IR 05000424/1987066

From kanterella
Jump to navigation Jump to search
Insp Repts 50-424/87-66 & 50-425/87-47 on 871116-20.No Violation or Deviation Noted.Major Areas Inspected:Welding & Nonwelding Activities Re Containment Spray Piping Supports, Preservice Insp & HVAC Quality Concerns
ML20238D138
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 12/18/1987
From: Blake J, Hallstrom G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20238D134 List:
References
50-424-87-66, 50-425-87-47, NUDOCS 8801040119
Download: ML20238D138 (12)
v • d • e


Text

_--.

l .

UNITED STATES g MUCLEAR REGULATORY COMMISSION

['$-pm 8touq'o,$

-

'

REGION 11 j 101 MARIETTA STRE ET, $

  • r ATLANTA, GEORGI A 30323

%...../

Report Nos.: 50-424/87-66 and 50-425/87-47 Licensee: Georgia Power Company P. O. Box 4645 Atlanta, GA 30302 Docket.Nos.: 50-424 and 50-425 License Nos.: NPF-61 and CPPR-109 l

Facility Name: Vogtle 1 and 2 Inspection Condu ed: November 16-20, 1987 Inspector: MM G. A. HaTl strom Whm /Af/.)~/8 7 Date Signed Accompanying Per 1: M. Glasman Blake (November 19 & 20)

Approved by: ./ -

/'k!/k!67 J. lake, Chief Date Signed M te als and Processes Secticn ng neering Branch ivision of Reactor Safety SUMMARY Scope: This routine, unannounced inspection was in the areas of welding and non-welding activities associated with Containment Spray Piping Supports ,

(Unit 2), Preservice Inspection (Unit 2), Housekeeping and Materials Control (Unit 2) welding activites associated with Reactor Head Ven'. Lines (Units I and 2), HVAC Quailty Concerns (Units 1 and 2), and licensee identified 50.55-(e) items (Unit 2)

Results: No violations or deviations were identifie <

.

8801040119 871223 PDR ADOCK 05000424 0 DCD

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ -

_ . _ _ _ _ _ _ _

_ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ -___

,

.

8 .

.

.

REPORT DETAILS Persons Contacted Licensee Employees

  • D. Rice, Vice President and Vogtle Project Director
  • H. Pinson, Vice President, Construction
  • W. Hayes, Project Quality Assurance (QA) Manager
  • D. Groover, QA Site Manager, Construction .
  • G. R. Frederick, QA Site Manager, Operations
  • M. Bellamy, Plant Manager, Operations
  • J. E. Sanders, Assistant Project Manager
  • W. F. Kitchens, Operations Manager

.

  • J. E. Swartzwelder, Manager Nuclear Safety and Compliance (NSAC),

Operations

  • R. M. Odom, NSAC Supervisor, Operations
  • T. Greene, Plant Support. Manager, Operations
  • A. L. Mosbaugh, Assistant Plant Support Manager, Operations
  • N. Lankford, Assistant Manager of Quality Control (QC), Construction
  • J. J. Gilmartin, Mechanical Staff Engineer, Construction
  • L. N. Brooks, Civil Discipline Manager, Construction C. F. Meyer, Operations Supervisor E. Kozinski, Human Performance Evaluation Systems (HPES), Operations H. Sinclair, Mechanical Piping Engineer, Construction L. Prill, NSAC Operations Assessment Program, Operations K. Pointer, NSAC Operations Assessment Program, Operations
  • A. McCorley, Project Compliance Coordinator, Construction
  • A. W. Harelson, Electrical Discipline Manager, Construction W. McConnel, Mechanical Construction Coordinator Other licensee employees contacted included construction craftsmen, engineers, technicians, mechanics, and office personne Other Organizations
  • C. Ramsey, Southern Company Services (SCS), Project Engineering Manager J. M. Agold, SCS, Preservice Inspection Coordinator
  • G. Kecie SCS, NDE-Level III Examiner i B. Reed, Westinghouse, Project Welding Engineer M. E. Maryck, Westinghouse, Vogtle Structural Analysis Mobile Unit (VSAMU), Manager .

M. J. Beer, Westinghouse, VSAMU Technical Assistant  !

L. Rale, Westinghouse, QA Engineer

  • D. W. Strohman, Bechtel Power Corporation (BPC), Project QA Engineers R. W. Braddy, BPC, Mechanical Core Discipline Project Engineer

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

.__ . _ _ .__ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _

L2

'.

.-

'

,

..

D. L. Carlson, BPC, Codes Engineer R. Stone, BPC, Codes Engineer W. G. Uhouse, BPC, Design Engineering "N" Stamp D.'C. Capito, BPC, Plant Design Group Supervisor N. J. Thakus, BPC, Plant Design Engineer H. Derow, BPC, Plant Design Engineer

  • B. L. Edwards, Pullman Power Products (PPP), Resident Construction Manager
  • J. E. Miller, PPP, QA Manager D. Kelly, PPP, Welding Engineer K. E. Wiess, PPP, Chief Engineer J. Pinell, ASME Authorized Nuclear Inspector (ANI)
  • D Smith, Oglethorpe Power Corporation, Construction Engineer i NRC Resident Inspectors
  • Livermore, Senior Resident Inspector (Construction)

"J. Rogge, Senior Resident Inspector (Operations)

  • R. Schepens, Resident Inspector (Operations)
  • C. Burger, Resident Inspector (Operations)
  • Attended exit interview Exit Interview The inspection scope and findings were summarized on November 19, 1987 (Unit 2) and November 20, 1987 (Unit 1), with those persons indicated in paragraph I above. The inspector described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the licensee. The licensee did not identify-as proprietary any-of the materials provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters Licensee Actions on previous enforcement matters within the scope of this inspection were not complet . Unresolved Items Unresolved items were not identified during this inspectio . Independent Inspection Effort Housekeeping (54834B), Material Identification and Control (429028),

and Material Control (42940B)

The inspector conducted a general inspection on Unit 2 containment to observe activities such as housekeeping, material identification and '

control; material centrol, and storag _ _ __ - __ _____--___ - ________- _____ _-

' '

. .

-

.

.

3 HVAC Quality Concern RII-86-A-0302 (Units 1 and 2)

The inspector conducted a Re-examination (See NRC Inspection Report No. 50-424/87-31) of the subject concerns in the following areas:

-

Use of 308 Versus 309 Welding Materials The inspector reviewed documentation attached to audit N .

,

P/K-F-P018 which supports clarification of BPC specification paragraphs H.3.4.H. and H.3.4.I to the effect that either 308 or-

, 309 weld metals may be used to join austenitic stainless to .

austenitic stainless base metal This interpretation was supported by BPC personne Lack of Re-examination of Stainless Welds Af ter Revision of Wel, Procedures to Include a 300 F Interpass Temperature Cognizant licensee personnel explained that the stainless welds involved joined light gage HVAC ducts and were generally from one side. The occasional weld required on the back side could not be made quick enough to violate the interpass temperature due to the duct geometry involved. The inspector concurred that there was negligible probability of violating the required interpass temperature contro Improper Implementation of a Desk Top Procedure This concern could not be substantiate The inspector concluded that the significance of the issues involved did not warrant further NRC activity and this item is considered

. closed, Within the areas examined, no violations or deviations were identifie . Safety-Related Supports - (Unit 2)

The inspector examined welding and non welding activities associated with Unit 2 Containment Spray Piping Supports to determine whether implementing procedures were appropriate and adequate to assure that these activities e,re controlled and performed according to NRC requirements and FSAR cocadtment s and whether quality records conformed with established prxedure and reflected work accomplishment consistent with requirement The applicable code is the AWS Structural Welding Code D1.1-197 I Non-Welding Activities - Verification Program (1) The below listed procedures were reviewed to determine whether j

'

procedures are appropriate and adequate to ensure control of the as-built verification progra J l

. - - - . _ -_ _ _ _ o

--_-_ ___

,

. .-

-

.

4 l

Procedure N Title PPP-X-18, dated 7/25/86 Field Welding Inspection j PPP-X-24, dated 5/15/86 Procedure for As-Builting Piping PCN #1, dated 9/17/86 Systems and Related Component PPP-IX-50, dated 7/8/86 Pipe Support Field Installation and Fabrication Procedure During the above review, the inspector noted that Procedure X-24 did not require re-verification of weld sizes and lengths. The inspector was informed by cognizant licensee and BPC personnel of elements in the X-24 re-verification program which satisfy IEB 79-14 and 79-02 requirement BPC personnel further expressed confidence that adequate weld sizes and lengths were assured by the final QC inspection and acceptance ' conducted by PPP during installation of each suppor (The inspector noted that a sample of the welds on the supports listed below had been independently examined by the NRC during this inspection with no undersized welds identified).

(2) The below listed supports were examined in the area of dynamic pipe supports and components supports structures that had been

! QC final inspecte Documentation for the installation, inspection and design were reviewed; the hangers were reinspected with the assistance of QA/QC inspectors; and the results discussed with the QA/QC inspectors to determine the effectiveness of the re-verification progra Support N V2-1206-054-H025 V2-1206-054-H023 V2-1206-013-H022 V2-1206-013-H021 V2-1206-007-H037 The above supports were reinspected against their detail drawings for configuration, identification, fastener / inchor installation, clearances, member size, welds and damage / protectio Within the areas examined, no violations or deviations were identifie i Welding Activities - (55100)

The inspector examined the majority (six minimum) of the required 5/16" fillet welds on the supports listed in paragraph 6.a.(2)

relative to the following: location, length, size and shape; weld surface finish and appearance; transitions between different wall

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ __ i

_ _ _ _ . . . . . . . . . _ . . . . . .

. .

.

W

l thickness; well reinforcement height and appearance; joint configura-tions on permanent attachments and structural supports; removal of temporary attachments, arc strikes and weld spatter; finish grinding or machining of weld surface, surface finish and absence of wall thinning; surface defects, crac'es, laps, lack of penetration, lack of fusion, porosity, slag, oxide fi'im and undercut exceeding prescribed - - -

limit Within the areas examined, no violations or deviations were identifie . Preservice Inspection (PSI) Unit 2 l The inspector examined documents and records as indicated below to determine whether PSI was being conducted in accordance with applicable procedures, regulatory requirements, and licensee commitment _ __

The Unit 2 PSI is being performed to the ASME Code Section XI, 1983 Edition through Summer 1983 Addenda, with the exception of the mechanized examination of the reactor pressure vessel (RPV) which was performed by Combustion Engineering. The mechanized RPV examinations were performed to the requirements of the ASME Code, 1980 Edition through Winter 1981 Addend SCS has been contracted by Georgia Power Company (GPC) to perform the required Code examinations as delineated in Vogtle Electric Generating Plant (VEGP) ISP-P-009 Preservice Plan, Revision Inspection Program B will be utilized at Vogtle Unit 2 in accordance 'e;ith ASME Section XI paragraph IWA-240 This program implements the requirements of the VEGP Preservice Inspection Program, detailed in Manual ISI-P-010, Revision 2. SCS has subcontracted Lambert MacGill and Thomas (LMT) to furnish Qualified examiners for this inspector effort, PSI Programmatic Review (73051)

l The inspector reviewed the below listed documents relating to the I licensee's PSI program (Plan) in the areas of program approval; QA program requirements including organizational structure, audit requirements, 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; cuality records; inspection scope; inspection intervals; personnel qualifi-cations; and NDE records, including provisions for storag ISI-P-009, Rev. 1 PSI Plan - Unit 2 ISI-P-010, Rev. 2 PSI Program - Unit 2 l

l

.

... _ -_

.

- - - - - - - _ _ _ - - - - - _ _ _ _ - . _ _ _ _ _ . _ _ _ _ .

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - . - _ _ _ - - - - - - - - . _ _ _ _ _ _ _ _ - - - - - - - - - . _ _ _ _

,

. .

-

.

.

.

SCS Inspection, Testing and Engineering Policy and Procedures 09.1-4 Temporary Procedures - Preparation, Approval, Distribution 09.1-50 Request for Deviation 09.2-1 Indoctrination and Training 09.3-50 Outage Planning / Control Revision 09.3-51 Program - Preparation and Revision 09.3-52 Examination and Testing Plans - Preparation and Revision 09.4-5 Drawings - Preparation and Approval 09.4-50 Basic Calibration Blocks - Design, Fabrication Verification 09.5-50 Inspection, Testing, and Engineering Files 09.5-51 Final Reports - Preparation, Approval, and Submittal 09.5-100 Quality Assurance Record Control 09.6-51 Control of Contractor Services 09.7-0 Quality Assurance 09.7-50 Nonconformance Item 09.8-0 Nuclear Safety and Reporting 09.8-50 Relief Requests - Preparation and Tracking

'

09.50-1 On-Site Data Review 09.50-2 On-Site Data Control 09.50-3 On-Site Control and Insurance of NDE Documents and Equipment I 09.50-4 Indication Notification 09.80-0 Plant Vogtle - ITE Administrative Procedures 09.80-1 Plant Vogtle - Site Responsibilities for ITE Activities

____--_________ -

..

. .

,

r i .

LMT Procedure QA-6, Rev.19, Qualification and Certification of NDE and Visual Examination Personnel b. Review of Procedures - (73052)

The inspector reviewed the PSI procedures indicated below to determine whether the procedures were consistent with regulatory requirements and licensee commitment (1) The following SCS procedures were reviewed in the areas of procedure approval, requirements for qualification of NDE personnel and compilation of required records:

-

AUX-H/F/V-300, Rev. 4, Procedure (Written Practice) for Qualification and Certification of Nondestructive Examination Personnel

-

UT-V-404, Rev. 1, Manual Ultrasonic Examination of Full-Penetration Welds

-

MT-V-505, Rev. 1, Dry Power Magnetic Particle Examination:

Yoke Method

-

PT-V-605, Rev.1, Color Contrast, Solvent Removable Liquid Penetrant Examination Procedure

-

VT-V-715, Rev. 1, Visual Examination (VT-1)

(2) In addition to the review above, procedure UT-V-404 was reviewed in the areas of compilation of required records and procedure content relative to: extent of coverage including beam angles and scanning techniques calibration requirements, search units, distance amplitude correction curve (DAC), sensitivity levels for evaluation and recording indications, and acceptance standard (3) Procedure PT-V-605 was reviewed in the areas of compilation of required records and procedure technical content relative to:

method consistent with ASME Code, specification of brand names of penetrant materials, specification of limits for sulfur and total halogens for materials, pre examination surf ace prepara-tion, minimum drying time following surface cleaning. penetrant application and penetration time, temperature requirements, solvent removal, method of surface drying, type of developer and method of application examination technique, technique for evaluations, acceptance standard, and requalification requi' ament _ _ - _ _ - _ - -___- _ -

.; 1

. .

\ .

8 -

.

(4) Procedure MT-V-505 was reviewed in the areas of compilation of required records and, procedure technical content relative to:

examination method, surface preparation, use of color contrast particles, examination directions and overlap, pole spacing and acceptance criteri Within the areas examined, no violations or deviations were identifie . Reactor Coolant Pressure Boundary Piping (Units 1 and 2) (55050)

.

The inspector examined welding activities for Reactor Head Vent Line Welds 055-W-136 (Unit 2) and 055-W-141 (Unit 1) to determined whether applicable code and procedure requirements were being met. Welds 055-W-136 and 141 join the one inch schedule 160 inconnel (SB-167) vent line pipe to its i first isolation valve (a 3000# 316 Stainless angle globe valve) and are l- located inside the upper head shroud. The applicable Code is the ASME Boiler and Pressure Vessel Code,Section III,1977 Edition with Addenda through W7 Production Welding Unit 2 Reactor Head vent Weld 055-W-136 was examined in process to

.

verify work conducted in accordance with traveler, welder identifi-l cation and location, welding procedures, WPS assignment, welding technique and sequence, materials identity, weld geometry, fit-up; temporary attachments, gas, purging, preheat, electrical charac-teristics, shielding gas, welding equipment condition, interpass temperature, interpass cleaning, process control systems, qualifica-tions of inspection personnel, and weld history record ISO Weld Size Status 2VI-1201-055-01 R/2 055-W-136 1" Fit-up Tacks and Root Pass The following inspector qualification status records and QA/QC Inspector C' qualification / Certification records were reviewed relative to inspection of the weld joints listed abov Inspector Type of Certification EEA-PPP VT-II Welder Performance Qualification The inspector reviewed the PPP program for qualification of welders and welding operators for compliance with QA procedures and ASME Code requirement _____ -

_ _ _ _ _ _ _ _ - _-

. :

,

.

The following welder qualification status records and Records of Performance Qualification Test" were reviewea relative to weld 055-W-13 Welder Symbol WP_S

_

R1 84-111/1-8/1-013-12-F43 c. Welding Procedure Specifications The Welding Procedure Specifications (WPS) applicable to weld 055-W-136 was selected for review and comparison with the ASME Code as follows:

Procedure Qualifications WPS Process PQR Reports 356-111/1-43/8-0131 1/GTAW 378 1/GTAW GSC Tungsten Arc Welding The above WPS and its supporting Procedure Qualification Record (PQP)

were reviewed to ascertain whether essential, supplementary and/or nonessential variables, including thermal treatment, were consistent with Code requirements; whether the WPSs were properly qualified and their supporting PQRs were accurate and retrievable; whether all mechanical tests had been performed and the results met the minimum requirements; whether the PQRs had been reviewed and certified by approprf ate personnel and whether any revisions and/or changes to nonessential variables were noted. WPSs are qualified in accordance with ASME Section IX, the latest edition and addenda at the time of qualificatio During the above examination, the inspector noted that there appeared to be a problem establishing the qualification status of the welder involved. After some discussion it was determined that the welder (RI) had been qualified to a special WPS (84-111/18/1-0B-12-F43) in order to complete the same weld (055-W-141) for Unit 1, but that WPS 356-111/1-43/8-013-1 had been issued on October 26, 1987, in order to l completed the weld on Unit 2. The inspector requested clarification '

as to the need for a new WPS for Unit 2, determination as to the  !

welder's qualification status, and complete documentation associated i with Unit I weld 055-W-14 Cognizant Licensee personnel informed the inspector that Unit I weld

,

055-W-141 had initially required repair due to cracking since the weld had been attempted using ER 308L filler metal. This occurred due I to incorrect identification of the reactor head vent pipe as

! Stainless (SA 312 Gr 304L) rather than inconel (SB-167). PPP DR

_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _L

_ _ _ - _ - . _ _ _ _ _ _ _ _ _ _ - _

--

l'. :

l' ;

.

.

l

!

l No.12203 was issued to control the repair which required removing all ER 308L filler (verified by an acid-etch inspection), repair of the weld areas, and rewelding. WPS. 84-111/1 was written for the purpose of welding P1 material (carbon steel) to P-8 material (stainless steel) using an intermediate layer of inconel butter (F43)

and inconel filler metal. Use of the WPS was considered justified since ASME Section IX under - QW 194 considers F43 weld deposits (inconel weld) to be equivalent to P43 (inconel) base metals for procedure qualification. However, some time after Unit I was welded, the licensee received a response to a request for a code interpretation (Code Interpretation IX-86-18) which did not agree-

'

that F43 was equivalent to P43 for procedure qualificatio Therefore, PQR 378 using inconel baseplate was completed October 28, 1987, and WPS 356-111/1 issued to prevent requiring another engineering disposition for Unit The inspector reviewed the complete supporting documentation for Unit 1 Weld 055-W-141 and noted the following:

The essential welding parameters which would require requalifi-cation were were not changed between the WDSs (PQRs) involved (84-111/1 and 356-111/1)

PPD Dh No.12203 includes all necessary supporting information to establish complete removal of the initial ER 308L filler metal (acid-etch inspection report), use of qualified welder ,

(RI), inconel filler (ER NiCR-3, lot C492G382), and Westinghouse and ANI concurrence. The inspector informed cognizant licensee personnel that the engineering justification provided along with the PQR for Unit 2 (PQR 356-111/1) proved that the welding technique would provide a sound weld and therefore, was sufficient to satisfy NRC concer Within the areas inspected, no violations or deviations were identifie . Licensee Identified Items (92700) ,

,

Prior to the inspection, the licensee identified the following items under 10 CFR 50.55(e):

(Closed) Item 425/CDR 82-30, Sheared Pinion Keys in Limitorque Motor Operators On August 4, 1982, the USNRC was notified by Westinghou'e Electric '

Corporation via telephone that six sheared pinion keys had been discovered )

in Limitorque Model SB-0-25 motor operator This was confirmed in )

Westinghouse letter NS-EPR-2637, dated August 6,198 Additionally, I&E

!

- - _ - - - _ - - _ _ _ ]

I '

\ ..

.

l

?

1

'

..

l Information Notice 81-08 informed utilities that failures of sheared

'

pinion keys had been experienced in Limitorque Model SMB-4 motor operator Neither SB-0-25 or SMB-4 operators are used at Vogtl However,. on June 1,1983, the licensee informed Region II of a 50.55(e)

item concerning the potential for sheared pinion keys in Limitorque SMB-0-15 motor operators at VEGP. The final Report was submitted on June 11, 1986. The final report has been reviewed and determined to be acceptable by Region II. The inspector held discussions with responsible licensee representatives and reviewed supporting documents to verify that corrective actions have been completed. This-item is considered close i i

___________m________ _ _ . _ _ _ _ _ _ _

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000424/1987066&oldid=3110022"