IR 05000254/1988012
| ML20196H220 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/28/1988 |
| From: | Ward D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20196H164 | List: |
| References | |
| 50-254-88-12, 50-265-88-06, 50-265-88-6, NUDOCS 8807060111 | |
| Download: ML20196H220 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSIO."
REGION III
Reports No. 50-254/88012(DRS); 50-265/88006(DRS)
Docket Nos. 50-254; 50-265 Licenses No. OPR-29; DPR-30 Licensee:
Commonwealth Edison Conipany Post Office Box 767 Chicago, IL 60690 Facility Name:
Quad Cities Station, Units 1 and 2 Inspection At.
Quad Cities Site, Cordova, Illinois Inspection Conducted:
March 10, April 11-12, 18, 21,
-26-29, May 10, 17-18, June 1 and 20, 1988
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l,/2//M Inspector:
. D. Ward l
Date Accompanied By:
D. H. Danielson
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(April-21, 27-28 Date and June 20, 1988)
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Approved By:
D. H. Danielson, Chief Materials and Processes section Date Inspection Summary Inspection on March 10, April 11-12, 18, 21, 26-29, May 10, 17-18, June 1 and 20, 1988 (Reports No. 50-254/88012(DRS); No. 50-265/88006(DRS))
A_reas Inspected:
Routine, unannounced inspection of inservice inspection (ISI)
activities including review of programs (73051), procedures (73052),
observation of work activities (73753), and data review (73755); of actions on Information Notice No. 88-03 (90717); of an independent measurements inspection (73051,'/3052, 73753, 73755, and 37701); of actions on IE Bulletin 80-07; of Temporary Instruction 2515/96 activities (37828); of actions on a licensee event report (92700) and of a modification / replacement (37701).
Results:
No violations or deviations were identified.
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DETAILS
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- Persons Contacted
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Commonwealth Edison Company (CECO)
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- R.-Rax, Senior Station Manager
-*R.~Robey, Services Superintendent
' *D. Gibson, Regulatory ' Assurance Supervisor
- T. Kuba, ISI Group Leader
~*G. Tagatz, ISI Coordinator
- J. Ford, Assistant QC Supervisor-
- A. Scott, QA Engineer
~C._ Smith,-QC Supervisor D. Thayer, Maintenance Senior Staff Engineer
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~ United States Nuclear. Regulatory Commission (NRC)
- D, Danielson, Chief, Materials and Processes Section (RIII)
- A. Morrongiello, Resident Inspector T. Ross, Project Manager, (HQS)
R. Higgins, Senior Resident-Inspector
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H. Kerch, Reactor Inspector (RI)
R. Harrb, NDE Techr.ician (RI)
R.'Mingus, NDE Technician (NRC Contractor)
R. Wiggins,.NDE Technician (NRC Contractor)
-Structural Integrity Associates, Inc.
D. Pitcairn, Associate General Electric (GE)
R. Hooper, Manager, Inspection Services Morrison Construction Company (MCC)
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W. Flesch,-QC Supervisor Hartford Steam Boiler Inspection & Insurance' Company (HSB)
F. Roose, ANII The irspector also contacted and interviewed other licensee and contractor employees.
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- Denotes those present at the exit interview June 20, 1988.
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'2.
License Action on IE' Bulletin-
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(Closed) IE Bulletin No. 80-07 (265/80-07-8B).
Ultrasonic examination
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(UT) of jet pump beam bolt assemblies.
Pursuant to the requirements of IE Bulletin No. 80-07, all jet pump beam bolt assemblies were UT's by CECO, and were found to be acceptable.
The NRC inspector observed UT, reviewed the procedure and other associated documentation and determined
.that the actions implemented by the licensee met the intent of the
~ Bulletin.- It is CECO's intent to continue to UT the jet pump beam bolt assemblies during each refueling outage; and, if beam bolt assemblies are found cracked, they.will be replaced prior to unit startup.
No violations or deviations were identified.
3.
Licensee Action ~on Temporary Instruction (TI) 2515/96 (Closed) Unit 1 and 2-TI 2515/96, Inspection For Verification of Mark I BWR Orywell Vacuum Breaker Modifications Multi-Plant Action Item D-20:
The purpose of this TI was to verify that torus to drywell vacuum breaker modifications required 'n response to Multi-Plant Action Item D-20 had been accomplished.
In December 1979, General Electric issued SIL No. 321 informing customers of unanticipated cycling and damage to drywell vacuum breakers during LOCA tests in a prototype Mark I containment.
To assure that drywell vacuum breakers would be capable of withstanding chugging and condensation oscillation loads, the NRC staff issued Generic Letter 83-08 requesting licensees of Mark I containments to perform plant-unique calculations to determine the structural adequacy of the drywell vacuum breakers.
The NRC staff received responses to the Generic Letter and issued Safety Evaluations.
The need for modifications was identified in the Safety Evaluation Report stating that the 18" valves would have wrought aluminum discs with stainless steel posts.
The old valve had cast aluminum discs.
These modifications also consisted of replacing the' shaft and the weight lever with those made of higher strength components.
The NRC inspector reviewed the plant-specific safety evaluation for the facility and determined.that the vacuum breaker modifications were necessary as a result of the licensee's Generic Letter 83-08 analysis.
The NRC inspector verified, via the licensee's design modification records travelers, inspection reports and other appropriate documents, that the modification was completed on all vacuum breakers using proper materials.
Unit 1 was completed in the fall of 1982 and Unit 2 was completed in the Fall of 1981.
4.
Licensee Action on Information Notice (Closed) Information Notice No. 88-03 (88900-01) Cracks in Shroud Support Access Hole Cover Welds:
CECO determined that no inspection of the covers were needed this outage because of the demonstrated experience of good water chemistry and no shroud head bolt cracks identified in the past.
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Licensee Action ~on Licensee Event Report (LER)-
(Closed) LER No.86-017. Revision 00:
Weld No. 125-S24, through wall indication 0.9"~in length:
On'May 4, 1988, while CECO was conducting a scheduled. inservice inspection (ISI) on Intergranular. Stress Corrosion Cracking-(IGSCC) susceptible piping in accordance with Generic Letter 84-11, an ultrasonic examination (UT) on Reactor Water Cleanup (RWCU)
System [CE) line 2-1202-6", ISI Weld No. 12S-S24 revealed a through wall crack indication.
The extent of the crack indication in the pipe to penetration flued head weld was determined to be 0.9" long and located in the heat affected zone (HAZ) on the pipe side at the twelve o' clock position.
In addition to the through wall axial flaw, one other axial and two circumferential flaws were detected during the UT on the pipe side.
The weld was then repaired with a "full structural" design overlay, hydrostatic tested and verified that there was no leakage from the weld repairs.
The NRC inspector reviewed various documentation and found it to be acceptable.
This item is closed (see Paragraph 6 for details).
6.
Inservice Inspection (ISI), Unit 2 a.
General (1) This was the ninth outage of the second period of the second ten y( & plan.
(2) A pre-ISI meet;ng was held at the site March 10, 1988.
CECO, GE and NUTECH performed the ISI in accordance with ASME Section XI, 1980 Edition, Winter 1980 Addenda.
CECO and NUTECH performed visual examinations (VT).
GE performed ultrasonics (UT), magnetic particle (MT), liquid penetrant (PT) and VT examinations.
The Level II and III personnel performing UT were qualified at the EPRI NDE center after September 10, 1985.
(3) The UT's were performed with the manual and automated UT
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systems.
The automated UT's were performed with the Ultra Image III Computerized Data Acquisition System (SMART).
(4) During the period of April 18 through April 28, 1988, an onsite independent measurements inspection was conducted on Units 1 and 2.
This inspection was conducted by NRC Region I inspectors i
and contracted nondestructive examination (NDE) personnel.
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purpose of this inspection was to verify the adequacy of the l
licensee's NDE program during plant modifications.
This was I
accomplished by duplicating, as near as possible, those examinations required by code and regulations, and evaluating
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i the results.
The examination results are documented in Region I Inspection Report No. 50-254/88-10; 50-265/88-11.
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(5) The initial stainless steel piping UT plan submitted to the NRC in accordance with Generic Letter 84-11 consisted of-the examination of a total of 80 weldments, which included 14 weld overlay repaired welds, 26 welds not stress improved, 33 welds that were IHSI treated in 1984, and seven welds that were previously reported to the NRC as being flawed during the last outage.
Based on the evaluation of IGSCC-like UT indications in the sample of previous unflawed welds, the initial sample was expanded to include all of the non-weld overlay repaired 12" and larger
- welds in the Recirculation system and the remainder of the accessible IGSCC susceptible Class 1 welds in the Reactor Water Cleanup system.
Each flaw indication was evaluated in accordance with NUREG 0313, Revision 2.
In addition to the initial and expanded UT samples, a total of 47 welds in the Core Spray, Residual Heat Removal and the Recirculation systems were MSIP treated during the outage.
As part of the MSIP treatment process, a post-MSIP UT was performed.
A total of 143 welds and.14 previously applied weld overlays were examined this outage.
The licensee's sampling plan for addressing IGSCC concerns was in accordance with Generic Letter 84-11.
Generic Letter 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, was sent to all licensees of BWRs and holders of construction permits for BWRs on January 25, 1988.
NRR agreed with-the licensee's position that the ISI program for austenitic stainless steel piping covered under the scope of Generic Letter 88-01 would be implemented at the next refueling outage.
(6) The company performing the actual welding was GAPCo. using the Gold Track II Automatic Tungsten-Inert-Gas (TIG) Welding System for making weld overlays..The welding filler metal used was Type ER308L for the weld overlays.
All welding was performed in accordance with welding procedure specifications written and qualified in accordance with ASME Section IX, the latest addition of the Code.
The preparation, application, and examination of the weld overlays were described in the station travelers and procedures for the work.
(7) The following welds were found to require a weld overlay:
(a) Reactor Water Cleanup System:
Weld No. 125-S24, 6" Flued Head-to-Pipe l
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Weld No. 125-F26AR, 6" Pipe-to-Pipe (b) Recirculaion System
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Weld No. 02J-S3, 12" Pipe-to-Elbow l
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Weld No. 02H-53, 12" Pipe-to-Elbow l
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--Weld No. 02K-F6, 12" Pipe-to-Saddle
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Weld No.' 02E-S3,'12"' Pipe-to-Elbow
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Weld No. 02F-S3, 12" Pipe-to-Elbow-
.6 Weld No.'02J-S4, 12" Pipe-to-Elbow
L Weld'No. 02L-S3,'12" Pipe-to Elbow
Weld No. 020-S3, 12" Pipe-to-Elbow
Weld No. 02G-S4, 12" Pipe-to-Pipe.
Weld No. 02K-F6, 12" Pipe-to-Pipe 1_2 Weld No. 02M-S4, 12" Elbow-to-Elbow b.
. Programs and Procedures The NRC inspector reviewed.the ISI procedures and programs and found them to be acceptable. Where the ASME' Code rules were determined to be impractical,-specific relief was requested in writing. The NRC-inspector reviewed-the specific relief requests and related documentation _and had no questions, c.
Review of Material, Equipment and Personnel Certifications, Audits and Data The NRC inspector reviewed the documents relating to the following:
(1) Data reports.
(2) Ultrasonic instruments, calibration blocks, transducers and UT couplant certifications.
.(3) Magnetic particle material, and equipment certifications.
'(4) Liquid penetrant material certifications.
(5) NDE personnel certifications in accordance with SNT-TC-1A.
(6) Audits /Surveillances, i
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Observation of Work Activities The NRC inspector observed work and had discussions with personnel during the ISI activities.
These observations included the following:
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(1). GE personnel using the Ultra-Image III Computerized. Data
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(2) Ultrasonic examinations of Welds No. 02AD-F8, No. 02BS-S12,
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No. 02BS-F2, No. 02M-F7, and No. 02J-S3.
(3)- Ultrasonic examination of Weld No.'.02A-S9 in the dry well with GE's automated system and the examination results.being recorded on the SMART system.
(a) Power Cutting Inc. (PCI) machining equipment in place and machining of weld overlay.
(b) Two liquid penetrant examinations at various depths of the weld overlay after machining which were found to be acceptable.
(c) Thickness examinations after machining.
(d) Welding of the weld overlay.
(5). Welding of the weld overlays on Welds No. 02J-S4, No. 02L-S3, No. 02F-53 and No. 02G-S4.
(6) The ANII-performing his duties.
No violations.or deviations were identified.
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7.
Modification / Replacement Main Steam Drain Valve Modification The need for this modification was due to the previous drain valves consistently failing Local Leak Rate Tests and requiring excessive maintenance in order to pass these tests.
The replacement valves were 1500# Anchor / Darling gate valves.
These valves are located in Line
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No. 2-3007-3B for Unit 2.
.This modification was performed in accordance with ASME Section XI, 1980 Edition, Winter 1980 Addenda.
The NRC inspector reviewed radiographs, NDE and welding reports and other rel_ated NDE and welding documents.
The
. inspector also examined the surface of the welds that were radiographed and also various stages of fabrication.
l L-No violations or deviations were identified.
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' Exit Meetina
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The.inspoctor: met with site representatives (denoted in Persons Contacted'
' paragraph);at the conclusion of the inspection..The inspector summarized-
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.the-scope and findings of the inspection noted in.this report.
The
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inspector also discussed the'likely' informational content of the
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! inspection report'with regard to' documents or processes reviewed by.the
, f" finspector during'the inspection.. sThe licensee did not identify any such documents / processes as proprietary.-
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