ML17194B660
| ML17194B660 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/21/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| IEB-82-03, IEB-82-3, IEB-83-02, IEB-83-2, LSO5-83-07-041, LSO5-83-7-41, NUDOCS 8307260559 | |
| Download: ML17194B660 (5) | |
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- Docket No. 50-249 LSOS-83-07-041 Mr. Dennis L. Farrar Director of Nuclear Licensing Commonwealth Ed1son Company Post Office Box 767
- Chicago, Illinois 60690
Dear Mr. Farrar:
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July 21, 1983
SUBJECT:
INSPECTIONS OF BWR STAINLESS STEEL PIPING
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DISTRIBUTION Docket GHolahan NRC PDR JZwolinski Local PDR ORB Reading NSIC DCrutchfield HSmith RGilbert OELD ELJordan JMTaylor HDenton ECase Regional Administrators Division Directois '
WJohnston.. :*
B.D. Liaw As you know, the Commission has recently been briefed on the results of inspections and tests conducted on BWR recirculation system and res1dual heat removal system piping. Based upon these discussions. the NRC has concluded that it is important to obtain additional infonnation regarding the extent of intergranular stress corrosion cracking (IGSCC) at your faci11ty as soon as practicable.
As a result of inspections conducted at 18 operating Boiling Water Reactors (BWRs) in confonnance to recent IE Bulletins (IE ~ulletin No.* 82-03, Revision 1, "Stress Corrosion Cracking in Thick-Wall, Large-Diameter, Sta1nress Steel, Reci.rculation System Piping at BWR Plants," and IE Bulletin No. 83-02 1 "Stress Corrosion Cracking in Large.-Diameter Stainless Steel Rec.irculation System Piping at' BWR Pl ants"), extensive IGSCC in the primary system pi p1 ng has.* been discovered.
These bulletins requested selected licensees to perfonn a number of actions regarding inspection and testing of p1pe welds.
The Commission is considering action to accelerate the conduct of inspections by BWR licensees that have not yet begun.inspections requested by the IE Bulletins.
Inspections conducted 1n response to these bulletins over the last nine months highlighted the IGSCC problem. Results of these and other inspections have revealed extensive cracking 1n large-diameter recirculation and residual heat removal system piping. For these plants, repairs, analysis and/or additional surveillance conditions were required.
The NRC has concluded that other uninspected BWR facilities may have similar IGSCC, which may be unacceptable for continued safe operation without inspection and repair of the affected pipes and additional surveillance requirements. For this reason, we are des1rous of accelerating the inspections as much as possible.
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Accordingly, pursuant to 10 CFR 50.54(f)., you are requested to submit, signed
~~O\\b under oath or affinnat;on, the infonnation described below. This 1nfonnat1on should be provided as soon as possible, but in ariy event, it must be received
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by the NRC by August ~-* 1983.
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- NRC FORM 318110/SOINRCM 0240 OFFICIAL RECORD *copy
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- U.S. GPO 1983-;-400-247'
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'CJ July 21, 1983
- 1. A justification for continued ~peration of your facility prior to completing the inspections described by Attachment A in view of the increased evidence of cracking since the issuance of IE Bulletin 83-02.
- 2.
Identify any weld inspections which appear to satisfy the sensitivity for detection specified by IE Bulletin 83-02.
The information provided should include a list of these inspections, the dates of the inspections, the extent and results of those inspections, and a description of the technique or equipment used.
If you have concluded that these previous inspections should influence the scope or schedule of the inspections described in Attachment A, please provide the basis for your conclusion.
Further, describe any other unique safety related feature, information or action that would justify not accelerat-ing your current test and inspection schedule in accordance with IE Bulletin 83-02.
- 3.
Describe any special surveillance measures in effect or proposed for primary system leakage in addition to the current Technical Specification requirements for your facility.
- 4.
Direct and indirect costs and impact, including effects on other safety related activities, of.conducting the inspections described in Attachment A:
(a) at a time which you would commit to conduct the inspections consistent with Chairman Palladino*s suggestion to the staff and licensees that a realistic schedule for the inspections be developed 11with the idea of accelerating the inspection as much as possible, 11* and {b) at the time of your n~xt scheduled refueling outage.**
- 5.
The direct and indirect costs and impact, including effects on other safety related activities, of suspending operation to ihitiate the inspection described in Attachment A within each of three possibl.e times:
(a) 30 days, {b) 60 days, and (c) 90 days from August 15, 1983.**
- 6.
A discussion of the availability of qualified inspection personnel to perform the inspection described in Attachment A at your facility for the various options in items 4 and 5, above, and the steps you have taken to obtain the services of such personnel.
- Transcript of Commission's 11 Meeting with Industry July 15, 1983, page 101 {See Attachment B).
BWR Owner's Group, 11
- In providing the information reque.sted in items 4 and 5, the bases for the cost information and the *reasons for the effects on other safety related activities should be discussed.
In addition, the option of conducting the required inspections at the specified times separate from or as a part of a ach should b discussed.
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NRC F0~:~~~18 (10-80) NRCM 0240 "Y4 OFFICIAL RECORD COPY USGPO: 1981-33!>-960
Upon receipt of the 1nfonnat1on requested above, the staff will arrange a meeting to discuss your submittal.
The schedule for the meeting will be arranged through the assigned NRC Project Manager for your facility.
If you need to request an extension of time for the submittal of the required infonnation, such a request shall set forth the justification for the delay and include a proposed schedule for supplying this 1nfonnat1on.
Such a request shall be directed to the Director, Div1s1on of Licensing, NRR.
Any such request must be submitted no later than July 28, 1983.
Enclosures:
- l. Attachment A, Gu1de11 nes for Conducting Inspections and Tests of Large Diameter P1pe Welds
- 2. Attachment B, Partial Transcript of the Commi ss 1 on* s 11 Meeting with Industry -- BWR Owner's
- Group, 11 July 15, 1983,
- ?:~f~y!t... :J~~¢ 101
- >;~~:.c. _w.f enclosures:
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- .~'i{;se*e:::'f'iext page
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S1 ncerely, Original signed by Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
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NRCFORM31a1101ao1NRCM024.o OFFICIAL REde'.R;b.';coPv
- u.s.GPo 1983-400.-241-
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- Mr. Dennis L. Farrar cc.
Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. Doug Scott Plant Superintendent Rural Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Corrrnission Resident Inspectors Office Dresden Station RR #1 Morris, Illinois 60450 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604 James G. Keppler, Regional Administrator Nuclear Regulatory ColTlllission, Region III 799 Roosevelt Road Glen Ellyn~ Illinois 60137 Mr. Gary N. Wright, Manager Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 July 21, 1.983
- e ATTACHMENT A GUIDELINES FOR CONDUCTING INSPECTIONS AND TESTS OF LARGE DIAMETER PIPE WELDS Enclosed is IE Bulletin 83-02, "Stress Corrosion Cracking in Large-Diameter Stainless Steel Recirculation System Piping at BWR Plants, 11 issued* on March 4, 1983.
The following items reflect an expansion to the IE Bulletin.
- l. Conduct inspections and evaluations as requested in the IE Bulletin 83-02.
- 2.
In addition to the examinations required in the IE Bulletin 83-02, the licensee should conduct an ultrasonic examination of six or 100% of the welds (if there are fewer than six) in the ASME Code Class 1 portion of the residual heat removal system.
- a.
If flaws indicative of cracking are found in the above examination, additional inspection of the welds within the ASME Class l portion of the RHR syste~_should be conducted in accordance with IW B 2430 of the ASME Code Section XI and appropriate action should be taken.
- b.
The ultrasonic inspection and evaluation of the RHR piping welds shall be in accordance with those specified in IE Bulletin 83-02.
- c.
Inspection reporting requirements shall be in accordance with those specified in IE Bulletin 83-02.
- 3.
The note on page 4 of IE Bulletin 83-02 is not applicable for the inspections described in items 1 and 2, above.