IR 05000306/1989010

Insp Rept 50-306/89-10 on 890403-06 & 24.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp Activities,Including Review of Program,Procedures, Observation of Work Activities & Data Review

ML20246C851
Person / Time
Site:	Prairie Island
Issue date:	05/01/1989
From:	Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20246C845	List: IR 05000306/1989010 ML20246C842
References
50-306-89-10, NUDOCS 8905100048
Download: ML20246C851 (4)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-306/89010(DRS)

Docket No. 50-306 License No. DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 j Facility Name: Prairie Island Nuclear Generating Plant, Unit 2 Inspection At: Prairie Island Site, Red Wing, Minnesota Inspection Conducted: April 3-6, and 24, 1989 Inspector: .' . f f/87 Date a%

Approved By: D. H. Danielson, Chief 6b/8f Materials and Processes Section Date Inspection Summary Inspection on April 3-6, and 24, 1989 (Report No. 50-306/89010(DRS))

Areas Inspected: Routine, unannounced safety inspection of inservice inspection (ISI) activities including review of program (73051), procedures (73052), observation of work activities (73753), and data review (73755).

Results: No violations or deviations were identified. Based on the results of the inspection, the NRC inspector noted the following strengths:

The implementation of the ISI followed the requirements of ASME Section XI and the licensee's progra NSP has established an excellent program for tracking and scheduling l required ISI examination The staff of both the licensee and ISI contractor groups were knowledgeable and competen In general, the inspection results indicate a continuing good

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DETAILS Persons Contacted Northern States Power Company (NSP)

• E. Watzl,' Plant Manager

~*L. Dahlman, Senior Materials and Special Processes Specialist

• J. Levelle, Senior Nuclear Safety and Technical Services Engineer

• A. Hunstad, Staff Engineer S. Redner, Materials and Special Processes Specialist Nuclear Regulatory Commission (NRC)

J. Hard, Senior Resident Inspector

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T. O'Connor, Resident Inspector Lambert, MacGill, Thomas, Inc. (LMT)

D. MacGill, Level III-Conam Inspection (Conam)

J. Sordini, Level II Westinghouse Electric Corporation (WEC)

R. Vollmer, Level III Hartford Steam Boiler Inspection and Insurance Company (HSB)

P. Fisher, ANII Supervisor The NRC Inspector also contacted and interviewed other licensee and contractor employee * Denotes those individuals present at the exit interview April 24, 198 . Inservice Inspection (ISI) Review-of Program (73051)

The NRC inspector verified that the licensee's ISI program was complete and conformed to regulatory requirements and to the licensee's commit-ments. The program was in accordance with ASME Section XI, 1989 Edition, Winter 1981 Addenda. There was sufficient organizational staff to ensure that acceptable ISI work was performed. Where ASME requirements were determined to be impractical, specific. relief from NRR was requested in writing. The NRC inspector reviewed specific relief requests and related documentation. The NRC inspector also reviewed audits / surveillance of ISI activities conducted by qualified personnel to verify compliance with the ISI progra _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ _ . - _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ ._ _-- - _ _ _ _ _ _ _ _ - - _ _ _ -

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b. Review of Procedures (73052)

The NRC inspector ascertained that the licensee's ISI procedures adequately covered all required aspects of the approved ISI program. All'ISI procedures were approved by the ANII and reviewed by the NRC inspector. The nondestructive examinations-(NDE) and techniques'were' adequately described and in conformance to the-requirements and guidance of ASME Section V, 1980 Edition, Winter 1981 Addenda.

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. c. Data Review and Evaluation (73755)

o The NRC inspector ascertained that the' reported data covered the scope of the examinations required during this inspection period as described in the ASME-Code, Technical Specifications, and the ISI program. This review included the examination of documents relating to the NDE equipment, data, and evaluation. The eddy current examinations. covered 100% of all accessible tubing within the steam

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generators. The NRC inspector reviewed the ET reports.and the results were as follows:

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Steam Tubes Plugged Total l Tubes Generator This Outage ' Plugged 21 3 62 22 5 135 No sleeving was performed this outage. The examination data was within the acceptable criteria as outlined in the applicable NDE procedures and Code requirement d. Observation of Work and Work Activities (73753)

The NRC inspector observed the following activities and verified that the ISI was performed in accordance with the Technical Specifications, licensee procedures, and the applicable ASME Codes:

(1) Conam personnel performing eddy current examinations on many steam generator tubes in steam generators 21 and 2 '

(2) WEC and Conam personnel. utilizing the Eddy Current Data Acquisition and Analysis Syste (3) LMT personnel utilizing the master / slave ultrasonic system, pulse-echo ultrasonic flaw detection instruments, and various transducer (4) LMT personnel performing ultrasonic examinations on the head adapter plug weld 8862-R3 and pipe weld Wl-15 on the ,

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pressurizer surge lin (5) LMT personnel performing liquid penetrant examinations on the head adapter plug weld 8862-R _ __ -

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(6) WEC personnel demonstrating to management and the NRC the technique for removing a mechanical plug from a tube in a mock up steam generato (7) WEC personnel training NSP personnel in removing mechanical plugs from steam generator tube ;

(8) Conam personnel performing visual examinations on 24 i Westinghouse mechanical plugs that were installed in the tubes !

of steam generators 21 and 22 on the hot leg side. Westinghouse l has had trouble with mechanical plugs with material heat N NX3962 at other sites on the hot leg side. There are 48 Westinghouse mechanical plugs with heat No. NX3962 installed in tubes in steam generators 21 and 22. Twenty-four plugs are in the hot leg side of the steam generators, four plugs in steam generator 21 and twenty plugs in steam generator 22. The remaining plugs are in the cold leg side of the steam generators. A video tape was made of the visual examination and video prints (pictures) were produced. The purpose of the inspection was to observe any leaking of the mechanical plugs with heat N NX3962. NSP quality control personnel, system engineer and the NRC inspector reviewed the video tapes and found no leaks present. There were several discussions between the NRC/NRR and NSP regarding whether some plugs were going to be removed.- It was finally decided that no plugs would be removed at this tim The NRC inspector reviewed the qualifications and certifications of all inspection personnel on site to ensure conformance with SNT-TC-1 The Level II and Level III LMT personnel performing ultrasonic exam-inations on stainless steel welds were qualified for detection and discrimination of intergranular stress corrosion cracking (IGSCC) by Electric Power Research Institute (EPRI).

No violations or deviations were identifie . Exit Meeting The inspector met with site representatives (denoted in Paragraph 1) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report. The inspector also discussed the likely information 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 document / processes as proprietar _ _ _ _ _ _ _ _ _ _ _ _ - - - - - )