United States Nuclear Power
Federal Regulations, Codes, & Standards
Users Group ©
Section XI Meeting Notes - December 2000
Prepared By: Dajun Song
Company: Progress Energy
Meeting Dates: December 11 - 14, 2000
Meeting Location: Nashville, Tennessee
1. ISI/NRC symposium will be held in Atlanta, GA.
2. Next Section XI meeting. San Francisco, CA
3. NRC Report
- V. C. Summer’s crack issue has not impacted NRC review of utility RBI submittals.
- Bechtel got the contract from DOE to manage Idaho Labs. Due to conflict of interest, NRC cancelled the contract with Idaho. Therefore, there will be delays on some reviews (Relief Requests, Plant Life Extension, Program reviews, and etc…). Expect delays till 9/01.
4. TG on Snubbers. Still trying to work with ISTD. O&M is trying to work with the NRC to resolve two issues; 1) O&M does not envelop reactor coolant boundary, and 2) No VT-3 requirement in OM Code (ISTD).
5. Two new Task Groups formed.
- TG on Inspection, Repair and Replacement of Cask Storage Containers (Rick Swayne Chairman).
6. The following Code Cases were reaffirmed through SGWCS;
N-481, N-546, N-609
7. The following Code Cases were voted (through SGWCS) to expire;
8. Beginning with the 2001 Edition, both English and metric units will appear in the Code.
Code Committee Protocol
A quick lesson on code committee protocol. Typically, a code item starts at Task Group (TG) level and must work its’ way through BNCS before utilities can use them. Here is the pecking order.
TG – Task Group
WG – Working Group
SG – Subgroup
SC XI – Subcommittee Section XI
MC – Main Committee (Items can still pass with 2 negative votes if it’s a "second
BNCS – Board of Nuclear Codes and Standards
Some popular "Groups";
TG ISIO – ISI Optimization
WG ISC – Inspection of Systems and Components
WG RBI – Risk Based Inspection
WG PT – Pressure Test
WG IWE/IWL – Containment
SG WCS – Water Cooled Systems
SG NDE – Nondestructive Evaluation
SG RRM – Repair, Replacement, and Modifications
Code Committee Items
1. Code Case N-560-2 should be published in the next Supplement.
2. A proposed code case on Risk-Informed Classifications and Requirements is out for comments by TG members. Comments are due back by 1/15/01. This will be letter balloted. This case only addresses Class 2 and 3. Class 1 is not included because it is assumed that all Class 1 components are High Safety Significant.
3. The Code Committee is working on a proposed code case to extend the PWR Reactor Vessel ISI Interval to 15 – 20 years. Current schedule is to present the Code Case to Subcommittee XI for a vote on August 2001 meeting.
4. Thermal Fatigue issue. The Thermal Fatigue Guideline will be published by EPRI’s Material Reliability Project. This Guideline only applies to Class 1 (B-J) welds on Westinghouse plants. Stan Walker of EPRI NDE center presented inspection guidelines. Exam scope includes piping OD size to 1 ½". The recommended NDE method is to either UT or RT the weld. NOTE: PDI only covers pipe sizes down to 2 inches. This is being categorized as a "voluntary nuclear compliance issue."
5. A proposed code case to clarify Class 1 & 2 bolting exam requirements, and allows surface exam of bolts (including RPV studs) in lieu of volumetric exam when they are removed. Received 2 negative votes at MC. One negative vote has been resolved. Will go back as a second consideration on Friday (12/16/00). It should pass MC. Another good code case to ask for relief.
6. Code revision to incorporate Class 2 set-on nozzle configuration with austinetic material passed SGWCS. Do we have any Class 2 set-on type nozzles?
7.Propo sed code change (Appendix III, paragraph III-2410) to retain the option of 50% transducer overlap in lieu of oscillating the transducer +20 degrees during scanning. Passed SC XI. Goes to MC.
8. Revision to Code Case N-553 to allow the user to use Appendix IV as published in the 1996 Addenda. The code case allows using eddy current method in lieu of surface examination method. Passed SC XI. Goes to MC.
9. A proposed code case to perform VT-1 exam in lieu of volumetric exam on nozzle inner radius of RPV is at BNCS. Robinson should look into this Code Case for their upcoming 10-year vessel exam.
10. Proposed code change to IWL-4110 to clarify which type of activities on concrete containment are subject to the requirements of IWL-4000. Passed SG and goes to SC XI in February, 2001.
11. Proposed Code Case, "Alternative to Subarticle IWE-5240." This code case would provide an alternative to the current VT-2 requirement in IWE-5240. It would require VT-3/General or VT-1/Detailed exam. Goes to MC.
12. Proposed Code Case, "Alternative to Augmented Examination Requirements of IWE-2500." This action will provide an alternative to visual and ultrasonic thickness measurement examination requirements of IWE-2500. At BNCS.
13. Proposed code change to eliminate SG tube examination requirements, Examination Category B-Q passed SG. Goes to SC XI. Mike B. – This should help you guys in dealing with Ernie F.
14. Proposed revision to Code Case N-613. This code revision is to align the code case with 10CFR requirements (Appendix VIII). It did not pass. Our Level III should look at this code case revision in detail.
15. Revision to Code Case N-513. Original code case allows temporary acceptance of flaws (including through-wall) in moderate energy Class 3 piping. This revision adds moderate energy Class 2 piping. Passed SC XI. At MC.
16. An interesting requirement inquiry was brought up at the Inquiry Session. It deals with examination of hangers on Class 2 piping with nominal wall thickness of less than 3/8 inches. This question is applies to users of Code Case N-491, and Code Edition 1990 Addenda and beyond. The question was not answered because the Inquiry Committee could not agree on whether the hangers are required to be examined or they must by included in the population for selection. Still, there are others that think that they are exempt from examination. I think the Code Committee, as a minimum, is leaning towards having the hangers included in the population for selection. We need to check our programs, and let’s discuss.
The following Intent Inquiry was approved. (NOTE: All intent inquires must by approved by the Main Committee.) The following intent inquiry was approved by SC XI, and will be letter balloted by the MC in January, 2001.
1. Q. Is it the intent of Code Case N-523-1 to allow the use of other editions and addenda of ASME Section XI (e.g., 1989 Edition) provided the corresponding paragraph numbers are used?
The following Requirement Inquires were approved.
1. Q. Is it a requirement of –2430(a) that for additional examinations, the sample size be expanded beyond that required by –2340(a)(1) to include all piping structural elements with the same postulated failure mode and the same or higher failure potential as the piping structural element whose examination revealed flaws or relevant conditions not meeting the acceptance standards of –3000? (Subject: Code Case N-577 and N-577-1)
2. Q. Is it a requirement of –2430(a) that if there are no additional piping structural elements with the same postulated failure mode and the same or higher failure potential as the piping structural element whose examination revealed flaws or relevant conditions not meeting the acceptance standards of –3000 then in order to meet the sample size requirements of –2430(a)(1), that additional examinations be performed on piping structural elements with the same postulated failure mode and a lower failure potential within the limitations of –2430(a)(2)?
3. Q. Does –2430(a)(2) allow additional examinations to be limited to piping structural elements categorized as "more-safety-significant" as identified in Code Case N-577, or "high-safety-significant" as identified in Code Case N-577-1 in accordance with Appendix I, I-4.2.6 through I-4.2.9?
4. Q. Is it a requirement of Code Case N-560; N-560-1; N-560-2; and N-578; and N-578-1 that methods and procedures used for the examination of FAC be qualified in accordance with Appendix VIII?
5. Q. Is it a requirement of Code Cases N-560; N-560-1; N-560-2; and N-578; and N-578-1 that personnel performing a FAC examination be qualified in accordance with Appendix VIII?
6. Q. Is it a requirement of Section XI, that when items originally procured for use as Code replacement items and with Certified Desgin Specifications are transferred between nuclear plants a new Certified Design Specification be created?
7. Q. Is it a requirement of Table IWB-2500-1 to disassemble all internal components of a valve at least once an inspection interval, to perform the VT-3 required by Category B-M-2, Item Number B12.50, even though the maintenance activity, repair, or volumetric examination may not require disassembly of some of the internal components?