ML061210425
| ML061210425 | |
| Person / Time | |
|---|---|
| Issue date: | 05/22/2006 |
| From: | Norris W NRC/RES/DFERR/ME/FAITB |
| To: | |
| Norris W E 415-6796 | |
| References | |
| DG-1135 RG-1.193, Rev. 2 | |
| Download: ML061210425 (15) | |
Text
1 Copies may be obtained from the American Society of Mechanical Engineers, Three Park Avenue, New York, NY 10016-5990; phone (212) 591-8500; fax (212) 591-8501; www.asme.org.
This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regulatory position in this area. It has not received staff review or approval and does not represent an official NRC staff position.
Public comments are being solicited on this draft guide (including any implementation schedule) and its associated regulatory analysis or value/impact statement. Comment s should be accompanied by appropriate supporting data. Written comments may be submitted to the Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
Comments may be submitted electronically through the NRCs interact ive rulemaking Web page at http://ww w.nrc.gov/what-w e-do/regulatory/rulemaking.html. Copies of comments received may be examined at the NRC Public Document Room, 11555 Rockville Pike, Rockville, MD. Comments will be most helpful if received by July 14, 2006.
Requests for single copies of draft or active regulatory guides (w hich may be reproduced) or for placement on an automatic distribution list for single copies of future draft guides in specific divisions should be made to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301)415-2289; or by email to Distribution@nrc.gov. Electronic copies of this draft regulatory guide are available through the NRCs interactive rulemaking Web page (see above); the NRCs public Web site under Draft Regulatory Guides in the Regulatory Guides document collect ion of the NRCs Electronic Reading Room at http://w w w.nrc.gov/reading-rm/doc-collections/; and the NRCs Agencyw ide Documents Access and Management System (ADAMS) at http://ww w.nrc.gov/reading-rm/adams.html, under Accession No. ML061210425.
U.S. NUCLEAR REGULATORY COMMISSION May 2006 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 DRAFT REGULATORY GUIDE
Contact:
W.E. Norris, (301) 415-6796 DRAFT REGULATORY GUIDE DG-1135 (Proposed Revision 2 of Regulatory Guide 1.193, dated August 2005)
ASME CODE CASES NOT APPROVED FOR USE A. INTRODUCTION In Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), Domestic Licensing of Production and Utilization Facilities, Section 50.55a(c), Reactor Coolant Pressure Boundary, requires, in part, that components of the reactor coolant pressure boundary be designed, fabricated, erected, and tested in accordance with the requirements for Class 1 components of Section III, Rules for Construction of Nuclear Power Plant Components, 1 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code or equivalent quality standards. Section 50.55a(f), Inservice Testing Requirements, requires, in part, that Class 1, 2, and 3 components and their supports meet the requirements of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) or equivalent quality standards.
Finally, 10 CFR 50.55a(g), Inservice Inspection Requirements, requires, in part, that Classes 1, 2, 3, MC (metal containment), and CC (concrete containment) components and their supports meet the requirements of Section XI, Rules for Inservice Inspection of Nuclear Pow er Plant Components, of the ASME BPV Code or equivalent quality standards.
The ASME publishes a new edition of the BPV and OM Codes every 3 years and new addenda every year. The latest editions and addenda of Section III,Section XI, and the OM Code that the U.S. Nuclear Regulatory Commission (NRC) has approved for use by licensees are
2 Revision 32 of Regulatory Guide 1.84 combined Regulatory Guides 1.84 and 1.85 to list all Section III Code Cases in one guide. The title of Regulatory Guide 1.84 has been modified to reflect this.
DG-1135, Page 2 referenced in 10 CFR 50.55a(b). The ASME also publishes Code Cases for Section III and Section XI quarterly and Code Cases for the OM Code yearly. Code Cases provide alternatives developed and approved by the ASME. Revision 33 of Regulatory Guide 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, 2 and Revision 14 of Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, are being revised to identify the Code Cases that the NRC has determined to be acceptable alternatives to applicable parts of Section III and Section XI.
The NRC staff has reviewed Section III and Section XI Code Cases listed in Supplements 7-12 to the 2001 Edition, and Supplement 1 to the 2004 Edition of the ASME BPV Code. Draft Regulatory Guide DG-1133 (proposed Revision 34 of Regulatory Guide 1.84) and Draft Regulatory Guide DG-1134 (proposed Revision 15 of Regulatory Guide 1.147) specify the Code Cases determined to be acceptable, and are being published concurrently with this draft guide for public comment. This regulatory guide does not approve the use of the Code Cases listed herein.
The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory guides are not substitutes for regulations, and compliance with regulatory guides is not required. The NRC issues regulatory guides in draft form to solicit public comment and involve the public in developing the agencys regulatory positions. Draft regulatory guides have not received complete staff review and, therefore, they do not represent official NRC staff positions.
Because this regulatory guide does not approve the use of the Code Cases listed herein, it does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
DG-1135, Page 3 B. DISCUSSION This regulatory guide lists the Code Cases that the NRC has determined not to be acceptable for use on a generic basis. A brief description of the basis for the determination is provided with each Code Case. Licensees may submit a request to implement one or more of the Code Cases listed below through 10 CFR 50.55a(a)(3), w hich permits the use of alternatives to the Code requirements referenced in 10 CFR 50.55a, provided that the proposed alternatives result in an acceptable level of quality and safety. A licensee must submit a plant-specific request that addresses the NRCs concerns about the Code Case at issue.
C. REGULATORY POSITION For this guide, the NRC staff reviewed the Section III and Section XI Code Cases listed in Supplements 7-12 to the 2001 Edition, and Supplement 1 to the 2004 Edition of the ASME BPV Code. Licensees must not implement Code Cases listed in this guide without prior NRC approval. This regulatory guide will be revised as necessary.
1.
Unacceptable Section III Code Cases The NRC determined that the following Section III Code Cases are unacceptable for use by licensees in their Section III design and construction programs. The ASME issues a new edition of Section III every 3 years, and publishes quarterly supplements to the edition containing Section III Code Cases. Hence, there are 12 supplements to each edition.
To assist users, Code Case changes specific to this draft guide are shaded. The shading will assist in focusing attention during the public comment period on the changes to the guide.
The third column of Table 1 lists the date of approval by the ASME, the reaffirmation date (signified by the letter R ), or for new Code Cases, and the supplement and edition in which each Code Case was published (e.g., 11/01E means Code Case Supplement 11 to the 2001 Edition).
DG-1135, Page 4 Table 1. Unacceptable Section III Code Cases Code Case Number Table 1 Unacc ept able Section III Code Cases Date or Supplement/
Edition Summary N-284-1 M etal Cont ainment Shell Buckling Design M ethods,Section III, Division 1, Class M C R5/9/03 (1)
The f ollow ing errata, misprints, recommendat ions, and errors have been identified:
Fig. 1 511.1, The curv e for "2L should not exceed 0.8 for any value of (R/t ).
-1512, The st atement See Fig. 1 512-1 then see
-171 3.1.2 f or method of calculating M should be rephrased as: See -17 13.1.2 for method of calculating M,
then see Fig. -15 12 -1.
-151 3, Recommend Use the value of "il given for spherical shells in accordance w ith -15 12.
-152 1, (i) In (a) Axial Compression, "2G = "2L should be changed to "NG = "NL. (ii) The source of t he equations show n under (a) Axial Compression provided separat e inst abilit y equations for st ringer-stiffened and ring-stiffened cy lindrical shells. The Code Case adopt ed t he instabilit y equations pert aining t o ring-st iffened shells, w hich are less conservative than those for stringer instability, for both ring and/or stringer stiff ened cylindrical shells. Is this the int ent ? (Ref. Sum mary of Buckling Tests on Fabricat ed Steel Cylindrical Shells in USA, by C.D. M iller, in Buckling of Shells in Offshore Structures, 19 82.)
-171 2.1.1, The equation C2h = 0.9 2/(M 2 - 0.6 36) should be changed to C2h = 0.9 2/(M N - 0.6 36).
-171 2.1.1-1, The left most curve should be labeled C2h
-17 12.2.2, (a) Axial Compression, (i) In t he formula for FNej, the denominat or should be (mB/Lj)2 C t N. (ii) The expressions f or CN and C2 should be separated.
-1712.2.3, (i) The f act or 1.9 44 in an older edit ion has been changed to 2.00. No basis is apparent. (ii) The misprint t 1 1/4 should be corrected to t 1 1/4.
-171 3.1.1, (i) The equation FJa= "N2CFN2el/FS should be changed to FJa= "N2LCFN2el/FS. (ii) The title of (c) should be changed to Ax ial Compression Plus In-Plane Shear.
-1713.1 -1, In (b), the low er value Ks= Fra on the vertical axis should be changed to Ks= Fha
-171 3.2.1, (i) The headings for (b) and (c) should include the w ords In-Plane. (ii) In (b) Axial Compression Plus Shear, F2 should be changed to FN.
Code Case Number Table 1 Unacc ept able Section III Code Cases Date or Supplement/
Edition Summary DG-1135, Page 5 N-284-1 (cont d)
M etal Cont ainment Shell Buckling Design M ethods,Section III, Division 1, Class M C R5/9/03 (2)
Applicants int ending to use Code Case N-284-1 shall subm it a request to t he NRC staff for its review and approval on a plant-specific basis.
(3)
The rules applicable t o evaluat e the buckling and instabilit y of cont ainm ent shells f or Section III, Division 3, are under development. Currently, use of Code Case N-284 -1 by licensees for storage canisters and transportation casks is permissible provided it has been review ed and approved by the NRC.
N-483-2 N-483-3 Alternat ive Rules t o t he Provisions of NCA -3800, Requirement s for Purchase of M aterial,Section III, Divisions 1 and 3 5/7/99 2/25/02 The Code Case lacks suf ficient det ail to ensure t hat the supplied material is as represented by t he Certif ied M aterial Test Report.
N-5 10 N-510-1 Borat ed St ainless St eel for Class CS Core Support Structures and Class 1 Component Supports,Section III, Division 1 12/9/93 8/14/01 No technical basis w as provided for ex panding t he Code Case to include borat ed st ainless st eel Types 3 04B, 304B1, 304B2, and 304B3. A considerable am ount of inf orm ation w as required to support t he types presently contained in the Code Case.
The revised Code Case w ould permit borated stainless steel to be used for component supports w ithin the reactor vessel.
The technical basis t o support the Code Case only addresses the use of these m aterials as component supports in spent fuel racks and t ransport ation casks.
N-5 19 Use of 6061-T6 and 6061-T6 51 Alum inum for Class 1 Nuclear Components Annulled 2/3/03 Code Case is applicable t o only one DOE aluminum vessel.
N-5 30 Provisions for Establishing Allow able Axial Compressive M embrane Stresses in t he Cylindrical W alls of 0-15 Psi Storage Tanks, Classes 2 and 3 R2/3/03 (7/01E)
There are numerous errors in the equations. The errors must be corrected before t he Code Case can be approv ed f or use.
Code Case Number Table 1 Unacc ept able Section III Code Cases Date or Supplement/
Edition Summary DG-1135, Page 6 N-5 65 Alternat ive M ethods of Nozzle Attachment for Class 1 Vessels 12/3/99 The Code Case essentially requires a design using a seal to protect the threads from the contained fluid, and seals are not a Code item. The seal, w hich plays a very important part in t he integrit y of t he joint, imposes too great a vulnerability in the design. The supporting inf orm ation for t he Code Case does not dem onstrate the resulting threaded nozzle conf iguration is equivalent in integrit y to t hat of a w elded connection.
N-5 95 N-595-1 N-595-2 N-595-3 Requirem ents for Spent Fuel St orage Canist ers,Section III, Division 1 2/26/99 9/24/99 12/8/00 04/08/02 Regulat ory approv al for t he use of mult i-purpose casks is presently addressed by the NRC Spent Fuel Project Office Interim Staff Guidance No. 4, Rev. 1 (ISG-4, Rev. 1 ). The interim staff guidance prov ides a f ramew ork to ensure t hat the cask sy stem, as designed, and w hen fabricated and used in accordance w ith the conditions specified in its Certificate of Compliance, meets the requirement s of 10 CFR Part 72. The A SM E is presently developing Code Case N-71 7 t o replace Code Case N-59 5-3.
Thus, Code Case N-595 -3 w ill be retained in Regulatory Guide 1.1 93, and t he NRC w ill review Code Case N-717 w hen it is published.
N-6 45 N-645-1 Use of Rupt ure Disk Devices on Nuclear Fuel Storage Canist ers, Class 1,Section III, Division 1 6/14/00 R2/3/03 (7/01E)
The NRC does not permit t he use of rupture disk devices in spent nuclear f uel st orage canister designs.
N-659-1 Use of Ult rasonic Exam inat ion in Lieu of Radiography for W eld Examination,Section III, Division 1 11/01E (a)
The w eld examinat ion volume has been unacceptably reduced w hich m ay exclude regions of high residual st ress.
(b)
Any f uture unspecified edition and addenda of Section V could be used for nondestruct ive examination.
(c)
A surface examination could be used to evaluate surface connect ed f law s w hich m ay be characterized by ult rasonic testing as cracks, lack of fusion, or lack of penetration.
Such characterizations w ould autom atically be rejected by Sect ion III criteria.
Code Case Number Table 1 Unacc ept able Section III Code Cases Date or Supplement/
Edition Summary DG-1135, Page 7 N-6 73 Boron Containing Pow der M etallurgy A luminum Alloy for Storage and Transportation of Spent Nuclear Fuel,Section III, Division 1 11/01E The Code Case does not address the follow ing:
(a)
Corrosion properties of t his material in spent fuel pool chemist ry and/or clean w ater.
(b)
Impact propert ies for use as a structural m aterial.
(c)
Uniform distribution of boron carbide in the aluminum matrix.
(d)
M echanical propert ies for t he use of the m aterial in high-temperat ure condit ions.
N-6 93 Alternative M ethod to t he Requirements of NB-32 28.6 for Analyzing Piping Subjected to Reversing Dynamic Loads,Section III, Division 1 10/01E The Code Case w ould permit the use of the design, serv ice, and test limits in Paragraph NB-36 56 (b) for Level D Service Limits.
The lim it s in Paragraph NB-3 656(b) are prohibit ed per 10 CFR 50.5 5a(b)(1 )(iii).
N-7 17 Requirements for Construct ion of Storage Containments for Spent Nuclear Fuel and High Level Radioact ive W aste and M aterial,Section III, Division 3 1/04E The provisions of the Code Case are copied from the July 1, 20 05, addenda to Containments for Transportation and Storage of Spent Nuclear Fuel and High Level Radioactive Material and W aste,Section III, Division 3. The changes to the ASM E Code contained in the addenda are presently being review ed by the NRC staff. The Code Case is listed in this guide pending the results of the NRC staf f review.
Regulat ory approv al for t he use of mult i-purpose casks is presently addressed by the NRC Spent Fuel Project Office Interim Staff Guidance No. 4, Rev. 1 (ISG-4, Rev. 1 ). The interim staff guidance prov ides a f ramew ork to ensure t hat the cask sy stem, as designed, and w hen fabricated and used in accordance w ith the conditions specified in its Certificate of Compliance, meets the requirements of 10 CFR Part 7 2.
DG-1135, Page 8 2.
Unacceptable Section XI Code Cases The NRC determined that the follow ing Section XI Code Cases are unacceptable for use by licensees in their Section XI inservice inspection programs. The ASME issues a new edition of Section XI every 3 years, and publishes quarterly supplements to the edition containing Section XI Code Cases. Hence, there are 12 supplements to each edition. To assist users, Code Case changes specific to this draft guide are shaded. The shading will assist in focusing attention during the public comment period on the changes to the guide. The third column of Table 2 lists the date of approval by the ASME, the reaffirmation date (signified by the letter R ), or for new Code Cases, and the supplement and edition in w hich each Code Case w as published (e.g., 11/01E means Code Case Supplement 11 to the 2001 Edition).
Table 2. Unacceptable Section XI Code Cases Code Case Number Table 2 Unacc ept able Section XI Code Cases Date or Supplement/
Edition Summary N-4 65 N-465-1 Alternative Rules for Pump Testing,Section XI, Division 1 11/30/88 Annulled 2/14/03 (8-9/01E)
The draft standard referenced in the Code Case is outdated.
The requirements contained in the OM Code, Code for Operation and Maintenance of Nuclear Pow er Plants, should be used.
Note that Revision 12 of RG 1.1 47 approved N-46 5 f or use.
The disapproval of N-4 65 for use applies only to new users.
N-4 73 N-473-1 Alternative Rules for Valve Testing,Section XI, Division 1 3/8/89 Annulled 2/14/03 (8-9/01E)
The draft standard referenced in the Code Case is outdated.
The requirements contained in the OM Code, Code for Operation and Maintenance of Nuclear Pow er Plants, should be used.
Note that Revision 12 of RG 1.1 47 approved N-47 3 f or use.
The disapproval of N-4 73 for use applies only to new users.
N-4 80 Examinat ion Requirement s for Pipe W all Thinning Due to Single Phase Erosion and Corrosion,Section XI, Division 1 Annulled on 9/18/01 Code Case has been superseded by Code Case N-59 7, Requirements for A nalytical Evaluation of Pipe W all Thinning, implem ent ed in conjunct ion w ith NSA C-202L, Recom mendations for an Effect ive Flow -Accelerated Corrosion Program.
N-498-2 N-498-3 Alternative Requirements for 10-Year System Hydrostatic Testing for Class 1, 2, and 3 Systems,Section XI, Division 1 6/9/95 5/20/98 Code Case N-49 8-4 is conditionally approved in Revision 13 of Regulatory Guide 1.147. Those licensees choosing to implement this Code Case are to implement Revision 4.
Code Case Number Table 2 Unacc ept able Section XI Code Cases Date or Supplement/
Edition Summary DG-1135, Page 9 N-532-2 Alternative Requirements to Repair and Replacement Docum entation Requirements and Inservice Summary Report Preparation and Submission as Requested by IW A-400 0 and IW A-600 0,Section XI, Division 1 7/23/02 The follow ing concerns w ere identified during review of t he Code Case:
(1)
The Code Case references new paragraph IWA-6350 w hich has not yet been incorporat ed into t he A SM E Code; (2)
NRC staff had dif ficulty reconciling Foot note 1 and Table 4 regarding the applicable edition and addenda; and (3)
Submission of Form OAR-1 is at t he end of each inspection period rat her t han 90 days follow ing the out age.
N-5 42 Alternative Requirements for Nozzle Inside Radius Section Length Sizing Performance Demonstration,Section XI, Division 1 Annulled on 3/28/01 Code Case N-542 w as subsum ed by Code Case N-552, Alternative M ethods-Qualification for Nozzle Inside Radius Section from the Outside Surface, w hich is being implemented by licensees.
Thus, there is no need t o approve Code Case N-542.
N-5 47 Alternative Examination Requirements for Pressure Retaining Bolting of Control Rod Drive (CRD) Housings,Section XI, Division 1 Annulled on 5/20/01 Code Case N-547 states that the examinat ion of CRD housing bolts, st uds, and nuts is not required. How ev er, 10 CFR 50.5 5a(b)(2 )(xx i)(B) requires t he examinat ion of CRD bolt ing material w henever the CRD housing is disassembled and the bolt ing material is to be reused. Examination of CRD bolting material is required to verify that service-relat ed degradation has not occurred, or t hat dam age such as bending and galling of threads has not occurred w hen performing maintenance activities that require the removal and reinstallation of bolting.
N-5 60 N-560-1 N-560-2 Alternat ive Examinat ion Requirement s for Class 1, Cat egory B-J Piping W elds,Section XI, Division 1 8/9/96 2/26/99 R2/14/03 (8-9-/01E)
(1)
The Code Case does not address inspection strategy for existing augment ed and other inspection program s such as intergranular stress corrosion cracking (IGSCC), f low -assisted corrosion (FAC),
microbiological corrosion (M IC), and pitt ing.
(2)
The Code Case does not provide system-level guidelines for change in risk evaluat ion to ensure t hat the risk from individual syst em f ailures w ill be kept small and dominant risk cont ribut ors w ill not be created.
Code Case Number Table 2 Unacc ept able Section XI Code Cases Date or Supplement/
Edition Summary DG-1135, Page 10 N-5 61 N-561-1 Alternat ive Requirement s for W all Thick ness Restorat ion of Class 2 and High Energy Class 3 Carbon Steel Piping,Section XI, Division 1 12/31/96 3/28/01 Neither the ASM E Code nor the Code Case have criteria for determining the rate or ext ent of degradation of the repair or the surrounding base metal. Reinspect ion requirement s are not provided to v erify struct ural integrity since the root cause may not be mitigated.
N-5 62 N-562-1 Alternat ive Requirement s for W all Thick ness Restorat ion of Class 3 M oderate Energy Carbon Steel Piping,Section XI, Division 1 12/31/96 3/28/01 Neither the ASM E Code nor the Code Case have criteria for determining the rate or ext ent of degradation of the repair or the surrounding basemetal. Reinspect ion requirement s are not provided to v erify struct ural integrity since the root cause may not be mitigated.
N-5 74 NDE Personnel Recertification Frequency,Section XI, Division 1 R2/14/03 (8-9/01E)
Based on dat a obtained by the NRC staf f during its review of Appendix VIII, Perform ance Demonstration for Ultrasonic Examination Systems, to Section XI, the NRC staff noted that prof iciency decreases over tim e. The data does not support re-certificat ion examinat ions at a frequency of every 5 years.
N-5 75 Alternative Examination Requirements for Full Penetration Nozzle-to-Vessel W elds in React or V essels w ith Set -On Type Nozzles,Section XI, Division 1 R2/14/03 (8-9/01E)
The supporting basis f or t he Code Case applies t o t he specif ic configuration of one plant and is not applicable on a generic basis.
In addition, there are insufficient cont rols on stress and operating conditions to permit a generic reduction in examination volume.
Finally, the boundaries of the volume of the w eld, cladding, and heat aff ected zone from Figure 2 are ambiguous.
N-5 77 N-577-1 Risk-Informed Requirements for Class 1, 2, and 3 Piping, M ethod A,Section XI, Division 1 9/2/97 R2/14/03 (8-9/01E)
(1)
The Code Case does not address inspection strategy for existing augment ed and other inspection program s such as intergranular stress corrosion cracking (IGSCC), f low -assisted corrosion (FAC),
microbiological corrosion (M IC), and pitt ing.
(2)
The Code Case does not provide system-level guidelines for change in risk evaluat ion to ensure t hat the risk from individual syst em f ailures w ill be kept small and dominant risk cont ribut ors w ill not be created.
Code Case Number Table 2 Unacc ept able Section XI Code Cases Date or Supplement/
Edition Summary DG-1135, Page 11 N-5 78 N-578-1 Risk-Inform ed Requirements f or Class 1, 2, and 3 Piping, M et hod B,Section XI, Division 1 9/2/97 R2/14/03 (8-9/01E)
(1)
The Code Case does not address inspection strategy for existing augment ed and other inspection program s such as intergranular stress corrosion cracking, flow -assisted corrosion, microbiological corrosion, and pitting.
(2)
The Code Case does not provide system-level guidelines for change in risk evaluat ion to ensure t hat the risk from individual syst em f ailures w ill be kept small and dominant risk cont ribut ors w ill not be created.
N-5 87 Alternat ive NDE Requirement s for Repair/Replacem ent Act ivities,Section XI, Division 1 Annulled 2/14/03 (8-9/01E)
The NRC believes this Code Case is in conflict w ith t he review process for approval of alternatives under 10 CFR 50.55a(a)(3). The Code Case w ould permit a licensee and the A ut horized Nuclear Inspect or to choose unspecif ied alternat ives to regulatory requirement s.
N-5 89 N-589-1 Class 3 Nonmetallic Cured-in-Place Piping,Section XI, Division 1 4/19/02 7/23/02 (1)
The inst allation process prov ides insuf ficient cont rols on w all thickness measurement.
(2)
There are no qualification requirements for installers and inst allation procedures such as those for w elders and w elding procedures.
(3)
Fracture toughness properties of the fiberglass are such that t he cured-in-place piping (CIPP) could crack during a seismic event.
(4)
Equations 4 and 5 in t he Code Case contain an i term [a st ress intensification factor] that is derived from fatigue considerations.
Stress int ensif icat ion fact ors, how ever, have not been developed for f iberglass materials.
N-5 90 Alternat ive to t he Requirement s of Subsect ion IWE, Requirement s for Class M C and M etallic Liners of Class CC Com ponents of Light-Water Cooled Plants,Section XI, Division 1 Annulled on 4/8/02 The provisions of the Code Case w ere incorporat ed into t he 1 998 Edition w hich has been approved by the NRC. Thus, the Code Case is no longer needed and w as annulled by the A SM E.
Code Case Number Table 2 Unacc ept able Section XI Code Cases Date or Supplement/
Edition Summary DG-1135, Page 12 N-5 91 Alternat ive to t he Requirement s of Subsect ion IWL, Requirement s for Class CC Concrete Com ponents of Light-W ater Cooled Plants,Section XI, Division 1 Annulled on 4/8/02 The provisions of the Code Case w ere incorporat ed into t he 1 998 Edition w hich has been approved by the NRC. Thus, the Code Case is no longer needed and w as annulled by the A SM E.
N-6 13 Ult rasonic Exam inat ion of Full Penet ration Nozzles in Vessels, Examination Category B-D, Item Nos. B3.1 0 and B3.9 0, Reactor Vessel-To-Nozzle W elds, Fig. IW B-2500-7(a), (b), and (c ),Section X I, Division 1 7/30/98 The Code Case conf lict s w ith and unacceptably reduces the requirements of 10 CFR 50.55a(b)(2)(xv)(K)(2)(i). A revision to t he Code Case has been developed t o address t he concerns.
N-6 15 Ultrasonic Examination as a Surface Examination M ethod for Category B-F and B-J Piping W elds,Section XI, Division 1 7/28/01 The Code Case requires that the ultrasonic technique used be demonstrated capable of detecting certain size flaw s on the outside diameter of the w eld, but it does not specify any demonstration requirement s. To be accept able, Sect ion XI, A ppendix VIII, type rules for performance demonstration need to be developed and applied.
N-6 18 Use of a Reactor Pressure Vessel as a Transportation Containment System,Section XI, Division 1 10/01E The Code Case w as developed as a potential option for shipping and disposal of a react or pressure v essel (RPV). The NRC staf f det ermined, how ever, t hat the Code Case w as not applicable to the review and approval process for transportation packages.
The use of RPVs as a transport ation package has been addressed under 10 CFR Part 7 1.
N-6 22 Ult rasonic Exam inat ion of RPV and Piping, Bolts, and St uds,Section XI, Division 1 4/19/02 The Code Case w as published in May 19 99. Industry Performance Demonstration Initiative eff orts since that t ime have made this Code Case obsolete. Issues assoc iat ed w ith supplements to A ppendix VIII are being addressed individually in separate Code Cases.
Code Case Number Table 2 Unacc ept able Section XI Code Cases Date or Supplement/
Edition Summary DG-1135, Page 13 N-6 53 Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping W elds,Section XI, Division 1 9/7/01 (1)
Section XI, A ppendix VIII, Supplem ent 11, requires a personnel performance qualification as part of the procedure qualification.
The detection acceptance criteria in the Code Case do not require personnel performance qualification as part of the procedure qualification. Personnel qualification is necessary t o validate the effect iveness of the procedure qualification.
(2)
The minim um grading unit is 1.0 inch in the circum ferent ial direction. The acceptance tolerance, how ever, is 0.7 5 inch root mean square error. Thus, the length sizing acceptance criteria do not adequat ely prev ent the use of testmanship rather t han skill t o pass length sizing tests.
N-6 54 Acceptance Criteria for Flaw s in Ferritic Steel Components 4 in.
and Greater in Thickness,Section XI, Division 1 4/17/02 Licensees int ending to apply the rules of this Code Case m ust obtain NRC approval of the specif ic applicat ion in accordance w it h 10 CFR 50.55a(3).
N-6 91 Application of Risk-Informed Insights to Increase the Inspection Interval for Pressurized W ater Reactor Vessels,Section XI, Division 1 11/01E The industry topical report in support of t he Code Case relies on information developed to re-evaluate present requirements related to pressure vessel embritt lement and the pressurized thermal shock screening criteria. This inform ation has not yet been fully review ed by NRC staff.
N-7 02 Alternat ive Requirement s for Boiling W ater Reactor (BW R) Nozzle Inner Radius and Nozzle-to-Shell W elds,Section XI, Division 1 12/01E A response to the NRC staff s request for additional information has not yet been received and therefore, insufficient information has been prov ided for t he st aff to m ake a determinat ion relative to the acceptabilit y of this Code Case.
DG-1135, Page 14 3.
Unacceptable OM Code Cases The following OM Code Cases w ere determined to be unacceptable for use by licensees in their inservice testing programs. The ASME issues OM Code Cases annually w ith publication of a new edition or addenda. No new OM Code Cases were added in this revision. To assist users of the OM Code, Column 3 of Table 3 lists the edition or addenda to which each Code Case was attached (E: edition; A: addenda), and whether the Code Case is new or reaffirmed.
Table 3. Unacceptable OM Code Cases Code Case Number Table 3 Unacc ept able OM Code Cases Date or Edition/
Addenda Summary of Basis for Exclusion OMN-10, Rev. 0 Requirements for Safety Significance Categorization of Snubbers Using Risk Insight s and Test ing Strategies for Inservice Testing of LWR Pow er Plants July 1, 2000A The method used f or categorizing snubbers could result in certain snubbers being inappropriately categorized as having low safety significance. These snubbers w ould not be adequat ely tested or inspect ed t o prov ide assurance of their operational readiness. In addition, unexpected extensive degradat ion in f eedw ater piping has occ urred w hich w ould necessitate a more rigorous approach to snubber cat egorization than presently cont ained in t his Code Case.
DG-1135, Page 15 D. IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staffs plans for using this draft regulatory guide. The NRC has issued this draft guide to encourage public participation in its development. This regulatory guide does not approve the use of the Code Cases listed herein.
REGULATORY ANALYSIS This regulatory guide lists only the Code Cases that the NRC staff has determined to be unacceptable for use in the design and construction, inservice inspection, and inservice testing of nuclear power plant systems and components. Therefore, the staff has not prepared a regulatory analysis for this guide.
Previous reviews of ASME Code Cases discussed only the Code Cases that the NRC staff determined to be acceptable. This guide was developed at industry request to list the Code Cases that the NRC staff has determined to be unacceptable for use in licensee design and construction, inservice inspection, and inservice testing programs, including a summary of the basis for disapproval. Providing the basis for disapproval of a Code Case affords licensees the opportunity to address NRC staff concerns through 10 CFR 50.55a(a)(3), w hich permits the use of alternatives to the mandated ASME Code requirements provided the proposed alternatives result in an acceptable level of quality and safety and their use is authorized by the Director of the Office of Nuclear Reactor Regulation.
Providing the basis for disapproval of a Code Case in this guide will also conserve industry resources. The cognizant ASME committees will be able to focus their attention on specific issues. In addition, licensees who choose to request alternatives under 10 CFR 50.55a(a)(3) will understand the NRC staff concerns to be addressed. NRC resources will be saved because the 10 CFR 50.55a(a)(3) process will be more efficient. When the ASME modifies a Code Case to address NRC staff concerns, additional NRC resources w ill be saved because the NRC will be able to generically approve the Code Cases thus obviating the need for case-by-case approval. In addition, since many Code Cases generally simplify implementation of ASME Code provisions, reduce radiological exposure, or incorporate operating experience and technological improvements, it is anticipated that, when NRC staff concerns have been addressed, licensees will be able to reduce allocated resources even further.