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Reactor Controls Inc. (RCI)

H. Ceane Project Manager R. Kananen, QA Supe rvisor Authorized Nuclear Inspector (ANI)

T. McCoy, Nuclear Energy Services, Inc. (NES)

R. A. Bott, NDE Supervisor M. Meenach, Level 11 UT Operator J. Robinson, Level II UT Operator ,

l Kaiser Engineers, Inc. (KEI) I T. Smith, Mechanical Inspector

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• Denotes those who attended the exit intervie Functional or Program Areas Inspected i

The functional and program areas inspected are identified in Sec tio l 1 and I l l

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SECTION I Prepared by K. D. Ward Reviewed by D. H. Danielson, Chief Er'6i neering Support Section 2

+ Review of Preservice Inspection (PSI) Program

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The inspector reviewed the following documents outlining the pre-service inspection requirements and determined the meet the require-ments of ASME Section III and XI, 1974 Edition with No Addend Preservice Inspection Program Plan, NES, No. 80All81, Re O, March 31, 1Ci Inservice Inspection Program Quality Assurance Manual, NES, No. 80A9021, Rev. 2, June 1, 197 Quality Assurance Plan for Inservice Inspection Program No. 80All80, Rev. O , July 20, 197 No items of noncompliance or deviations were identified .

26 Review of Preservice Inspection Procedures

The procedures applicable to the activity were reviewed and it was-determined that they meet the requirements of ASME Section III, V and XI, 1974 Edition with no Addenda, Ultrasonic Examination Procedure for Piping Butt Welds and Longitudinal Welds, No. 80All68, Rev. O, January 17, 197 Manual Ultrasonic Examination Procedure for Vessel Welds and Support Skirt Weld, No. 80All69, hev. O, January 19, 197 ,

' Automated Ultrasonic Examination Procedure for Reactor Pressure Vessel Welds , No. 80All?0, Rev. O, March 3,197 Ultrasonic Exauination Procedure for Closure Head Welds,

, No. 80All74, Rev. O, January 19, 197 ;

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e. Ultrasonic Examination Procedure for Vessel Flange Welds and l Ligaments, No. 80All72, Rev. O , February 2, 197 f. Ultrasonic Examination Procedure for Closure Head Nozzle Welds, No. 80A1173, Rev. O, January 23, 197 g. Automated Ultrasonic Examination Procedure for Reactor Vesoel Nozzle Welds , No. 80All74, Rev. O , February 15, 197 h. Ultrasonic Examination Procedure for Closure and Recirculation Pump and Valve Studs and Nuts, No. 80A1175, Rev. O, March 20, 197 i. Liquid Penetrant Examination Procedure, No. 80All78, Rev. O, Septembe r 22, 197 j. Visual Examination Procedure, No. 80All?9, Rev. O, December 19, 197 k. Remote Ultrasonic Examination Procedure for Reactor Vessel Nozzle Safe-end and Transition Wolds, No. 80All82, Rev. O, March 1, 197 . Mar.ual Ultrasonic Examination Procedure for Closure Head Nozzle to Flange Welds, No. 80All83, Rev. 0, February 15, 197 m. Ultrasonic Examination Procedure for RHR Heat Exchanger Welds, No. 80All85, Rev. O , February 15, 197 n. Grinding Procedure for Inservice Inspection (Inter-Office Memorandum from CG6E to KEI, doted April 1, '. 9 7 7 ) .

o. Inservice Inspection Data Control System No. 25-DC-001, Rev. 1, July 24, 197 p. Procedure for Certifying Visual Examination Personnel for Pre-Service /In-Service Examination, No. CVEP-PSIS, Rev. O, January 1, 197 q. Procedure for Certifying Penetrant Test Personnel, No. CPTP-1, Re v. 4, May 16 , 1969, r. Ultraaonic Instrument Linearity Verification, No. 25-PS-002, Rev. 2, October 19, 1975.

l s. Procedure for Certifying Ultrasonic Test Personne l, No. CUTP-1, Rev. 4, January 196 l l

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I There will be no magnetic particle, eddy current or radiographic examinations performed for preservice inspection No items of noncompliance or deviations were ide n t if ie d . I l

Observation of Work and Nondestructive Examination Activities

' The inspector observed the following nondestructive examinations  ;

being performed in accordance with ASME Section III, V and XI, 1974 Editio Ultrasonic examination of a 24" diameter, Main Steam line weld, No. IMS-OlBD-24. The instruments used were a Sonic MKI and a UJ Reflectoscope, Sperry. The transducers used were a 3/4" dia. 2.25 MHZ and a 1/2" x 1", 45 , 2.25 MHZ. The couplant used was Sonotrace and there were no recordable indications observe The radiographs of the above weld were re vie we d . The radi-ography was performed using IR 192. There were no unacceptable indications viewed in the radiograph The areas observed included, preparation, calibration, performance of the examination and the documentatio No items of noncompliance or deviations were identified in the ,

areas observe '

4. Data Review and Evaluation Review of PSI data and NDE reports for the Recirculation System, Feedwater System, RHR System, HPC System, LPC System, and MS System, demonstrated that the QA/QC commitments had been complied wit No items of noncompliance or deviations were identified abov . NDE Personnel Qualifications and Certifications Review The inspector reviewed the following NDE personnel qualifications and certifications in detail. The inspector determined that personnel were certified by Nuclear-Energy Services, Inc., in accordance with SNT-TC-1 Name Le ve l Methods F. Carr III MT-UT-PT R. Bott II UT-PT E. Anderson II UT-PT-HT-5-

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Name Level Methods C. Thompson II RT-UT-PT-MT M. Meenach II PT-UT D. Burrelli II PT-UT J. Robinson II UT M. Shallis II MT-PT A. Piersiak I UI-PT J. Bagley I UT G. Foster I UT-PT No items of noncompliance or deviations were identified abov . Review of Liquid Penetrant Material and Ultrasonic Couplant Certifications The inspector reviewed the following certification Liquid Penetrant Materials, Penetrant SKL-HF/S, Formula B, Developer SKD-S and Cleaner SKC-S, No. 10172 Ultrasonic couplants, Ultragel 11 and Sonotrace, No. 1117 No items of noncompliance or deviations were identifie . Independent Inspection Radiographs were reviewed for the following welds in accordance with ASME Section III and V, 1974 Edition with no Addend Spool Seam Diameter Thici: ness Date IRH01A18-37A A 18" 0.875 1/21/76 1RH01A18-37A B 18" 0.875 1/21/76 1RH01B18-34A A 18" 0.937 10/5/76 1RH01B18-34A B 18" 0.937 10/5/76 1RH01B18-35 A 18" 0.937 2/1/76 1RH01B18-35 B 18" 0.937 2/1/76 1RH01B18-35 C 18" 0.937 2/1/76 1Rh01B18-36 E 16" 0.937 3/30/76 1RH01B18-36 F 18" 0.931 3/30/76 No items of noncompliance or deviations were id e n t i f ie d .,

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SECTION 11 Prepared by C. !!. Erb Reviewed by D. H. Danielson, Chief Engineering Support Section 2 Safety Related Components - QA Record Review

. Welds to a 24 x 20 x 24 isolation valve were examined and found to be smooth and acceptable for preservice examination. This valve is in the Main Steam system and was fabricated by Rockwell Manuf acturing Company. The valve was built to the requirements of GE Specification 21A9257, Rev. 3 and the QCR for Valve S/N 160 indicated acceptable material certifications, nondestructive test results and performance tests. ASME Section III, 1971 Edition, no Addenda is applicable for this valv Welds to an 18" gate valve were inspected and found to have a ground surf ace suitable for preservice testing. This valve was manuf actured by Wm. Powell Company and is a reactor feed-water isolation valve. This valve was item 132, Tag. 1B21 F065A and material certifications were on file from Adirondack Steel Casting Company and Cameron Iron Works. The certificate of design and compliance were in the file. This valve is actuated by a Limitorque SMB, size 3, and the certificate of shop inspection was signed by a representative of Hartford Steam Boiler Insurance Compan Welds to a 20" motor operated discharge valve in the Recir-culation system were inspected and found to have a ground surface suitable for preservice examiration. This valve was ;

manufactered by Darling Valve Company and built to GE l Specification 21A9280, Rev. 3. Cas ting certifications were l in the file f rom Quaker Alloy Company for the body, bonne t l and disc. The GE Product Quality Checklist (PQC) listed acceptable performance tests and indicated source inspection j by the cus tome l I

No items of noncompliance or deviations were found in the above area ;

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2. Standby Liquid Control Storage Tank - QA Record Review QA documentation for this item was examined. This tank is nuclear Class 2 and was build by Lamco Industries to the requirements of ASME Section III, 1971 Edition with Winter 1973 Addendu Six non-conformances with acceptable replies were listed. Material certifica-tions and radiographic reader sheets to procedure 16 RT, Rev. 1, we re in packag A Hartford Steam Boiler and Insurance represent-ative had signed the certificate of shop inspectio No items of noncompliance or deviations were found in the docu-me n t a t ion .

i 3. Reactor Vessel Internals and Safe End Modification lent Pins Lower Core Plate Pins have been mechanically polished to remove traces of lead i contamination. Experiments have been performed to ascertain the allowable amount of straightening that can safely be performed. Straightening of the pins had not been performed at the conclusion of this inspectio Shroud Head and bteam Separator Assembly Work on this item will be performed under General Electric FDI 81/63000. Several areas of nonconformance were found when this item was inspected at the sit The area of nonconformance included arc strikes on the shroud head flange, undersized fillet weld on top of bolt lug and slag in a gusset weld between standpipes. All rework was outlined and exact location clearly shown on r5e paperwork covering the nonconformances, Scram Discharge Header - CRD System Several Class 2 socket welds in the area above the CRD modules were examined and found to be acceptable as to size and con-figuratio Radiography on a 8" scram discharge header butt veld, identification FWRD2, was examined. This carbon steel weld was made using an insert with GTAW and finish welded with SMAW. This weld showed some acceptable suckback in the root, and the film had been read by RCI, KEI, and the A . . . - . -. ._

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, Feedwater Nozzle Safe End Replacement Four original 12" feedwater saf e-ends were replaced. The neu safe ends utilize a tuning fork design with the thermal sleeve welded to a prong machined into the safe end. Inconel is a transition material between the nozzle and the carbon steel piping. Weld procedure WPSG 3.51N-75A-0014, Rev. 4, was used with the inconel specification SB-166, alloy 600. The daeumentation indicated this weld was made to ASME Section III, 1971 Edition, Summer 1973 Addenda and Code Case 1332-6. These welds are Class 1 and the hyrdo tes; was successfully performed in July 197 The radiographs were not available at the site for examination. This is on unresolved ite (358/78-19-01)

Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable i te ms , items of noncompliance, or deviations. Unresolved items disclosed during the inspection are discussed in Section II, Paragraph Exit Interview The inspectors met with site staf f representatives (denoted under Persons Contacted) at the conclusion of the inspection on August 30, 1978. The inspectors summarized the purpose and findings of the inspection. The licensee acknowledged the finding !

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