IR 05000348/1986008

Insp Repts 50-348/86-08 & 50-364/86-08 on 860414-18.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp of Unit 2 & Previously Opened Items

ML20197J909
Person / Time
Site:	Farley
Issue date:	05/13/1986
From:	Blake J, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20197J885	List: IR 05000348/1986008 ML20197J882
References
50-348-86-08, 50-348-86-8, 50-364-86-08, 50-364-86-8, NUDOCS 8605200202
Download: ML20197J909 (9)

Text

p Ett UNITED STATES

_4' o NUCLEAR REGULATORY COMMisslON g g REGION ll y j 101 MARIETTA STREET, .*' s ATLANT A, GEORGI A 30323

\...../

-Report Nos.: 50-348/86-08 and 50-364/86-08

' Licensee: . Alabama Power Company 600 North 18th Street

, ,

-Bireingham, AL 35291 Docket Nos.: 50-348 and 50-364 License No.: NPF-2 and NPF-8

. Facility Name: Farley 1 and 2 Inspection Conducted: April 14 - 18, 1986 Inspector: h f- /1 - #4

' s' Date Signe Approved by: 3 6 J J/ Blake, Section Chief- Date Signed npneeringBranch Division of Reactor Safety SUM 4ARY Scope: This routine, unannounced inspection-involved 37 inspector-hours on site

in the areas of inservice inspection (ISI)'of Unit 2-and previously-opened item Results: No violations or deviations were identifie _

p 202 860514 G M 05000348-PDR J

.e

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REPORT DETAILS Persons Contacted Licensee Employees

• D. N. Morey, Assistant Plant Manager, Operations

• R. M. Coleman, Systems Performance Supervisor

• S. T. Burns, Senior Project Engineer, Inservice Inspection (ISI)

• R. V. Badham, General Plant Engineer

• C.~ Carstensen, Junior Engineer

• T. P. Davis, Safety Audit and Engineer Review Group Other licensee employees contacted included engineers, technicians, operators, mechanics, security office members and office personne Other Organizations K. Johns, Southern Company, ISI R. Davis, Southern Company, ISI J. Campbell, Westinghouse Electric (W), ISI NRC Resident Inspectors

• H. Bradford, Senior Resident Inspector B. Bonser, Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on April 18, 1986, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The licensee did identify as proprietary, material provided and reviewed by the inspector during this inspection; however, this material is not discussed in this repor . Licensee Action on Previous Enforcement Matters Unit 1 (Closed) Violation 348/85-33-05, Failure to Follow Procedures for Verifica-tion of Spring Support Settings. This item identified an incident where verification of variable spring type hangers, as required by the controlling procedure, was omitted. ,This omission was attributed to personnel error, in that the inspection personnel failed to identify the settings on the spring hangers, and supervision performing the data review failed to identify the omission. Additionally, the procedure did not lend itself to proper review as there were no blanks on the data sheet to record support spring setting .

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This is considered an isolated incident as a review of additional hanger data sheets failed to identify any additional omissions. The omitted spring hanger settings will be verified during the next refueling outage and this will comply with ASME Section XI and other controlling documents. The individuals involved with data collection and review have been reinstructed on the necessity of procedure adherence and proper review and the controlling procedure, FNP-2-STP-157.0, has been revised to facilitate data review. The inspector has no further questions regarding this matte . Unresolved Items

Unresolved items were not identified during the inspectio . Independent Inspection Effort The inspector conducted a general inspection of the auxiliary building, turbine building and Unit 2 containment to observe activities such as welding, material handling and control, housekeeping and storag Within the areas examined, no violations or deviations were identifie . Inservice Inspection (ISI) - Review of Program (73051) (Unit 2)

The inspector reviewed the licensee's ISI program in the areas indicated below. The ISI is for the first interval, second period, second outage, and is being performed by Westinghouse (W) in accordance with the ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition with Addenda through the Summer of 197 The inspector reviewed the ISI program for the current outage to determine whether the program had been approved by the licensee and included a description of areas to be examined, examination category, method of inspection, extent of examination, and justification of any exception The inspector reviewed W procedure OPS-NSD-101, Revision 5, field changes 1, 2, 3, and 4,Preservice and Inservice Inspection Documen-tation" to assure that a procedure had been established (written, reviewed, approved, and issued) to control general quality assurance (QA) requirements including examination reports and to establish controls for generation, approval, custody, storage and maintenance of nondestructive examination (NDE) records Inservice Inspection - Review of Procedures (73052) (Unit 2)

The inspector reviewed the ISI procedures indicated below to determine whether the procedures were consistent with regulatory requirements and licensee commitment .

a. The following procedures were reviewed in the areas of procedure approval, requirements for qualification of NDE personnel, and compila-tion of required records:

(1) 151-205, Revision 2, Am. 03, FCs 01, 02, 03 and 04, " Manual Ultrasonic Examination of Full Penetration Circumferential and Longitudinal Butt Welds" (2) MRS 2.4.2 APC-6, Revision 1, " Digital Multi-Frequency Eddy Current Inspection of Preservice and Inservice Heat Exchanger Tubing" (3) ISI-15 Revision 6, Am.2, " Ultrasonic Examination of Studs, Bolts, and Nuts" (4) ISI-47 Revision 2, " Manual Ultrasonic Examination of Circum-ferential and Longitudinal Butt Welds in Ferritic Vessels of 2 "

Thick and Greater" b. Procedures ISI-205, ISI-15, and ISI-47 were reviewed for technical content in the areas of:

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Type of apparatus

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Extent of coverage including beam angles and scanning techniques

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Calibration requirements

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Search units

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DAC curves

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Reference level for monitoring discontinuities

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Method of demonstrating penetration

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Levels for evaluation and recording indications

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Acceptance criteria c. Procedure MRS 2.4.2 APC-6 was reviewed for technical content in the areas of:

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Equipment

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Test sensitivity

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Material Permeability

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Test method

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Calibration

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Acceptance criteria In addition, the following associated procedures were reviewed:

MRC 2.2.2 APC-1, R1, " Installation and Removal of Temporary Nozzle Covers"

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MRS 2.2.2, APC-2, R2, " Steam Generator Tube Sheet Marking" In this area of inspection, no violations or deviations were identi-fie .

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. l 4 Inservice Inspection - Observation of Work and Work Activities (73753)

(Unit 2)

The inspector observed the ISI activities described below to determine whether these activities were being performed in accordance with regulatory requirements and licensee procedure Examiner Qualification The inspector reviewed the qualification documentation for the below listed examiners in the following areas: employer's name; person certified; activity qualified to perform; effective period of certifi-cation; signature of employer's designated representatives; basis used for certification; and annual visual acuity, color vision examination and periodic recertificatio Method - Level VT Examiner UT PT MT RT EC 1-2-3-4 GRA I II -- -- --

III III III --

JBC II II II II --

III --- --- --

JC II II II -- --

II --- --- --

JMC II II II -- --

II --- --- --

EGH I II I -- --

II --- --- --

-- -- -- --

RWH II II II II II HK I II -- -- --

II --- --- --

JSM -- -- -- -- --

II --- --- --

ELM III III III -- --

II --- --- --

--

RRS II II II --

II --- --- --

-- --

SS II II --

II --- --- --

TLS II II II -- --

II --- --- --

LPT I II II I -- --- --- --- --

MDT II II II -- --

II --- --- --

TJU II II II -- -- --- --- --- --

PV I II II -- --

II --- --- --

FG -- -- --

-- III II --- --- --

NG -- -- -- --

IIA --- --- --- --

JC -- -- -- --

IIA --- --- --- --

EH -- -- -- --

IIA --- --- --- --

JK -- -- -- --

I --- --- --- -- In prccess liquid penetrant (PT) inspection of loop 2 safety injection system welds 18,19, 20, 21, 22, and 23BC on 150 APR-1-4205 was observed and compared with the requirements of the applicable proce-dures and Code in the following areas:

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Availability of and compliance with approved NDE procedures

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Use of knowledgeable NDE personnel

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Use of NDE personnel qualified to the proper level Recording of inspection results

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Method consistent with procedure

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Penetrant materials identified and consistent with ASME Code

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Certification of sulfur and halogen content for penetrant materials

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Surface preparation

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Drying time following surface cleaning

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Penetrant application and penetration time

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Examination surface temperature

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Penetrant removal

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Drying of surface prior to developing

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Developer type, application and time interval after penetrant removal

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Time interval between developer application and evaluation

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Evaluation technique

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Reporting examination results In addition, certification records for the following penetrant materials were reviewed:

Developer Batch 85M035 Penetrant Batch 85L045 Cleaner Batch 85M039 In process ultrasonic (UT) inspection including calibration activities of the following welds was observed:

IS0 SYSTEM WELD APR-1-4200 Loop 2 Reactor Coolant Pipe 4DM, SDM (45 scan)

APR-1-4208 Loop 2 Pressurizer Spray 6 (0* and 45 )

APR-1-4208 Loop 2 Pressurizer Spray 5 (45 )

APR-1-4208 Loop 2 Pressurizer Spray 3 (0 )

The above in process UT inspections were compared with the requirements of the applicable procedures and Code in the following areas:

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Availability of and compliance with approved NDE procedures

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Use of knowledgeable NDE personnel

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Use of NDE personnel qualified to the proper level

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Recording of inspection results

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Type of apparatus used

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Extent of coverage of weldment

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Calibration requirements

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Search unit

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Beam angles

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DAC curves

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Reference level for monitoring discontinuities

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.

--

Method of demonstration of penetration

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Limits of evaluating and recording indications

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Recording significant indications

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Acceptance limits The examinations of the reactor coolant pipe welds were being conducted using a new examination procedure, a new calibration block, and a new type UT probe that utilizes a pitch / catch arrangement with a 45*

longitudinal wave with a focused beam. In order to determine if the examination sensitivity levels were adequate, utilizing the new examination parameters, an attenuation comparison was made between the original calibration block, the new calibration block, and some of the reactor coolant pipe welds in the field, using the new UT probe. The results of this comparison indicated that there were some attenuation differences between the new calibration block and the original

- calibration block but the use of the new calibration block appears to -

give a more conservative examination and the new block seems to be more representative of the material in the fiel During the NRC inspector's observation of the UT examination of Loop 2 reactor coolant pipe weld SDM an indication was noted by .the UT examiner and some preliminary reflector information was recorded. The inspector. observed the reflector which appears to have an amplitude of 100 percent of reference level at a location of approximately 2.32" from the outside surface of the pipe while the sound beam is directed toward the steam generator. Additional UT reflectors were noted in welds 8 and 9 during the course of the Loop 2 reactor coolant pipe weld examinations. - Additional . information was still being collected and analyzed with no final disposition of any of the reflectors having been determined at the conclusion of the NRC inspectio '

The following certification / calibration records relative to the above inspections were reviewed:

UT Couplant - Sonotrace 40, Batch 8554 Calibration Blocks - ALA-7 A1A-APR-33 UT Instruments - Sonic 08212E Sonic 01057E UT Transducers - Serial B20572 Serial L13422 Serial B13036 In process eddy current (ET) inspection data evaluation including calibration checks were observed for the following steam ganerator (SG)

tubes:

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Tube I.D. SG-B Tube I.D. SG-C Row Column Row Column 42 67 46 41 28 43 38 46 35 69 44 59 31 72 13 61 12 74 44 62 18 83 12 64 13 92 39 67 19 64 11 72 19 52 11 74 23 17 8 79 28 72 30 46 18 73 39 41 The inspections were compared with the requirements of applicable procedures and code in the areas of:

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Equipment

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Sensitivity

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Test method

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Calibration

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Acceptance criteria In addition, certification records for the following ET standards were reviewed:

Z-3160 Z-2429 Z-1593 At the conclusion of the NRC inspection all examinations had not been completed, however, the final examination results will be reported to the NRC in accordance with TECH SPEC requirements. The inspector discussed the ET program and status with the licensee and the preliminary ET examination status for steam generators B and C are listed below. Examination of steam generator A had not yet starte SG-B SG-C Tubes Examined 3290 3294 Tubes with reportable indications 24 44 Possible tubes to be plugged 12 40 Previously plugged tubes 98 94

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In this area of inspection, no violations or deviations were identi-fie . Inservice Inspection, Data Review and Evaluation, Unit 2 (73755)

Records of completed nondestructive examinations were selected and reviewed to ascertain whether: the methods, technique and extent of the examination complied with the ISI plan and applicable NDE procedures; findings were properly recorded and evaluated by qualified personnel; programmatic deviations were recorded as required; personnel, instruments, calibration blocks and NDE materials (penetrants, couplants) were designate System / Component Item / Weld Sketch / ISO N NDE Method R.V. Closure Head 1 APR-1-1300 UT-0 ,45 ,60 Pressurizer 8 APR-1-2100 UT-0 45 Loop 1 RHR Take-Off 4 APR-1-4111 UT-45 3 Loop 1 RHR Take-Off 5 APR-1-4111 UT-45*

Loop-1 RHR Take-Off 6 APR-1-4111 UT-45 Loop 2 RC Pipe 9 APR-1-4200 UT-0 Loop 2 RC Pipe 21BC APR-1-4200 UT-0 Loop 2 RC Pipe 7 APR 1-4200 UT-0 Loop 2 RC Pipe 8 APR-1-4200 UT-0 Loop 2 RC Pipe 4DM APR-1-4200 UT-0 -45 Loop 2 RC Pipe SDM APR-1-4200 UT-0 Loop-2 RC Pipe 7 APR-1-4200 PT Loop-2 RC Pipe 15BC APR-1-4200 PT Loop-2 RC Pipe 21BC APR-1-4200 PT Loop-2 RC Pipe 4DM APR-1-4200 PT Loop-2 RC Pipe 9 APR-1-4200 PT Loop-2 RC Pipe SDM APR-1-4200 PT Loop-2RCPipe 8 APR-1-4200 PT R.C. Pump "C ' Seal Housing Bolting N/A APR-1-5110 VT R.C. Pump "C" Seal Housing Bolting 1239 APR-1-5110 MT/VT R.C. Pump "C" Bolts 1199 APR-1-5110 MT/VT -

R.C. Pump "C" Bolts 1209 APR-1-5110 MT/VT R.C. Pump "C" Bolts 965 APR-1-5110 MT/VT R.C. Pump "C" Bolts 2068 APR-1-5110 MT/VT R.C. Pump "C" Bolts 1269 APR-1-5110 MT/VT R.,C. Pump "C" Bolts 1224 APR-1-5110 MT/VT In this area of inspection, no violations or deviations were identified.

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