IR 05000424/1987036
| ML20234D123 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/23/1987 |
| From: | Blake J, Hallstrom G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20234D104 | List: |
| References | |
| 50-424-87-36, 50-425-87-25, NUDOCS 8707070107 | |
| Download: ML20234D123 (9) | |
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l p REGu UNITED STATES g
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'o NUCLEAR REGULATORY COMMISSION 8Yf REGION 11
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. 2 ATLANTA, GEORGI A 30323 101 MARIETTA STRE ET. N.W.
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Report Nos.
50-424/87-36 and 50-425/87-25
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Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.
50-424 and 50-425 License Nos.:
NPF-61 and CPPR-109 Facility Name:
Vogtle 1 and 2 Inspection n ct d:
yr25-28, 1987 b <;23 $ 7 Inspecto.
.1skrpm Da 5ig ed
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' M 3 87 Approved b u,
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BTake, Section Chief Date Signed n 'neering Branch is ision of Reactor Safety SUMMARY Scope: This routine, announced inspection was in the areas of licensee actions on previous enforcement natters (units 1 and 2), housekeeping (unit 2), materials control (unit 2), and welding activities associated with safety-related piping i
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Results:
No violations or deviations were identified.
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DjO 07 870630 G
CK 05000424 PDR
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REPORT DETAILS l
1.
Persons Contacted
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Licensee Employees
- P. D. Rice. Vice President and Vogtle Project Director
- R.
H. Pinson, Vice President, Construction
- C. W. Hayes, Project Quality Assurance (QA) Manager
- E. D. Groover,.QA Site Manager, Construction
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- G. A. McCarley, Project Compliance Coordinator i
D. M. Fiquett, Unit II Field Construction Manager
- J. E. Sanders, Assistant Project Construction Manager, Unit II-
- R. Hollands, Electrical Field Office Coordinator, Compliance W. C. Ramsey, Project Engineering Manager A. M. Harrelson, Electrica? Discipline Manager Other licensee en'pl oyee s contacted included construction craftsmen, engineers, technicians, mechanics, and office personnel.
Other Organizations
- C Garrett, Ogelthorpe Power Corporation, Construction Engineer D. W. Strohman, Bechtel Power Corporation (BPC), Project Quality Assurance Engineer R. Valdez, BPC QA Engineer
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S. Pietrzyk, BPC Field Project Electrical Engineer B. L. Edwards, Pullman Power Products (PPP), Resident Construction Manager J. E. Miller, PPP, QA Manager T. C. Clark, PPP, Assistant QA Manager R. Pauis, PPP, QA-Welding Supervisor
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J. Agold, Southern Company Services (SCS), Preservice/ Inservice Inspection Supervisor
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- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on Mayf 28,1987, with those persons indicated in paragraph 1 above. The inspector described the
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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 ~
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to or reviewed by the inspector during this inspection.
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Licensee Action on Previous Er.forcement Matters a.
(Closed) Uriresolved Item - 424/85-07-02. Preservice Inspection Program Procedures
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This item concerned establishment of Preservice. Inspection
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procedures to defineiPSI responsibilities, audits, control of materials, and indoctrination / training of vendor PSI personnel. - NRC concerns had been previously addressed in a June 1985 GPC/SCS procedure k
( ADM-U-127). but this item had. remained open pending further NRC review.
(Inspection. Report No. 50-424/85-25)- Cogni.zant Licensee
_ personnel informed the inspector that ADM-V-127 -had been superseded on' December 15, 1986, by' GPC _ procedure 09.80-1, Plant Vogtle-Site l
. Responsibilities for ITE _ activities.
TheLinspector. reviewed proce-dure 09.80-1 and concluded that the procedure was adequate to resolve
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NRC concerns.
This item is considered closed.
b.
btosed)
Violation 424/87-14-01, Failure to Assure Adequate Protection of V;tal Equipment GPC's letter of response dated May 8,.1987, has been reviewed and j
determined to be acceptable by Region II. The. inspector examined the correctivo actions as stated in the response.
The inspector concluded _tnat GPC had determined the full extent of the subject violation, performed the necessary survey and^ followup actions to correct the subject conditions, and developed the necessary corrective actions intended to preclude the recurrence ' of similar circumstances.
The corrective actions identified in-the letter o.f response were implemented.
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(Liosed) Violation 425/87-05-01, Failure to Protect Permanent Plant Equipment J
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.j GPC's letter of response dated March 5,1987, has been reviewed and de'. ermined to be acceptable by Region II.
The inspector examined
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the corrective actions as stated in the response. 'The inspector R
concluded that GPC had determined the full ' extent of the subject
'f violaticn, performed the necessary survey an';. followup actions to i
correct the subject conditions, and developed the necessary correc-tive actions intended to preclude the recurrences of_-similar circumstances.
The corrective actions identified in -the letter of
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responses were implemented.
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(Closed) Violation 425/87-10-02,__ Failure _ to Follow Procedures for
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Control of Welding GPC's. letter of response dated May 13,-1987, has been-reviewed-and determined.to be acceptable by Region II.
The inspector examined the ccrrective 'c4 tons as stated in-the response.
The - i nspector
~y concluded +% v had determined the: full extent of 1the subject'
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violatiom cf, ad.the __necessary. survey _ and followup - actions' to i
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correct the subject conditions, and developed the necessary corrective actions intended to preclude.the recurrence. of 'similar circumstances. The corrective actions identified in the letter of response were implemented.
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(Closed) Violatio'n 425/87-10-03, Feilure to Accomplish Adequate.
Corrective Action GPC's letter of response dated May 13, 1987, has been. reviewed and determined to be acceptable by Region II.
The inspector examined the corrective actions as stated in the response.
The inspector concluded that GPC had determined the full extent of.the subject violation, performed the necessary survey and followup actions: to corrective actions intended to preclude the recurrence 'of similar circumstances. The corrective actions identified in the letter of
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response were implemented.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort Housekeeping (548348), Material Identification and Control (429028), and Material Control (429408)
The inspector conducted a general inspection on Unit 2 containment and the reactor auxiliary building to observe activities such as housekeeping, material identification and control; material control, and storage.
Within the areas examined, no violations or deviations 'were identified.
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6.
Safety-Related Piping (Unit 2)
The inspector examined welding and nonwelding actisities. for safety-related piping to determine whether applicable code and procedure requirements were being met.
The applicable code for safety-relat'ed piping is the ASME Boiler and Pressure Vessel Code,Section III, 1977 Edition with Addenda through W77, a.
Review of Nonwelding Quality Records (49065)
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The inspector selected various safety-related piping components.
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pipe, fittings and welded-in components) for review of pertinent records to determine conformance with procurement,. storage and installation specifications and QA/QA site procedures.
Records of the following. items were selected-for review to ascertain-whether they (racords) were in conformance with applicable requirements relative to the following areas:
material test
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reports / certifications;. vendor supplied NDE reports; Nuclear.SteamL j.
Service Supply. quality release; site receipt inspections; storage;-
installation; vendor nonconformance reports.
Item Heat / Control No-System
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24" dia SS 472432 Containment Air Cooling Sched 40 pipe 1" dia CS 013B Main Steam RD HD plug-(Header Assembly)'
1" dia CS
.SP No. 2-1301 Main. Steam 6000#.Sockolet 105-S-02 (Header Assembly)
h" dia SS 474744 Main Steam sched 80. Pipe
- " dia SS Coupling ENE Main Steam 1" dia SS.
466422 Radiation Monitoring Sched 40 Pipe Containment Penetration S/N 1153 Radiation Monitoring No. 13A h" dia SS 470320 Main Steam Sched 80 Pipe (Blowdown Samples)
Containment Penetration S/N 1140 Main Steam No. 12 (Blowdown Sample)
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2" dia. CS W12253 Auxil ia ry. Component Sched 160 Pipe Cooling Water 2" dia. CS RISK Auxiliary Component 6000# 90 ell Cooling Water lh" dia. CS D27320 Essential Chilled Water Sched 80 Pipe.
Ih" dia. CS S/N.H339AAR Essential Chilled Water 1500# Gate Valve 2" x 1" SS M7747 Nuclear Service SWAGE FTG Cooling Water.
j 1" dia SS S/N'BG313 Nuclear-Service 1500# Globe Valve
' Cooling Water.
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Within the areas inspected, no violations' or.. deviations were
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identified.
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Welding Activities (1) Production Welding (55050)
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The inspector observed in process welding activities of safety-related piping field welds inside ' containment and the reactor auxilia ry building as described below to ' determine. whether applicable code and procedure requirements were being met.
The bel'ow listed welds were examined in process to verify work conducted in accordance with traveler, welder identification and-location, welding procedures, WPS assignments, welding technique and sequence, materials identity weld geometry, fit-up; temporary.
attachments, gas purging, preheat, electrical' characteristics, shielding gas, welding equipment condition, interpass tempera-ture, interpass cleaning, process control systems,' qualifications q
of inspection personnel, and weld history 1 records.
2V4-1501-035-01 R/1 035-W-03A 2h" Hot Pass 2K5-1301-002-01 R/7 105-W-103A 1"
Fill Pass 2K4-1301-068-01 R/1 068-W-122 h"
Final Weld *
2K4-1609-019-01 R/0 019-W-110 1"
Root Pass
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2K4-1301-102-02 R/1 102-W-116 Fill Pass 2J4-1217-150-01 R/0 150-W-718 2"
Fill Pass 2K3-1592-024-01 R/0 024-W-126 1h" Fill Pass 2K3-1202-155-01 R/2 155-W-125 1"
Fit-up, Tack, Root' Pass
- Welding completed but not QC inspected.
Completed visual examination of final weld.
The following inspector qualification status records and QA/QC Inspector Qualification / Certification records were reviewed relative to inspection of the weld joints listed below.
Inspector Type of Certification EEA-PPP VT-II BFP-PPP VT-II KL-PPP VT-II WPK-PPP VT-II RJG-PPP VT-II l
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6-h (2) Welding Procedures
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Welding Procedure Specifications-(WPS) applicable to the weld joints listed in paragraph 6.b,(1) were selected for review and comparison with the ASME code as follows:
Procedure Qualification.
WPS Process PQR Reports
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24-111/1-8-KI-12 GTAW/SMAW 110, 120,-133 (3/24/84)
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27-111/1-8-0B-12 GTAW/SMAW-110, 125, 132, 133 (10/13'W)
38-111/1 d-KI-1 GTAW 120,.121 (12/6/85)
IT10-111/1-1-0B-1 GTAW 045, 055A, 055B (8/15/84)
IT12-111/1-1-08-12 GTAW/SMAW 045, 034A, 055A, (4/17/85)-
055B,~058 1/ GTAW - Gas Tungsten. Arc Welding 2/ SMAW - Shielded Metal' Arc Welding The above WPSs and 'their supporting. Procedure Qualification-Records (PQRs) were reviewed to ascertain whether essential.,
supplementary and/or. nonessential variables,; including thermal-treatment, were consistent with Code.' requirements; whether the -
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WPSs were properly qualified and' their1 supporting-PQRs were,
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accurate and retrievable; whether all mechanical tests had been
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performed and the results met the minimum requirements; whether j
the PQRs had been reviewed and certified.by appropriate contractor / licensee personnel and whether essential were noted,
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WPSs are qualified in accordance with' ASME Section IX, the latest edition and addenda at the time of. qualification.
(3) Welder Performance Qualification The inspector reviewed the PPP program for qualification of welders and welding operators for compliance with QA procedures and ASME Code requirements.
The following welder qualification status records an'd " Records 1!
of Performance Qualification Test'_' were reviewed relative to the
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i weld joints-listed in paragraph 6.b.(1).
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'l Welder Symbol WPS DT 24-111/1-8-KI-12 AX5 IT10-111/1-1-0B-1 ZH1 38-111/1-8-KI-1 NY 27-111/1-8-08-12 CY-1 27-111/1-8-0B-12 i
CH-1 IT-12-111/1-1-0B-12 l
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JD-2 IT-10-111/1-1-0B-1
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FZ-3-38-111/1-8-KI-1-
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(4) Welding Filler Material Control
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The inspector reviewed the PPP program for control of welding materials to determine whether materials were being purchased, j
accepted, stored and handled in accordance with QA procedures
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and applicabie code requirements.
The'following specific area were examined.
Purchasing; receiving, storing, and distribution and
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handling procedures; material identification; and inspection of welding materials issuing stations.
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Welding material purchasing and receiving records for the '
following material applicable to' the weld _ joints listed in pa ragraph 6.b.(1) were reviewed for conformance with applicable procedures and code requirements.
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Ty_pe Size Heat, Lot Batch /No.
IN308L 1/8" x 5/32" K-Insert 4894T308L ER308L 1/16" x 36" 26245 ER308L 3/32" x 36" P5474
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ER308L 1/8" x 36" P0443
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E705-2 3/32" x 36" F8524 E70S-2 1/8" x 36" F7164 E7018 3/32" x 14" MM084 Within the area inspected, no violations or deviations were identified.
7.
Previously Identified Inspector Followup Items
_ Closed) Inspector Followup Item (424/86-120-01; 425/86-56-01)
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Adequacy of Upper Tier Procedure For Design: Change Notices.
This item concerned discrepancies in section C4 of the-upper-tier controlling procedure for the Vogtle project (the BPC) Project-Reference Manual).
Paragraph 4.B of Section C4, Rev. 3 (10/28/86)
established requirements for Drawing Change Notices. (DCNs) _without-including specifies.of the authority / responsibility for the necessary
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t approvals involved.
During an earlier inspection the inspector.had established that specifics regarding DCN approvals had been included in earlier revisions of the PRM but were inadvertently omitted during
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major revisions which occurred during 1984.
However, the necessary.
controls had been in place in the interim since personnel involved had used non-formal " approval check-off" lists. to complete daily.
work. These lists had been examined by readiness review teams during.
assessment of DCNs and no major discrepancies had been identified.
This item was opened pending correction of Section C4 and Licensee examination of the ;omplete PRM to ensure that similar discrepancies did not exist in other areas.
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The inspector reviewed internal Licensee correspondence (BPC File
.No. X7BD44, Log:
PFE-13800) which established procedural and scheduling requirements for the PRM review..The review had been expanded. to include assessment of-PRM revisions necessary to implement GPC Nuclear Operations interface requirements and changes to reflect " lessons learned" from Unit construction.
Cognizant Licensee personnel informed the inspector that two sections of the PRM (C4-Bechtel Drawings and C9-Design Calculations) had required
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correction to include authority / responsibility pecifics. Twenty-two
additional sectio'ns had required revisions aue-to Operations interface and lessons learned program enhancements.. The inspector completed a review of the latest revision of PRM Sections C4 (Bechtel Drawings), C9 (Design Calculations), C 17 (Field: Change Requests) and Appendix 2
.Section 19 (Greenlining). The inspector concluded that corrections were sufficient to resolve NRC concern. This item is considered closed, b.
(0 pen) Inspector Followup Item (425/87-10-01):. Revision of Bechtel Specification X3AR01.Section E8-Raceway Systems
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This item concerns need for improvement of upper-tier Bechtel Specification X3AR01 Section E8.
During an earlier inspection the inspector had noted that over 30 FCRs/DCNs were outstanding for the current (Revision 23) specification.
This situation caused undue complexity in the field and also caused a lack of conformance.to PRM requirements for revision of specifications / drawings (Section -C-26).
This problem had been previously identified by a licensee audit (CAR No. VS-87-209) and completion of corrective action was not complete.
This 4 tem was opened pending NRC review of ?AR corrective actions
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and Revision 24 of Section E8.
The inspector ' reviewed the latest-revision of Section E8 (Revision 25 issued May 7,1987) and noted
.that eleven FCRs/CSCNs were' applicable to the new revision.
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Cognizant licensee personnel responded that the present situation i
was an improvement relative to the complexity of field use of Section E8.
However, the majority of outstanding FCRs/CSNCs were the result of scheduled implementation of " lessons learned" and additional changes would be required.
Implementation of " lessons learned" is anticipated by September 1987.
This item. remains. open pending further NRC review.
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