IR 05000338/1987031

Insp Repts 50-338/87-31 & 50-339/87-31 on 870831-0904.No Violations or Deviations Noted.Major Areas Inspected:Unit 2 Inservice Insp,Unit 1 Ongoing Eddy Current Exam of Steam Generator Tubing,Nrc Bulletin 87-001 & Info Notice 87-036

ML20235F872
Person / Time
Site:	North Anna
Issue date:	09/18/1987
From:	Blake J, Glasman M, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20235F843	List: IR 05000338/1987031 ML20235F839
References
50-338-87-31, 50-339-87-31, IEB-87-001, IEB-87-1, IEIN-87-036, IEIN-87-36, NUDOCS 8709290351
Download: ML20235F872 (13)

Text

UNITED STATES pje Rtog%

NUCLEAR REGULATORY COMMISSION

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y g REGION ll 101 MARIETTA STREET, j

• ATL ANTA, GEORGI A 30323

%, . . . . . f Report Nos.: 50-338/87-31 and 50-339/87-31 Licensee: Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.: 50-338 and 50-339 License Nos.: NPF-4 and NPF-7 Facility Name: North Anna 1 and 2 Inspection Con d: August 31 -September 4, 1987 Inspector : I 7 R ome Dat ~ Signed i /9/97 f

. n Date Si ned Approve by 9 6 87 J. J B' lake, Chief Date Signed t rials and Processes Section i ision of Reactor Safety SUMMARY Scope: This routine, unannounced inspection was in the areas of Unit 2 Inservice Inspection (ISI), Unit 1 ongoing Eddy Current Examination of Steam Generator Tubing, licensee preliminary actions relative to NRC Bulletin 87-01 and Information Notice 87-36, and previously opened inspection item Results: No violations or deviations were identifie PDR ADOCK 05000338 G PDR

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L REPORT DETAILS Persons Contacted Licensee Employees

• E. W. Harrell, Station Manager

• Kansler, Maintenance Superintendent D. Dodson, Senior Staff Specialist

• L. N. Hartz, Engineering Supervisor, Inservice Inspection (ISI)

H. L. Travis, Supervisor Quality, NDE G. Harkness, Licensing Coordinator

• J. Leberstien, Licensing Engineering

• V. Lawshe, Quality Control /NDE

• T. Johnson, Quality Assurance Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security f-orce members, and office personne NRC Resident Inspector

• J. L. Caldwell, Senior Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on September 4,1987, with those persons indicated in the above paragraph. The inspectors described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the license The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters (Closed) URI 50-338,339/EG-26-01, Fitup Inspection of Structural Steel Weld This item deals with the interpretation of the American Welding l Standard D1.1 Section 6 as imposed by ANSI 45.2.5 for the requirement to j rerform fitup inspection of structural steel weld The licensee.has obtained an official interpretation from the ANSI committee regarding this I matter and has presented documentation indicating that their position is j consistent with the interpretation commonly used throughout the industr j The inspectors have no further questions regarding this matte i Unresolved Items Unresolved items were not discussed during this inspectio I

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..- Inservice Inspection (ISI) Unit 2 The : inspectors examined documents, activities, and records as indicated below- to determine whether ISI was being conducted in accordance with applicable -procedures, regulatory requirements and licensee . commitment The applicable code for ISI is American Society of Mechanical Engineer Boiler and Pressure Vessel (ASME B&PV) Code,Section XI, 1974 edition with addenda through' Summer 197 ISI- examinations are being conducted by Virginia Power (VP) personnel. and Westinghouse Electric Corp. (W), and Virginia Corp. of Richmond (VCR)

personnel, for the licensee, Inservice Inspection, Programmatic Review (73051)

! The inspectors reviewed the below listed documents relating to the licensee's' Inservice Inspection (ISI) program (Plan) for the current-outage in the areas 'of: program approval; general QA requirements (examination reports, control of deviations from established program; quality documentation and identification of components); work and quality ' inspection procedures; - control of processes; corrective action; document control; control of examinations and examination equipment; quality records; inspection scope; inspection intervals; personnel qualifications; and, NDE records including provisions for storeg Procedure NDE. 6.-2. R0 Review of Contractor NDE Interpretation by Virginia Power Co. Level II Personnel Virginia Power Nuclear Operations . Inservice Inspection Plan for Internal 1 Period 2 Unit 2, 1987 Refueling Outage Eddy Current Inspection Plan for Unit 2 Steam Generators Review of Procedures (73052)

(1) The inspectors reviewed the Virginia Power & Westinghouse (W)

procedures indicated below to determine whether the procedures were consistent with regulatory requirements and licensee commitment The procedures were also reviewed in the areas of procedure approval, requirements for qualification of NDE personnel, and compilation of required records; and if applicable, division of responsibility between the licensee and contractor personnel if contractor personnel are involved in the )

.ISI effor .))

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Procedure ID Title NDE-MT-1 R4 Magnetic Particle Examination (Preliminary)

NDE-RT-1 R1 Radiographic Examination (Preliminary)-

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ISI-15- R1 Ultrasonic Examination of Studs,iBolts and Nuts NDE-UT-6 RO Ultrasonic Examination of Bolts and Studs ISI-8- R7 Visual Examination Procedure

.with Amendment 01 ISI-11 R9- Liquid Penetrant Examination Procedure with Amendment 03 ISI-205 R2 Manual Ultrasonic Examination of Full with Amendment 03 Penetration Circumferential and Longitudinal Butt Welds- ,

i NDE-VT-2~ R1 Visual Examination Procedure H (2) The inspectors reviewed Ultrasonic Procedures -ISI-15, NDE-UT-6 l and ISI-205 to. ascertain whether-they had been reviewed and j approved in. accordance with the licensee's established QA ;

procedure The above procedures were reviewed for technical

- adequacy and conformance with ASME,Section V Article 5 and other license' commitments / requirements 'in the below listed areas: type of apparatus used; extent of coverage of weldment; j calibration requirements; search ~ units; beam angles; DAC curves; I reference level for monitoring discontinuities; method for demonstrating penetration; limits for evaluating and recording indications; recording significant indications .and; acceptance limit (3) The inspectors reviewed Radiographic Procedure NDE-RT-1 in the e following areas: the type of material to be radiographer has been identified; the material- and weld surface condition requirements; the material thickness .is specified; type o radiation source, effective focal spot or effective source size; film brand, tyae, and number of films in cassette are identified; min mum source to film distance; blocking or masking technique, if used; type and thickness of intensifying screens and filters; exposure conditions for procedure qualifications; ]

quality of radiographs - limits on mechanical, chemical, or i

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other blemishes, such as fogging, process marks, scratches, finger marks, loss of detail, or false indications; film density and sufficient contrast for single arid composite viewing; use of densitometers for assuring compliance with film density requirements; system of radiograph identification; use of location markers; methods of reducing and testing for back-scatter; selection and use of penetrameters including:

penetrometer placement, including special requirements for single and double wall viewing; number of penetrameters; shims under penetrameters; radiographic technique for double wall viewing; and, evaluation and disposition of radiograph (4) The inspectors reviewed liquid penetrant Procedure ISI-11 to ascertain whether it had been reviewed and approved in accordance with the licensee's established QA procedures. The above procedure was reviewed for technical adequacy and conformance with ASME,Section V, Article 6, and other licensee commitments / requirements in the below listed areas: specified method; penetrant material identification; penetrant materials analyzed for sulfur; penetrant materials analyzed for total halogens; acceptable pre-examination surface; drying time; method of penetrant application; surface temperature; solvent removal; surface drying prior to developing; type of developer; examination technique; evaluation technique; and procedure requalificatio (5) The inspectors reviewed magnetic particle Procedure NDE-MT-1 to ascertain whether it had been reviewed and approved in accordance with the licensee's established QA procedures. The above procedure was reviewed for technical adequacy and for conformance with ASME Section V, Article 7, and other licensae commitments / requirements in the below listed areas: examination method; contrast of dry powder particle color with background; surface temperature; suspension medium and su-face temperature for wet particles; viewing conditions; examination overlap and directions; pole or prod spacing; current or lifting power (yoke) and; acceptance criteri (6) The inspectors reviewed the visual examination procedures to determine whether they contained sufficient instructions to assure that the following parameters were specified and controlled within the limits permitted by the applicable code, i standard, cr any additional specification requirement; method -

direct visual, remote visual or translucent visual; application

- hydrostatic testing, fabrication procedure, visual examination  ;

l of welds, leak testing, etc. ; how visual examination is to be i i performed, type of surface condition available; method or tool {

l for surface preparation, if any, whether direct of remote '

l viewing is used; special illumination, instruments or equipment

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to be used, if any; sequence of performing examination, when applicable; data to be tabulated, if any; acceptance criteria is specified and consistent with the applicable code section or controlling specification; and report form completio c. Observation of Work and Work Activities (73753)

The inspectors observed a limited amount of work activities due to i the limited amount of examinations required during this outage. The inspectors reviewed certf fication records of equipment, materials, and NDE personnel which had been and will be utilized during the required ISI examinations during this outage. The reviews conducted by the inspectors are documented belo (,1) Examiner Qualification The inspectors reviewed the qualification documentation for the below listed Westinghouse (W) and Virginia Corp. of Richmond (VCR) examiners in the follo ing areas: employer's name; person certified; activity qualified to perform; effective period of certification; signature of employers designated representatives; basis used for certification; and annual visual acuity, color vision examination and periodic decertificatio Method-Level VT Company Examiner UT PT MT -

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VCR GAT T- TI IT VCR MJB II II II II - - -

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II II II II VCR JD - - -

II II II II VCR JB - - -

II II II II

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VCR GT -

II II II II W HMA -

I I I I I I W RSC -

I I I I I I W RRH II II II II II II II 9 WWM II II II II II II II W GAM II II II II II II II (2) The inspectors observed the ultrasonic examinations indicated belo The observations were compared with the applicable procedures and the Code in the following areas: availability of and compliance with approved Nondestructive Examination (NDE)

procedure; use of knowledgeable NDE personnel; use of NDE

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personnel qualified to the proper level; type of apparatus used; l extent of coverage of weldment; calibration requirements; search units; beam angles; DAC curves; reference level for monitoring discontinuities; method of demonstrating penetration; limits of evaluating and recording indications; recording significant indications and; acceptance limit _ - - -___-_____ _ ____ -

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Description Serial N MCP Seal Housing Bolt 505

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518

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599

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631 The following listed ultrasonic equipment and materials certification records were reviewed:

Ultrasonic Instruments Manufacturer Serial N Sonic 04405E Sonic 06209E Sonic 07853E Ultrasonic Couplant Batch No. 8557 Ultragel II Batch No. 8662 Sonotrace 40 Ultrasonic Transducers Size Frequency Serial N UT5" 2.25 MHz F10376 1.0" 2.25 MHz G07313A 1.0" x 0.375" 2.25 MHz L83003 Ultrasonic Calibration Standards Identification N yT 3e Heat N #12 BOT- 669374/ HEE

1. 13 B0H 669374/ HEE (3) The inspectors observed the magnetic particle examinations indicated below. The observations were compared with the applicable procedures and the Code in the following areas:

examination methods; contrast of dry powder particle color with background; viewing conditions; examination overlap and directions; and, acceptance criteri Description I. MCP Seal Housing Bolt 565-~

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518

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599

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631 (4) The inspectors reviewed the below listed liquid penetrant materials certification records to ascertain if the sulfur and halogen content of the material was within acceptable content limit ___-__ _

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Materials Batch Number Liquid Penetrant 85LO45 Cleaner / Remover 86A010 Developer 85M035 Inservice Inspection, Data Review and Evaluation, Unit 2 (73755)

Records of completed nondestructive examinations 'were selected and reviewed to. ascertain whether: the method (s), technique and extent of the. examination complied with the ISI plan and applicable NDE procedures; findings were properly recorded and. evaluated by

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qualified personnel; programmatic deviations were recorded as required; materials (personnel,' instruments, penetrants, couplants) were calibration blocks designate and NDE

. Records selected for this' review are listed below: 1 Drawings Item (s) NDE Method VGB-1-5100A-2: 12 #1 Seal Housing Bolts - MT MCP "B" VGB-1-5100A-2 12 #1 Seal Housing Bolts - UT MCP "B" VGB-1-51000 Flywheel MCP "B" UT VGB-2-115 Regenerative Heat Exchanger Welds UT Welds 5, 6, 11 and 12

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VGB-1-4500 Pressurizer Safety Nozzle PT Weld 02 ECI-1048 Hanger / Supports SI-A-42, SI-SH-41 VT and SI-SH-32 ECI-104E Hanger / Supports 2-RS-R-9 and VT 2-RS-R-10 ECI-104G Hanger / Support 2-QS-SH-49 VT ECI-111-AP Hanger / Supports SI-R-65 and VT 1 SI-R-65A  !

ECI-111-AG Hanger / Supports SI-R-93 and VT SI-R-93A In this area of inspection, no violations or deviations were identifie j l

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8 Steam Generator (SG) Tubing Eddy Current Examination - Unit 1 The examinations currently in progress are being accomplished as a result of a tube rupture in SG "C" that occurred on July 15, 1987. For additional information concerning this event and subsequent actions by the licensee, refer to NRC reports 50-338,339/87-24 and 50-338/87-2 The inspectors observed tube data analysis activities, as listed below, to

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determine whether these activities were being conducted in accordance with applicable procedures, regulatory requirements, and licensee' commitments.

! The licensee's data evaluation program requires that the obtained data will be evaluated by two analysts working totally independent of each other. When interpretation conflicts arise, the two involved analysts review the signals jointly and resolve the conflict in accordance with established analysis rules. If the signal in conflict is determined to be a relevant indication no further action is required. However, if the signal in conflict is determined not to be representative of a relevant indication, agreement of a third analysis is required before the signal can be classified as non-relevan The inspectors observed the two electronic analysis assistance systems, IEDA and DDAS, and Westinghouse and Echogram Technology, Inc. personnel performing data analysis functions on the below listed tubes. These observations included:several analysts and included ~

both primary and secondary tube data evaluations and data comparisons being made between the examinations conducted in May 1987 and the current examination Tube Steam Generator Row Column Date Type C

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W 44 8x1 C 11 84 8x1 C 10 84 8x1 C 8 84 8x1 B 15 38 Standard Bobbin B 13 36 Standard Bobbin B 11 36 Standard Bobbin B 5 28 Standard Bobbin B 13 38 Standard Bobbin B 7 36 Standard Bobbin C 42 41 Standard Bobbin A 38 74 Standard Bobbin A 37 74 Standard Bobbin

• C 15 36 Standard Bobbin

• C 23 41 Standard Bobbin

• C 14 36 Standard Bobbin

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• C 24 41 Standard Bobbin

" *C 13 36 Standard Bobbin

• C 25 41 Standard Bobbin

• • C 9 55 Standard Bobbin

• • C 31 53 Standard Bobbin

• • B 30 24 Standard Bobbin

• May examination date being re-examine **May/ July examination data compariso .

b. At the time of this inspection, Westinghouse and Virginia Power  ;

personnel were engaged in the re-evaluation of the May 1987 eddy-current data. The inspectors witnessed review of the data obtained from the Hot Leg of Steam Generator "C" with the Standard Bobbin Coil probe. Data was being reviewed by Westinghouse personnel using the Westinghouse Intelligent Eddy-Current Data Analysis (IEDA)

System, followed by interpretation by Westinghouse analyst The Westinghouse effort was being overseen and sampled by Virginia Power

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NDT/QA personne During the May 1987 outage,' tubes which were candidates for closer examination for potential degradation were selected based on the following eddy-current indication parameters:

Greater than 1.0 to 1.25 volts Greater than 10 to 15 phase angle For this most recent examination (July - September 1987) criteria for closer examination are essentially the same, however, the latitude for interpretation was eliminated. The new criteria are:

Greater than 1.0 volt Greater than 10 phase angle Listed below are re-evaluated eddy-current data on six hot leg locations for Steam Generator "C" obtained in the May 1987 outag All indications listed below were classified as " Distorted" during the recent outage (based on the new interpretation criteria). Three of these indications were plugged in the May 1987 outage, and three were left in servic Disposition of the three unplugged tubes had not been determined at the conclusion of this inspectio Row / Col Location Volts Phase Indication Remarks 3/17 4 SP R F DI Not plugged

! 2 SP 1.40 21 DI 1 SP 1.22 28 DI 3/13 3 SP 1 DI Plugged 5/87 3 SP DI 2 SP 2. 9 18 DI

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3/1 1 SP 1. 8 19 DI Not plugged 4/3 2 SP 1. 6 24 DI Not plugged 4/4 5 SP 3. 9 26 DI Plugged 5/87

! 4/6 4 SP * DI Plugged 5/87 2 SP 4 DI 2 SP 2. 6 50 DI 1 SP DI The inspectors discussed the examination status with the licensee just prior to the conclusion of this inspection. The EC examination status for the Unit 1 steam generators is tabulated belo Number of Tubes PROBED Steam Generator Standard Bobbin 8x1 A 2685 7179 CL 3179 HL B 2662 3210 CL 3210 HL C 2390 CL 3117 CL 373 HL 3117 HL Number of Tubes ANALYZED Steam Generator Standard Bobbin 8x1 A 2597 III4 CL 3178 HL B 2631 1115 CL 3210 HL C 2380 CL 3109 CL 373 HL 3099 HL CL - cold leg HL - hot leg In this area of inspection, no violations or deviations were identifie . IE Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants and Information Notice 87-36, Significant Unexpected Erosion of Feedwater Line The licen:;ce has not officially responded to the requirements of Bulletin 87-01; however, the inspectors conducted a preliminary review of documentation and data relative to the actions being generated as a result of this bulletin and information notice. The inspectors also observed work being performed as a result of actions being taken by the license _ - - _ - ____________ _ _ _ _ - _ _ _ _ _ .__ _ - _ - - -

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The documentation reviews and observations conducted by the inspectors are doctaented in the following subparagraph Plan Review The inspectors reviewed the below listed documents relating to the inspection plan in the areas of: plan approval; general QA requirements; examination procedures; control of examinations and examination equipment; quality records, personnel qualifications; and

NDE records.

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ISI-8.0, Secondary Single Phase Piping Examinations (Draft)

ISI-8.1, Secondary Two Phase Piping Examinations with

Attachment 1 (Draft)

MEMORANDUM dated 8/27/87 relative to additional inspection points as a result of IN 87-3 The inspectors reviewed Procedure NDE-UT-4 R0, Ultrasonic Thickness Measurement This procedure is being utilized to obtain the thickness readings required by the licensees inspection plan. The procedure was reviewed in the areas of procedure approval, requirements for qualification o NDE personnel, and compilation of required records, The inspectors observed approximately 200 thickness readings being taken on the items listed below. The inspectors reviewed certification records of equipment, materials, and NDE personnel being utilized during the examination of these item Drawing Component ID SIE-2401A 02-ES-PSF 2-3 S2E-2401A 02-ES-PPS-29 In this area of inspection, no violations or deviations were identifie . Inspector Follow-up Items (Closed) 338/86-12-01, Reactor Coolant Pump (RPC) Flywheel Assembly Procedur This item was identified when a review of Procedure EMP-C-RC-4 was found lacking in specific instruction for the disassembly and reassembly of the reactor coolant pump flywhee Revision 11 to the subject procedure has been issued and now issued and now includes the specific instructions necessary to adequately perform the required task. The inspectors have no further questions regarding this ite (Closed) 338/85-37-02, Examination of Transition Welds in S/Gs "A" and "C". This item was identified as a result of an internal memoranda suggesting that the site perform a surface examination on

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the I.D. of the transition weld in each of the SG' This suggestion was made as a result of the cracking that was discovered in the Surry SG' Licensee review of pre- and post-weld heat treat records indicate that the North Anna welds were subjected to a favorabl stress relief temperature and time. In addition, magnetic particle (MT) surface examination of selected areas on the I.D. of one girth weld in Unit 1 and one girth weld in Unit 2 steam generators failed to detect any evidence of cracking. At Surry, the cracking was thought to be caused by the combined presence of copper, oxygen, chlorides and high residual weld stress. At North Anna chlorides have been lower and the welds were processed in a manner to preclude .

high residual stresses. Examination of additional girth welds is not l considered justified based on the MT examination results and the information provided above. This item is considered close l

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