ML20043C019
| ML20043C019 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/03/1990 |
| From: | Evans L HOUSE OF REP. |
| To: | Carr K NRC COMMISSION (OCM) |
| Shared Package | |
| ML20043C017 | List: |
| References | |
| NUDOCS 9006010188 | |
| Download: ML20043C019 (1) | |
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1 LANE EVANS t 77# Ol41 AICT. allmOtt
.A&*c86GTD8e. DC 200,4 (2035316-4908
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Congress of the mited #tates
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May 3, 1990
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use'w"s. m"^o,'.s"s Mr. Men Cart,- Chairman NUCLEAR' REGULATORY COMMISSION 11555 Rockville Pike Rockville, MD 20852 Dea r fir. Carr:
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As you may know, cracks have been discovered in the~ dome of reactor No. 2 at Commonweal th Edison's Quad Ci ties. Nuclear
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Generating Station.
I would like toibe'kept updated on this matter and notified of-any meetings that may be' planned < by: the 'NRC to consider this problem.
I understand that at an April.19, 1990, technical meeting, Commonwealth Edison officials told'the NRC.that cracks in the stainless steel coating of the reactor.posedLno immediate danger-1 to citizens or employees.
However, if the' cracks deepen'in'the situation could change.next several months and extend into the carbon' steel do that1 Obviously, that might threaten their safety, citizens of the area.are concerned about L.
j them that'the situation is being closely monitored.so I want to be able to~ assure l
.therefore, appreciate your sharing any information that you might I would,
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have with me.
Thank you for your cooperation in this matter.
I look forward to working with you in the days ahead.
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Sincerely, det6 h
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L LANE EVANS i
l Member of Congress x
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ENCLOSURE 1
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UNITED STATES i
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NUCLEAR REGULATORY COMMISSION l
ti W ASHINGTON, D. C. 20665
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April 27,1990; j
Docket No. 50-265 Licensee:
Commonwealth Edison Company facility: -Quad Cities Station, Unit 2
SUBJECT:
MEETING
SUMMARY
.- APRIL 19, 1990 MEETING TO DISCUSS QUAD CITIES UNIT 2 REACTOR YESSEL HEAD CRACKS On April 19, 1990, the NRC staff met with Corinonwealth Edison (the licensee) to discuss the cracks and other indications found on the reactor vessel head for Quad Cities, Unit 2.
A list of the attendees is provided in Enclosure 1.
The slides presented by the licensee ~are included in Enclosure 2..
The licensee presented a detailed-discussion of the examinations. performed (vistfal, dye penetrant and ultrasonic), the initial results of the metallurgical-o tests of several boat samples, and the fabrication history of the vessel: head.-
General Electric (GE), the nuclear steam supply system vendor, presented industry experience with clad cracking.
The licensee excavated a sufficient number of cracks to determine the crack depth and to confirm the results of the ultrasonic testings.
The mostclimiting crack-depth resulting from the excavations and boat. samples was used by the licensee in the ASME Code Section XI fracture mechanics analysis. The analysis.
concluded that an assumed crack of 0.7" would not grow more than.050"_during-L the next fuel cycle, and that the required margin' of-the ASME Code is satisfied for operation with existing flaws.
During the presentation, the NRC staff raised conevns'about other back-clad
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areas in the vessel, in particular.the beltline re;jon, and in other similar BWRs throughout the country. _To address'this concern, the licensee had GE perform a fracture mechanics evaluation of a postulated flaw in the beltline l
region. This analysis indicates that high_. fracture margins exist and indications found thus far' pose no fracture concern even-if postulated to be inlthe beltline region.
GE stated that-it will inform its customers of the Quad Cities Unit 2 experience and recommend future inspections and other followup actions.
The licensee presented its planned future activities to support-the restart of-Quad Cities Unit 2 on May 2, 1990. The licensee indicated that-they will complete the metallurgical analyses of. all Quad Cities Unit:2 boat samples, review fabrication records of their-other BWR vessels' to identify target-regions for inspection and establish an examination action plan for upcoming refueling outages for their other BWR vessels. The staff intends:to' review.
these examination plans after the-licensee has completed the metallurgical p+5M 'i&M 3 1
ENCLOSURE 1 4
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2-analysis and their review of fabrication records. The NRC staff raised no objection to the licensee's fracture mechanics analysis and' restart plans ~as presented at the meeting.--
fed.
Leonard N. 01shan.= Project Manager 4
Project Directorate III-2 Division of Reactor Projects III
-IV, V and Special Projects 1
Office of. Nuclear Reactor. Regulation l
Enclosures:
As stated cc:
See next page i
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Fr. Thor.as J. Kovach Quad Cities Nuclear Power Station Comonwealth. Edison Company Units 1 and 2-
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cc:
Mr. Stephen E. Shelton-
-Vice: President Iowa-Illinois Gas and.
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Electric Company P. O. Box 4350 Davenport, Iowa 52808 l-Michael I' Miller, Esq.
Sidley and Austin One First National Plaza t-
- Chicago, Illinois 60690 Mr. Richard Bax-Station Manager Quad Cities Nuclear Power Station 22710.206th Avenue North Cordova, Illinois 61242._
Resident Inspector U. S. Nuclear Regulatory Commission 22712 206th Avenue North' Cordova, Illinois'61242 i
Chairman-Pock-island County Board of Supervisors-1504 3rd Avenue Rock Island County Office. Bldg.
Rock Island, Illinois 61201
Illinois Department-of Nuclear Safety Office of Nuclear Facility Safety-1035 Outer Park Drive 1
Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Comission n
-799 Roosevelt Road, Bldg. #4 Glen Ellyn,-Illinois 60137 b
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C:mmoncealth Edistn -
ENCLOSURE 2 j
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l-1400 Opus Pl cs.
l Down rs Grova, Illinois 60515 May 4, 1990 f
Dr. Thomas E. Murley Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Consnission Washington, DC - 205M Subjects
-Quad Cities Nuclear Power Station Units 1=and 2 Dresden Nuclear Power Station Units-2 and 3 LaGa11e Nuclear Power Station Units 1 and 2-Reactor Vessel Head Inspection NRC Docktt Nos. 50-254/2651 50-237/2491 59-373/374
Reference:
L. N. Olshan to-T; J. Kovach letter dated April 27, 1990.
Dr. Murley:
.On April 19, 1990 members of Nuclear Reactor Regulation's (NRR) and Commonwealth Edison Company's staffs conducted a technical ~ meeting concerning~
the cracks identified in the Quad Cities Unit.2 reactor vessel head. During_
this meeting,- Conunonwealth Edison described a number of actions-which would be
-performed as the result of the identifled cracks.=.The referenced letter requested that Conunonwealth Edison provide a-schedule _ for submitting information. associated with> our: investigation. The requested schedule is attached.
If there are any questions regarding' this subject,' please ' call this office.
-Very truly yours,.
R. Stols
-t Nuclear Licensing _ Administrator cc:
A.B. Davis - Regional Administrator, RIII L.N. 01shan - Project Manager, NRR P.L. Eng - Project Manager, NRR R.M. Pulsifer - Project Manager, NRR B. Elliot - Technical Staff, NRR Senior Resident-Inspector, Dresden Senior Resident Inspector,. Quad Cities Senior Resident Inspector, LaSalle
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9 ATTACBENT SCREDULE
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~1.
RESULTS OF THE TRACTURE MECHANIC ANALYSIS =
The fracture mechanic analysis hes been completed.1 The analysis concluded-that continued operation of the plant for the next fuel; cycle is justified in that ASME Section 'XI and Section III Margins are maintained.- The analysis SASR-90-33 " Structural Evaluation.of Cracks lln the Top Head'at t
Quad Cities Nuclear Power Station, Unit 2". dated April,,1990 is attached.
.2.
RESULTS OF 'THE BOAT SAMPLE METALLURGICAL ANALYSES-The results of the boat sample metallurgical examinations on the, Quad-Cities Unit 2 Reactor. Pressure Vessel Head will be: submitted to the NRC by; July 1, 1990. There is a' potential that.the Scanning. Electron Microscopy 1 (SEM) results will not be included in the. July 1,1990 submittal, due. to Argonne National. Laboratory commitments associated.with the Three' Mile l
Island Reactor Vessel work.
In the-event that the information is not yet-J available, Commonwealth Edison-will define a-submittal date of the SEM results in the July 1, 1990 submittal.
3.
SUMMARY
OF. TEE FABRICATION HISTORY The review of the f abrication history for each of the Ceco BWR vessels has been prioritized by the Refueling Outage scheduleJand information needed d
t to support the development'offthe inspection plans.The? fabrication-I history review required to support the development ofothe: inspection plan includes the reactor vessel head,. vessel-to-flange veld, and uppermost shell-to-shell weld for each reactor vessel.
The' fabrication records:for the LaSalle Station Unit 2-reactor vessel head i
has been reviewed to support the current Refueling Outage vessel. head i
inspection.
No-anomalies, similar to. the Quad ' Cities : Unit -2 f abrication.
l history. were identified. A review,of.the vessel-to-flange _ weld and l
uppermost shell-to-shell weld f abrication records will.be conducted. The l
fabrication history summary for the vessel head, shell-to-flange weld and shell-to-shell weld will.be submitted by July 12, 1990.- The first phase review for the remaining units will be'provided:as:follows:
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Dresden Unit.2
. July 2, 1990 i
Quad Cities Unit 2 July 2, 1990
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Quad Cities Unit 1 August 1, 1990 Dresden-Unit 3 September 4,.1990 4
LaSalle Unit 1 October 1,.1990-H The fabrication review summary for the remaining areas of each BWR vessel
-l will be submitted by December 31, 1990.
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INSPt.CTION PIANS An Inspection Plan will be developed for each unit prior to the respective This Inspection Plan development schedule will allow Refueling Outage.
for lessons learned to be incorporated from the previous unit's inspection-into each inspection plan. The schedule for submitting-the Inspection l
Plans is as followat
.i Insoection Plan Suh=mittal Refueline Outaee Schedule.
Dresden Unit 2 July 2, 1990-September, 1990
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-Quad Cities Unit 1 August 1, 1990 October,-1990 Dresden Unit;3 December 3.-1990.
March, 1991 I
1.aSalle Unit.1 January 2, 1991 April, 1991 Quad Cities Unit 2 June.3, 1991 September,:1991 LaSalle Unit 2 October 1, 1991 January, 1992
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