IR 05000321/1986002: Difference between revisions

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{{Adams
{{Adams
| number = ML20137V029
| number = ML20199K968
| issue date = 02/06/1986
| issue date = 04/03/1986
| title = Insp Repts 50-321/86-02 & 50-366/86-02 on 860106-10. Violation Noted:Failure to Follow Procedure for Sign Off of Traveler Steps for Induction Heat Stress Improvement
| title = Ack Receipt of 860314 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/86-02 & 50-366/86-02.Implementation of Corrective Actions Will Be Examined During Future Insps
| author name = Blake J, Crowley B
| author name = Brownlee V
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =  
| addressee name = Kelly R
| addressee affiliation =  
| addressee affiliation = GEORGIA POWER CO.
| docket = 05000321, 05000366
| docket = 05000321, 05000366
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-321-86-02, 50-321-86-2, 50-366-86-02, 50-366-86-2, NUDOCS 8602190407
| document report number = NUDOCS 8604100263
| package number = ML20137U990
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 1
| page count = 9
}}
}}


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{{#Wiki_filter:p2 Keto  UNITED STATES
{{#Wiki_filter:9d\m m es a Georgia Power Company
/ ATTN: Mr. R. J. Kelly Executive Vice President P. O. Box 4545 Atlanta, GA 30302 Gentlemen:
SUBJECT: REPORT NO. 50-321/86-02 AND 50-366/86-02 Thank you for your response of March 14, 1986, to our Notice of Violation issued on February 13, 1936, concerning activities conducted at your Hatch facilit ,We have evaluated your response and found that it meets the requirements of 10 CFR 2.201. We will examine the implementation of your corrective actions during future inspection We appreciate your cooperation in this matte ,


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Sincerely, 1b Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects cc:d.T.Beckham,VicePresidentand
'o -
  /p>.GeneralManager-NuclearOperation
NUCLEAR REGULATORY COMMISslON
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n  REGION 11 g, j  101 MARIETTA STREET N.W.
 
* 's  ATLANTA, GEORGI A 30323
\...../
Report Nos.: 50-321/86-02 and 50-366/86-02 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.: 50-321 and 50-366  License Nos.: DPR-57 and NPF-5 Facility Name: Hatch 1 an! 2 Inspection Conducted: JanJary 6-10, 1986 Inspector: >,    .2 [ [ . Ttow  /  'Da e igned Approved b . .
0 8b . ite, Section Chief   'Date Signed En in ring Branch 0 vi on of Reactor Safety SUMMARY Scope: This routine, unannounced inspection entailed 41 inspector-hours on site in the areas of inservice inspection (Unit 1), nuclear welding (overlay welding and induction heat stress improvement) (Unit 1), and inspector followup items (Units 1 and 2)
Results: One violation was identified - failure to follow procedure for sign off of traveler steps for IHSI - paragraph 7.b.(2)(b).
 
8602190407 860213
$DR ADOCK 05000321    l PDR    l j
 
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J REPORT DETAILS Persons Contacted Licensee Employees
*H. C. Nix, Site General Manager
*T. V. Green, Deputy General Manager
*C. T. Jones, Manager of Engineering
*T. Setz, Manager of Maintenance
*J. L. Wilkes, Manager of Special Projects D. A. McCusker, Superintendent of Quality Control (QC)
*T. L. Elton, Supervisor of Regulatory Compliance
.
J. Hadden, QC Supervisor C. L. Powell, Senior Methods Training Specialist P. Norris, Senior Plant Engineer D. J. Vaughn, Senior QA Representative G. R. Brinson, Senior QC Specialist R. K. Godby, Plant Engineer
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Other licensee employees _ contacted included QC personnel, engineers, mechanics, security force members, and office personne Other Organizations T. N. Epps, Manager,'nspection,I Testing and Engineering, Southern Company Services (SCS)
A. G. Maze,. Supervisor of NDE, SCS
*J. M. Agold, Supervisor of Coordination and Documentation, SCS
*D. R. Barnes, ISI Site Coordinator, SCS
* A. Loftus, Lead Inspector - Level III, SCS W. J. McConaghy, Site ~ Project Manager Nutech Engineers, Inc. (Nutech)
J. H. Kessler, QA Site Supervisor, Nutech R. J. Benoit, Day Shift Supervisor, Nutech J. D. Frymyer, Welding Engineer, Welding Services, Inc. (WSI)
-
NRC Resident Inspectors
*P. Holmes-Ray, Senior Resident Inspector G. N. Nejfelt, Resident Inspector
* Attended exit interview Exit Interview The inspection scope and findings were summarized on January 10, 1986, with those persons indicated in paragraph 1 above. The inspector described the
< areas inspected and discussed in detail the inspection findings listed below. No dissenting comments were received from the license . - - - - . - . _ . - - - - - - .- --_ .-
 
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(0 pen) Violation 321/86-02-01, Failure to Follow Procedure for Signoff of Traveler Steps for IHSI - paragraph 7.b.(2)(b)
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio l 3. Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
 
4. Unresolved Items Unresolved items were not identified during the inspection.
 
5. Independent Inspection Effort (548348) (429028) (429408) (Unit 1)
The inspector conducted a general inspection of portions of the reactor and auxiliary buildings to observe activities such as housekeeping, material identification and control, and .naterial storag Within the areas inspected no violations or deviations were identified.
 
6. Inservice Inspection - Observation of Work and Work Activities (737530)
(Unit 1)
The inspector observed the ISI activities described below to determine whether these activities were being performed-in accordance with regulatory requirements and licensee procedures. The applicable code is the ASME Boiler and Pressure Vessel Code, Section XI,1980 Edition, W80 Addend (See RII Report 50-321/85-35 for a previous-inspection in this area).
 
As.noted in RII Report 50-321/85-35, the first 10 year. interval inspections are to be completed during the current outage. In addition, the licensee is inspecting 100% of the 130 stainless steel welds in the Reactor Recirculation (RECIRC), Residual Heat Removal (RHR), and Reactor Water Cleanup (RWCU) System Also, the licensee is performing Intergranular Stress Corrosion Cracking (IGSCC) mitigation techniques using weld overlays or Induction Heat Stress Improvement (IHSI) on welds not previously mitigated. T.3 observations detailed below pertains to inspections of the stainless steel weld Prior to IHSI, ultrasonic (UT) inspection was performed on an original sample of 22 stainless steel welds. As a result of finding indications, the sample was expanded to 49 welds (23 - 12" RECIRC, 2 - 27" RECIRC, 3 - 28" RECIRC and 21 - 6" RWCU). Seventeen of the 49 welds were found to contain reportable indications (2 - 28" RECIRC, 2 - 22" RECIRC, 9 - 12" RECIRC and 4
  - 6" RWCU). The decision was made to overlay weld 8 (4 - 12" RECIRC and 4-6" RWCU) of the 1 ,
 
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: Personnel qualification / certification records for two level I-UT, four
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level II-UT and 3 level II-PT examiners associated with the inspections of paragraphs b. and c. below were reviewe In addition to the SNT-TC-1A, qualification, the inspector verified that the examiners had completed the applicable qualification / demonstration at the EPRI NDE center. The level II examiners inspecting for IGSCC
,  .were required to have passed the recent EPRI NDE center course on
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IGSCC detection. The Level II examiners inspecting weld overlays were required to have satisfactorily completed the EPRI NDE Center practical exam portion of the EPRI NDE center weld overlay workshop. In addition, i
for overlay inspections, the inspector noted that a level III examiner with qualifications in IGSCC detection and sizing as well as overlay
;  inspections was involved in a supervisory or overview position on each shift.
 
, A portion of the in-process UT inspection, including calibration activities, was observed for the following welds:
I Weld  Weld Condition  Examination
<
1831-1RC-12AR-F-1 Post IHSI  45 1831-1RC-12E R-C-2 Overlay  0 1831-1RC-12BR-C-3 Overlay  0 1831-1RC-12BR-D-3 Overlay  0 1E11-1RHR-24B-R-13 Overlay *  0
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1E11-1RHR-208-D-3 Overlay  0
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1831-1RC-28A-4  Post IHSI  45 1831-1RC-28A-5  Post IHSI  45 IB31-1RC-12AR-F-2 Overlay  Creeping Wave 1831-1RC-12AR-F-3 Overlay  Creeping Wave 1813-1RC-12BR-E-3 Overlay  60 IB31-1RC-12BR-E-2 Overlay  60 1E11-1RHR-248-R-13 Overlay  60
 
.  * Demonstration of UDRPS equipment - exam not officia i  Tha inspections identified above for overlay welds were for overlay weins made during previous outages. There are a total of 23 previously
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madt overlays. For the current inspection the surface of these welds
:  ~had .len prepared by grinding and in some cases additional weldin ,
The aspections were compared with applicable procedures in the fol' awing areas:
'
I  (1) Availability of and compliance with approved NDE procedure (2) Use of knowledgeable NDE personnel
!
  (3) Use of NDE personnel qualified to the' proper level j  (4) Recording of inspection results j  (5) Type of apparatus used (6) Extent of coverage of weldment
 
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  (7) Calibration requirements (8) Search units (9) Beam angles DAC curves Reference level of monitoring discontinuities M- .id of demonstrating penetration (13) Ln,ts of evaluating and recording indications (14) Recording significant indications
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  (15) . Acceptance limits In-process liquid penetrant (PT) inspection of overlay- weld
;
IB31-1RC-28A-10 was observed and compared with the requirements of the applicable procedures and code in the following areas:
  (1) Availability of and compliance with approved NDE procedures (2) Use of knowledgeable NDE personnel (3) Use of NDE personnel qualified to the proper level t  (4) Recording of inspection results (5) Method consistent with procedure (6). Penetrant materials identified and consistent with ASME. Code (7) Certification ' of sulfur and halogen content for penetrant materials (8) Surface preparation (9) Drying time following surface cleaning (10) Penetrant application and penetration time
-  (11) Examination surface temperature 12) Penetrant removal 13) Drying of surface prior to developing 14) Developer type, application and time interval after penetrant removal (15) Time interval between developer and application and evaluation (16) Evaluation technique (17) Reporting examination results
, Certification records for the batches of inspection materials listed
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below, used for the inspections of paragraphs b. or. c. above, were reviewe '
{  UT Couplan Batch No. 42285 Penetrant  - Batch No. 828035 Cleaner  - Batch No. 85J058 Developer  - Batch No. 85H029 Within the areas inspected, no violations or deviations were identifie . Nuclear Welding (55050) (Unit 1)
    '
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The inspector examined the welding and IHSI activities detailed below -to determine whether applicable code and regulatory requirements were being me The applicable code is the ASME Boiler and Pressure Vessel Code,
*
Section XI, 1980 Edition with addenda through W8 .
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a. Welding Welding Services, Inc. (WSI) is the welding contractor'for overlay welding. The welding is being accomplished under the Georgia Power Company (GPC) QA program using GPC procedures. Welders are being qualified by GP (1) The inspector observed welding and reviewed associated records for the following in-process overlay welds:
,
1831-1RC-12AR-H-3 (Exi' ting Overlay surface improvement)
IB31-1RC-12AR-G-3 (New Overlay)
Th.? welding was observed to determine whether:
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Work was conducted in accordance with a document which coordinates and sequences operations, references procedures, established hold points, and provides for production and inspection approva Procedures, drawings, and other instructions were at the work station and readily availabl ,
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- WPS assignment was in accordance with applicable Code requirement Welding technique and sequence were specified and adhered to.
 
- Welding filler materials were the specified type and traceable to certification Weld joint geometry was in accordance with applicable
,
procedure and was inspected.
 
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  - Alignment of parts was as specifie Temporary attachments were by qualified welders in accordance with a qualified WP Preheat and interpass temperatures were in accordance with applicable procedure Welding technique was in acc6rdance with applicable procedure Electrodes were used in positions and with electrical
 
characteristics specified.
 
j  - Shielding gas-was in accordance with the welding procedur l i
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    -  Welding equipment was-in good condition and automatic welding equipment was calibrated.
 
i    -  Interpass cleaning was in accordance with applicable procedures.
 
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    -  Temporary attachments were removed in accordance with
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applicable procedure ,
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    -  Gas purging, if specified, was used in accordance with    '
I    applicable procedure.
 
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    - -Process control system had provisions for repairs.
 
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    -  Welders were qualified.
 
f    -  No peening performed on root and surface layer .(2) The inspector verified by review of qualification records (including RT film) that the following. welding. operators, who were
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welding on the welds listed in paragraph (1) above, were currently i -
qualified to weld under the applicable procedure.
 
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!    WSI-07 WSI-11 WSI-14 WSI-18 WSI-23
: IHSI IHSI was being performed on .99 (all welds not overlayed) stainless i  steel welds in the RECIRC, RHR, and RWCU system Nutech Engineers, i  Inc. was the contractor for the IHSI with Thompkins-Beckwith, Inc.
 
1  furnishing labor as a subcontractor to Nutech. The work was being
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accomplished under the Nutech QA Manua (1) Procedure Review
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The inspector reviewed the following documents controlling the IHSI:
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    -  Nutech "Quali ty Assurance Manual" including Quality Engineering Procedures (QEPs) - ,The QA manual was not
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reviewed in detail, but to the degree necessary to determine that QA requirements such as procedure issue and control, l
process control, qualification certification of personnel, i
control of inspections, control of nonconformances, and I
control of records was covered by procedures.
 
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C. Nix, Site General Manager ,
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W. E. Fornel, Site QA Supervisor d.. Gucwa, Manager, Nuclear Safety and Licensing bec: C Resident Inspector gh S. Jordan Executive Secretary  -
Nutech Procedure XGP-11-100 Revision 0, " Procedure for Induction Heating Stress Improvement at Edwin I. Hatch Nuclear Power Plant Unit 1".
Document Control Desk State of Georgia 8604100263 860403
 
  {DR ADOCK0500g1 l
(2) Observation of Work Activities and Review of Quality Records The inspectcr performed the following observatior.s/ reviews and compared the results with applicable procedures:
      :
Observed (a) Welds 1B31-1RC-28A-17 and 1831-1RC-22AM-1BC-1:
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in-process activities associated with IHSI (b) For the follcwing IHSI completed welds, the IHSI Weld Packages, including heat. charts, were reviewed:
    ]{$
IB31-1RC-12AR-G-1 1831-1RC-12AR-F-1 IB31-1RC-22AM-3BC-1 IB31-1RC-12AR-K-1 IB31-1RC-28A-16
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During review of the above records, the inspector noted that in some cases Nutech personnel signing traveler inspection steps were the same individuals as the individuals signing the traveler for performing the activities being inspecte This is in violation of paragraph 10.1.2 of the Nutech QA Manual which requires that " Inspection personnel shall be individuals other than those who performed or directly supervised the activity being inspection -- ". Further investigation revealed that the steps were being perfonned by Thompkins-Beckwith (T&B) craft personnel (Nutech's subcontractor) reporting to T&B craft supervision even though the steps were being signed off by Nutech. This is in violation of Nutech QEP 9-4, paragraph 2.5, which requires that subcontractors sign or stamp the traveler indicating that their described operation is completed. This failure to follow procedure is in violation of criterion V of Appendix B to 10 CFR 50 and is identified as item No. 321/86-02-01, Failure to Follow Procedure for Signoff of Traveler Steps for IHS (c) The inspector reviewed personnel training / certification records for personnel involved with the IHSI of the welds listed in paragraphs (a) and (b) above.
 
Within the areas inspected, no violations, except as noted in paragraph 7.b.(2)(b), or deviations were identifie .
8 Inspector Followup Items (92701B) (Units 1 and 2) (Closed) Inspector Followup Item 321/85-35-01, Revision of Procedures UT-H-400 and UT-H-470 to Specify Qualification to the EPRI Progra Deviation 001 to procedure UT-H-400 and Deviation 001 to procedure UT-H-470 have been issued to specify qualificacion to the EPRI NDE center program, (Closed) Inspector Followup Item 321/85-35-02, Revision of Procedure UT-H-408 for UT of Overlay Welds. Deviations 001, 002 and 003 have been issued to procedure UT-H-408 to clarify and amplify procedure requirements in the areas of personnel qualification, search Unit angles, surface finish and gain setting for scannin (Closed) Inspector Followup Item 321/85-35-03, Revision of MT Procedure MT-H-501 to Cover Measurement of Black Light Intensity. Deviation 001 has been issued to procedure MT-H-501 to .pecify requirements for measurement of black light intensity, (Closed) Inspector Followup Item 321, 366/85-26-02, Review of Revised PT Procedur Revision 0 to procedure 45QC-INS-006-05 has been issued to take the place of procedure 52IT-MNT-003-0. Procedure 45QC-INS-006-0S clarifies requirements in the areas of surface preparation, temperature requirements, and lighting requirement .
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Revision as of 04:14, 19 November 2020

Ack Receipt of 860314 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/86-02 & 50-366/86-02.Implementation of Corrective Actions Will Be Examined During Future Insps
ML20199K968
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/03/1986
From: Brownlee V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Kelly R
GEORGIA POWER CO.
References
NUDOCS 8604100263
Download: ML20199K968 (1)


Text

9d\m m es a Georgia Power Company

/ ATTN: Mr. R. J. Kelly Executive Vice President P. O. Box 4545 Atlanta, GA 30302 Gentlemen:

SUBJECT: REPORT NO. 50-321/86-02 AND 50-366/86-02 Thank you for your response of March 14, 1986, to our Notice of Violation issued on February 13, 1936, concerning activities conducted at your Hatch facilit ,We have evaluated your response and found that it meets the requirements of 10 CFR 2.201. We will examine the implementation of your corrective actions during future inspection We appreciate your cooperation in this matte ,

Sincerely, 1b Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects cc:d.T.Beckham,VicePresidentand

/p>.GeneralManager-NuclearOperation

.

C. Nix, Site General Manager ,

W. E. Fornel, Site QA Supervisor d.. Gucwa, Manager, Nuclear Safety and Licensing bec: C Resident Inspector gh S. Jordan Executive Secretary -

Document Control Desk State of Georgia 8604100263 860403

{DR ADOCK0500g1 l

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