IR 05000213/1987024

Insp Rept 50-213/87-24 on 870810-14.No Violations Noted. Major Areas Inspected:Licensee Surveillance of Vendor Inservice Insp Activities,Review of Inservice Insp NDE Procedures & Balance of Plant Erosion/Corrosion Program

ML20235G502
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/17/1987
From:	Mcbrearty R, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20235G483	List: IR 05000213/1987024 ML20235G479
References
50-213-87-24, NUDOCS 8709300073
Download: ML20235G502 (9)

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l U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /87-24 Docket N License No. DPR-61 Licensee: Connecticut Yankee Atomic Power Company P. O. Box 270 Hartford, Connecticut 06141 Facility Name: Haddam Neck Plant Inspection At: Haddam, Connecticut Inspection Conducted: August 10-14, 1987 Inspectors: k h' '

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/7 / fp7 R.A.McBrearty,Reactorpgineer Approved by: /87 R. Strosnider, Chief, Materials and date Processes Section, EB, DRS Inspection Summary: Inspection on August 10-14, 1987 (Inspection Report No. 50-213/87-24)

Areas Inspected: A routine, unannounced inspection was conducted by one regional based inspector of licensee surveillance of vendor ISI activities; review of ISI NDE procedures; review of ISI data; observations of ISI in progress, including collection and analysis of eddy current examination data; review of NDE personnel qualification / certification records; and the balance of plant erosion / corrosion progra Results: No violations were identifie I 8709300073 070921 3 PDR ADOCK 0500 G

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DETAILS Persons Contacted Northeast Utilities N. Azevedo, Engineer

• J. Beauchamp, Quality Services Supervisor

• J. Bouchard, Unit Superintendent

• J. Calderone, ISI Engineer

• J. Delawrence, ISI Engineer ,

R. Fuller, NDE Level III i W. Heinig, QC Engineer F. Ickes, ISI Coordinator (NUSCD)

L. Laskowski, Engineer - Nuclear Materials and Chemistry

• D. Miller, Jr. , Station Superintendent

• D. Ray, Engineering Supervisor S. Sikonski, NDE Level III M. Smith, ISI Coordinator (CY)

Conam Inspection J. Funanich, ET Level III B. Marlowe, ET Level III U.S. Nuclear Regulatory Commission

• A. Asars, Resident Inspector

• Denotes those present at the exit meetin . Inservice Inspection Program Review The current refueling outage at the Haddam Neck plant is the last outage of the 2nd ten year inspection interva The examinations scheduled for completion during the ongoing outage will complete the ISI requirements for the interval. The program for the next inspection interval has been submitted by the licensee to the NRC for review and approval. The governing ASME Code,Section XI for the current examinations is the 1980 Edition up to and including Winter 1980 Addenda, which became applicable commencing with the 1983 refueling outag The Haddam Neck plant was constructed and commenced commercial operation prior to the establishment of ASME Section XI examination requirement At the end of the first inspection interval, when the RPV weld examina-tions were required to be performed, the applicable Section XI was the 1974 Edition through Summer 1975 Addenda. The second inspection interval is currently governed by the requirements of the edition referenced abov Reactor pressure vessel examination requirements which were applicable at various times during the life of the plant were comprised of the following:

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RPV Weld Examination Requirements at Haddam Neck

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Preservice 1st Inspection 2nd Inspection Inspection Interval Interval No Section XI 1974 through S'75 1980 through W'80 None 10% of the length of each 100% of the length of one longitudinal weld beltline region longitudinal 5% of the length of each 100% of the length of one circumferential weld beltline region circumferential weld As stated above, the licensee is currently committed to perform the reactor pressure vessel inspection in accordance with the 1980 Edition through Winter 1980 Addenda of Section XI. As indicated in the Table, the scope of the required beltline inspection is 100% of one longitudinal weld and 100% of one circumferential weld. It should be noted, however, that the scope of the first 10 year interval required by the 1980 Edition through Winter 1980 Addenda of Section XI requires 100% inspection of all beltline welds. Because the first inspection interval for Haddam Neck was conducted in accordance with the 1974 Edition through Summer 1975 Addenda, the Haddam Neck reactor pressure vessel does not have a 100%

baseline. NRC Region I and Headquarters staf f discussed this subject with licensee representatives in a conference call on September 2, 1987. At that time the scope of the beltline weld inspection planned by the licensee was greater than the two welds required by the Code and included essentially all of the beltline region welds with the exception of some portion of the lower course longitudinal welds. Subsequently, the licensee decided to inspect 100% of the lower beltline course longitudinal welds. Thus the scope of the current inspection will include all of the beltline welds providing a Baseline for the beltline welds consistent with that which would have resulted from performing the first ten year interval inspection in accordance with the 1980 through Winter 1980 Edition of Section X The program has been computerized for outage planning purposes and for status tracking to assure compliance with code and regulatory require-ment Information maintained by the computer includes examination status of each item, weld wall thickness 4 applicable calibration block ident1-fication and the code required examination metho The inspector found that the tracking system is capable of identifying the current status of each item in the program, and that updates to the system are entered on a frequent basi _____ _-_

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4 Review of ISI Implementing Procedures The following nondestructive examination procedures were reviewed by the inspector with regard to technical adequacy, and to ascertain compliance with applicable ASME Code and regulatory requirement *

Procedure No. NU-MP-1, Revision 6, " Procedure for Magnetic Particle Examination"

Procedure No. NU-LP-1, Revision 7, " Procedure for Liquid Penetrant Examination"

Procedure No. NU-UT-5, Revision 3, " Ultrasonic Examination Procedure for Thickness Measurements"

Procedure No. 42-EC-131, Revision 3, "Multifrequency Eddy Current Procedure - Westinghouse Series 27 Steam Generator Tubing - MIZ-18 Digital Eddy Current System"

Procedure No. 42-EC-135, Revision 1, " Motorized Rotating Probe Procedure for Westinghouse Series 27 Steam Generator Tubing - MIZ-18 Digital Eddy Current System"

Procedure No. 42-EC-159, Rev. O, " Procedure for Marking Tubes with the SM-10 and the Conam Tube Marker"

Procedure No. 42-EC-160, Revision 0, " Procedure for Installing, Operating and Removing the SM-10 Fixture" The procedures for magnetic particle, liquid penetrant and ultrasonic examination are licensee procedures which are used by trained ISI vendor personne The procedure for ultrasonic thickness measurements was used for the balance of plant erosion / corrosion program activitie The procedures which governed the steam generator tubing examinations were developed by Conam Inspection, the licensee's eddy current examination vendo The inspector's review indicated that the above listed procedures meet applicable code and regulatory requirements, and are technically acceptable for their intended us No violations were identifie .

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4. Observations of Work in Progress The steam generator tube eddy current examination sample selected by the licensee included 3% of the tubes in each of the four steam generators as required by Technical Specification 4.10.1. During the inspection of steam generator #1 tubes on August 1, 1987, the inspection results were classified into category C-3 which required that the inspection sample be increased to include 100% of the tubes in #1 steam generator, and 6% of the tubes in each of the other steam generators. During the examination of #2 steam generator tubes on August 6, 1987, those results were l classified into category C-3. The licensee was then required by Technical Specification 4.10.1, Table 1-2 to inspect all tubes in each steam generato The inspector observed the eddy current inspection of tubes in steam generator #1 to ascertain compliance with the facility Technical i

Specificatio The observations included inspection of the following

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tubes:

Row Column 39 40 30 40 l

6 40 5 40 4 40 2 46 .

30 47 The inspections were performed by Conam Inspection personnel using the MIZ-18 inspection syste The system incorporates a computer controlled robotic arm (SM-10 fixture)

which locates the probe at the designated tube. Templates were not required for tube identification, and the SM-10 fixture was attached to the steam generator manway, thereby reducing radiation exposure to equipment installer In addition to observing the data collection process, the inspector observed the steam generator training mock-up, and the health physics station where steam generator inspection activities were monitored and controlled. Personnel activities at the steam generators were monitored by closed circuit television, and instructions to the personnel were conveyed by voice contact from the control statio Timers were set up at each video monitor so that stay times could be accurately controlled by the health physics personnel who were assigned to the activity. A spare SM-10 fixture was purchased by the licensee for the purpose of

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training personnel in correct installation and removal procedure The spare was attached to the mock-up at the time of the inspector's observatio The inspector also visited the offsite location where eddy current inspection data were analyzed and interpreted by Conam Inspection Level IIIA and Level III analyst The system for analyzing data included analysis and interpretation by two qualified Level IIA analysts (primary and secondary), and by a qualified Level III individual. When the data are brought from the site, a copy is made so that the two, primary and secondary, analysts each have a copy of the complete data. The results of each analyst are checked with a computer program which identifies any discrepant calls for individual tubes. The Level III reviews the data including the discrepancies, and he is responsible for resolving discrepancies, and overruling calls if necessary. The licensee has placed controls on the data analysis process to minimize missing significant indications and unreviewed overruled calls by the Level III. If one of the original analysts identifies a pluggable tube and the Level III agrees that the tube is pluggable, the results are documented on the discrepancy printout and are considered fina If the Level III disagrees with the "pluggable" call, he fills out and signs an Overruling Pluggable Indication Report Form", and then i has a second analyst complete and sign the form. The second analyst is not one of the original analyst If the second analyst agrees with the Level III the results are considered final. If the second analyst disagrees with the Level III, the original results will prevail and the tube will be plugge The inspector found that the Conam analysts were trained prior to the commencement of work at the site to meet requirements which were established by the licensee to minimize the possibility of significant indications being missed, and tubes net being inspecte The licensee provided training tapes of previous inspections at the facility to familiarize the analysts with the type of defects which were detected at the facility in the past. The licensee has established an action plan for optimizing steam generator inspection programs at -

Northeast Utilities plants of which the above is a part. The plan includes a provision to deve'op and implement a plant specific data f analyst training and performance demonstration program. The analyst  !

training which was implemented met the intent of the licensee's l recommendations for training, but development of the program occurred too l late for full implementation at Haddam Neck during the July 1987 outag Examination and data analysis personnel were found to be qualified and certified in accordance with applicable requirement I m_____.__.____.______ . _ _ J

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The inspector found that the data were analyzed in accordance with licensee requirements and the inspections were done in accor 'ance with the facility Technical Specification and with code requirement No violations were identifie . Inservice Inspection (ISI) Data Review

The inspector reviewed selected ISI data representing ultrasonic and j liquid penetrant examinations to ascertain that the data were complete, and that the ASME Code and regulatory requirements were me Data associated with the fcilowing were included in the inspector's revie *

Reactor Coolant Loop 4 weld #43-12, valve to pipe

• Reactor Coolant Loop 4 weld #50-5A, lh" socket weld

• Reactor Coolant Loop 3 weld #33-08, pipe to elbow

Reactor Coolant System weld,#22-12, valve to pipe Indications which were reported in the welds were evaluated by Level III personne The penetrant indication reported in weld 50-5A was evaluated to be rejectable in accordance with ASME Section XI criteria, and was dispositioned to be repaire NCR #87-182 was issued on August 5, 1987, and was not yet closed at the time of this inspectio This is the first time the licensee performed a surface examination on this weld. Weld 33-08 was penetrant examined on the as-welded surface, and displayed numerous indications over a large area. A 6" length of weld which represented the worst case was ground and re-examined. The majority of l the indications were removed, and those which remained were found to be acceptable in accordance with Section XI criteria. A supplemental ultrasonic examination was perforned using a technique which was qualified for the detection of near surface reflectors. The technique incorporated a VSY-60 refracted longitudinal angle beam transducer, and calibration of the system was based on an ECM surface notch and 0.03" diameter side drilled holes at various depths from the test surface. The rerolts of the ultrasonic examination showed that the remaining penetrant indications were approximately 0.1" maximum depth, randomly oriented, and were determined to be acceptable by cod The inspector found that the examinations were performed by qualified and certified NDE personnel, the results were reviewed by the licensee and evaluations and dispositions were properly documente j No violations were identifie . Secondary Side Erosion / Corrosion Examination Program The inspector reviewed the licensee's actions with regard to the detection of erosion / corrosion in plant components. Concern regarding erosion / corrosion in balance of plant piping systems has been heightened l as a result of the December 9, 1986 feedwater line rupture that occurred

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at Surry Unit This event was the subject of NRC Information Notice 86-106 issued on December 16, 1986 and its supplement issued on February 13, 1987. The inspection was conducted to ascertain the scope of the licensee's program, and the results to dat The licensee has established an inspection prcgram to identify the existence of piping with less than minimal designed wall thickness requi rernents. A five year inspection interval for complete coverage of all designated areas, both single and two phase flow, has been established by the licensee. The areas of inspection will include main steam, turbine exhaust piping, condensate, feedwater, and service water piping system The licensee plans to incorporate into the program a contingency for more frequent inspection of potential trouble area Ti.e 11cer.see's program was started in 1977 with the measurement of selected areas. The program was expanded in 1984 to include more areas and to provide for more complete record keepin Data which were collected beginning with the 1984 examinations will be used for trending purposes. There are 179 examinations scheduled for completion during ine current outage, and at the time of this inspection 73 examinations were completed, but the results were not fully evaluate The calculation for minimum required wall thickness which is provided by ASME Section III will be used as a reference poin If the minimum wall thickness measured is viithin 10% of the minimum thickness calculation, a retest will be made. If the minimum wall thickness measured is equal to or below the minimum thickness calculation, that piping will be recom-mended for immediate replacemen The licensee is currently working with the EPRI C.H.E.C. (Chexal-Horowitz Erosion-Corrosion Program), and the MIT Erosion-Corrosion Program. When finalized, the programs are anticipated by the licensee to do the followir.g:

Predict the erosion corrosion rate

• Rank-components for any system in order of potential erosion corrosion damage

Compare its predictions with measured p'ar.t data for performing statistical analy~ sis

Calculate time at vhich the minimum code allowable wall thickness is rear.hed The licensee anticipates that the computer program will be in place by the end of the 1987 outag The inspector had no further questions at this time.

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l l Nondestructive Examination (NDE) Personnel Qualification / Certification Records The inspector reviewed records related to the qualification / certification 4 of Conam Inspection personnel who were responsible for the eddy current '

inspection of steam generator tubes at Connecticut Yankee, and for the analysis of eddy current examination data. Additionally, qualification /

certification records were reviewed for EBASCO personnel who performed inservice examinations at Haddam Neck. The review was done to ascertain that the individuals were qualified and certified to perform their assigned responsibilities in accordance with applicable requirement The inspector found that the records confirmed that each individual was properly certified, and was qualified to perform his assigned responsibilitie No violations were identifie . Licensee Surveillance of Vendor ISI Activities The inspector reviewed the licensee's actions regarding surveillance of activities performed by its ISI vendor The inspection was conducted to ascertain the adequacy of the licensee's overview of vendor activities, and further, to ascertain that licensee and regulatory requirements were me The inspector's review included reports of ten surveiilances which were performed by the licensee during the period from July 28, 1987 to August 11, 1987. Areas covered by surveillance included the hydrostatic test of spent fuel heat exchangers, weld examinations, examination of supports and steam generator tubing examination The above examir,ations included liquid penetrant, magnetic particle, eddy current and ultrasonic examination method The inspector found that the scope of the licensee's surveillance was broad enough to assess the vendors' performanc The inspection indicated that the surveillance were performed by licensee personnel who were familiar with the activities being monitored, and that licensee and regulatory requirements were me No violations were identifie . Exit Meeting The inspector met with licensee representatives, denoted in paragraph 1, at the conclusion of the inspection on August 14, 1987. The inspector summarized the purpose and scope of the inspection and the findings. At no time during this inspection was written material provided by the inspector to the license _ _ - - _ _ _ _ _ _ _ ._