ML20211J309
| ML20211J309 | |
| Person / Time | |
|---|---|
| Issue date: | 02/18/1999 |
| From: | Jerome Murphy Committee To Review Generic Requirements |
| To: | Travers W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| NUDOCS 9909030116 | |
| Download: ML20211J309 (65) | |
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i UNITED STATES s* j 2
NUCLEAR REGULATORY COMM_lSSION WASHINGTON, D.C. 20066-0001
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MEMORANDUM TO: William D. Travers Executive Director for Operations FROM: Joseph A. Murphy, Chairman Committee To Review Generic Require ents
SUBJECT:
MINUTES OF THE CRGR MEETING NUMBER 335 The Committee To Review Generic Requirements (CRGR) met on Tuesday, January 12,1999, from 9:00 a.m. to 12:30 p.m. to hold,the Committee's 335* meeting. Attachment 1 contains the list of attendees. J. Murphy presided over the meeting as Acting Chairman.
i W. Kane, S. Shankman, W. Hodges, and L. Kokajko - all of NMSS - briefed the Committee on '
their planned approach to licensing reviews and cask certification reviews which will lead to 10 CFR Part 72 amendments in the near future. Attachment 2A contains the staff's presentation material, and Attachment 2-B is the Spent Fuel Project Office Communications Plan. The latter includes office interfacing information as well as a tentative schedule for various activities. The staff's briefing focused on issue C.1-7, " Dual Purpose Spent Fuel Cask Reviews," from the Chairman's Tasking Memorandum. The staff plans to issue a storage-related certificate of compliance through Part 72 rulemaking, and a Part 71 transportation certificate of compliance for dual-purpose spent fuel cask designs. Additionally, the staff plans to make the following process modifications to Part 72: (1) revise Section 72.48 (similar to 10 CFR 50.59) to incorporate NRR initiatives; (2) streamline the rulemaking process to allow for direct and final rulemaking for the certified cask design; (3) clarify general versus site-specific license requirements; (4) expand the scope of Part 72 to cover enforcement; (5) revise geologic and seismologic criteria for dry cask storage; and (6) eliminate the 30-day wait between pre-operational testing and fuelload. The staff proposed to brief the CRGR at the final stage of rulemaking for the dual-purpose cask designs. The Committee decided that it will review the rulemaking related to the Holtec spent fuel storage cask design to determine the extent of its future involvement.
J. Craig (RES), A. Serkiz (RES),'and J. Davis (NRR) presented for CRGR review and endorsement the draft Regulatory Guide DG-1076," Service Level I,11, and lil Protective Coatings Applied to Nuclear Power Plants." Attachment 3A and 3B contain the staff's presentation material. Via this guide, which is a proposed Revision 1 to Regulatory Guide 1.54, the staff endorses various ASTM standards. This effort is consistent with Public Law 104-113 OMB Circular A-119, and NRC's Strategic Plan for FY 1997-2002. This draft guide updates the NRC guidance on the selection, qualification, acceptance, application and maintenance of Class I, il and lll protective coatings, and makes such guidance consistent with industry practice.
The Committee expressed a concern on the backfit aspects of this proposed action.
Consequently, the staff made this proposed guide a forward-fit only and revised the regulatory analysis accordingly. On February 17,1998, a formal CRGR endorsement (Attachment 3-C) for issuance of this draft guide for public comments was relayed to the staff. y k'd W \
030023 ~
g 9909030116 990218 ##N .
PDR REVGP NRCCROR MEETING 335 PDR ,[#[
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William D. Travers M. Mayfield (RES), R. Wessman (NRR), and'D. Jackson (RES) presented for CRGR review and endorsement the draft final Regulatory Guide (RG) 1.84, " Design and Fabrication Code Case !
Acceptability," RG 1.85, " Materials Code Case Acceptability," and RG 1.147, " Inservice '
Inspection Code Case Acceptability." Attachment 4A contains the staff's presentation material.
These guides were not submitted for CRGR review and endorsement prior to issuance for public comments. The Committee offered various comments and recommendations. Most significantly, the Committee noted that various proposed requirements for licensees to submit information to NRC seemed to be incons_istent with other ongoing staff efforts, such as, those related to reducing the bulk ofinformation to be included in the updated FSAR. The Committee also commented on the purpose of the information being sought and the standards to be used in evaluating the heensee-fumished information. The Committee has been informed that these .
documents are currently being revised by the staff. Following NRR and OGC re-concurrence, when the revised guides are.re-submitted, the Committee has instructed the CRGR staff to j evaluate these documents in light of the Committee's comments and recommendations, and ;
..also provide its assessment and recommended action to the CRGR members. If the revisied
{
draft final guides change substantially, they may be re-noticed for public comments. !
' in accordance with the EDO's July 18,1983 directive conceming " Feedback and Closure of '
. CRGR Review", a written response is required from the cognizant office to report agreement or disagreement with the CRGR recommendations in these minutes. The response is to be forwarded to the CRGR Chairman and if there is disagreement with the CRGR recommendations, to the EDO for decision making.
Questions conceming these meeting minutes should be referred to Raji Tripathi (415-7584).
Attachments: As stated cc: Commission (5) SECY M.Knapp,DEDE. F. Miraglia, DEDO J. Lieberman, OE M. Springer, ADM H. Bell, OlG K. Cyr, OGC J.' ~ Larkins, ACRS H. Miller, R-l L. Reyes, R-il J. Dyer, R-Ill E. Merschoff, R-IV C. Paperiello, NMSS A. Thadani, RES - S. Collins, NRR W. Kane, NMSS J. Craig, RES l
1 1
M1!nilOrants' '
M. Mayfield (RES), R.'Wassman (NRR), and D. Jackson (RES) pres nt d for CRGR review and cndorsement the draft final Regulatory Guida (RG) 1.84, "D: sign and Fabrication Code Case Acceptability," RG 1.85, " Materials Code Case Acceptability," and RG 1.147, " Inservice inspection Code Case Acceptability." Attachment 4A contains the staff's presentation material.
These guides were not submitted for CRGR review and endorriement prior to issuance for public comments. The Committee offered various comments and recommendations. Most significantly, the Committee noted that various proposed requirements for licensees to submit information to NRC seemed to be inconsistent with other ongoing staff efforts, such as, those related to reducing the bulk of information to be included in the updated FSAR. The Committee also. commented on the purpose of the information being sought and the standards to be used in evaluating the licensee-fumished information. The Committee has been informed that these
.,. documents are currently being revised by the staff. Following NRR and OGC re-concurrence, when the revised guides are re-submitted, the Committee has instructed the CRGR staff to evaluate these documents in light of the Committee's comments and recor'nmendations, and i also provide its assessment and recommended action to the CRGR members. If the revised l
- draft final guides change substantially, they may be re-noticed for public comments.
l In accordance with the EDO's' July 18,1983 directiverconcoming " Feedback and Closure of ,
' CRGR Review", a written responseJs required from the cognizant office to report agreement or
. disagreement with the CRGR recommendations in these minutes. The response is to be forwarded to the CRGR Chairman and if there is disagreement with the CRGR recommendations, to'the EDO for decision making.
Questions conceming these meeting minutes should 'be referred to Raji Tripathi (415-7584).
Attachments: As stated cc: ' Commission (5) SECY M. Knapp, DEDE F. Miraglia, DEDO ,
J. Lieberman, OE M. Springer, ADM .
H. Bell, OlG K. Cyr, OGC J. Larkins, ACRS. H. Miller, R-l L. Reyes, R-Il J. Dyer, R-Ill E. Merschoff, R-IV C. Paperiello, NMSS A. Thadani, RES S. Collins, NRR W. Kane, NMSS J. Craig, RES M. Mayfield, RES I Distribution:
i File Center (w/attch) PDR (NRC/CRGR) (w/o attch. 2-B and 2-C) SShankman,-
CRGR SF CRGR CF JMurphy DDambly JJohnson, RIV BSheron MVirgilio MFederline JMitchell LKokajko JJohnson, OCM GMillman WHodges . FCherny ' NDudley ASerkiz MMarshall JDavis RCorreia' LCampbell Alee CCarpenter YHuang TSullivan EHackett DJackson KWichman .RWessman Clauron NOsgood DISK / DOCUMENT NAME: S:\CRGR\DMTS-335.WPD To racerve a cop ', indicate "C" = Copy w/o attachment / enclosure. "A*
- Copy with attachment / enclosure. "N" a No cop" NO MARK s NO COPY 1 OFC . CRGR C CRGR C C CRGR C j NAME GWest jc RTripathi h JMurphy DATE - 2.1 (QP99 2 /)f /99 / 19 9 omCiai.RsCoRo Con
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udpi[x, (.!s fj;p%?.t[j CWBR;. No. 335 Meeting xN: :7 pg;:-y :;,in y g : y ,-
CRGR MEMBERS NRC STAFF J. Murphy (Chairman) S. Shankman, NMSS D. Dambly L. Kokajko, NMSS B. Sheron W. Hodges, NMSS J. Johnson W. Kane, NMSS E. W. Brach for M. Virgilio F. Chemy, RES J. Craig, RES A. Serkiz, RES M. Marshall, RES J. Davis, NRR R. Correia, NRR L. Campbell, NRR A. Lee, NRR C. Carpenter, NRR Y. Huang, NRR T. Sullivan, NRR E. Hackett, RES D. Jackson, RES M. Mayfield, RES K. Wichman, NRR R. Wessman, NRR C. Lauron, NRR CRGR STAFF ACRS STAFF R. Tripathi N. Dudley G. West (on detail) l l
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'VI. TOPIC AREA:~ Other Agency Programs and Areas of Focus C.1-7 SPECIFIC ISSUE: Dual-Purnose Cask Reviews Internal Stakeholder Goal Activity Date NMSS/SFPO Ownership This is considered complete with the development of the October 1998 Management & organizational structure (06/98), various intamal guidance Staff documents [SRPs (various dates), stan interactions with applicants (06/98), SER guidance (09/98), interim staff guidance (10/98)), and the team approach (07/98) to dual-purpose spent fuel cask reviews. Other intamal process procedures have been implemented as well.
SFPO has initiated a lessons leamed process and an issues identification program. (Note - supported two Communications Plan strategy meetings.)
Other NMSS Awareness Complete by Communications Plan presentation on October 5, Management October 5,1998. Maintain contact with associated staff 1998 (tMNS, FCSS, members in IMNS (rulemaking, P. Holahan, et al.) and DWM, PMDA) . PMDA (budget and contracts, J. Linehan, et al.) on an as-needed basis for support. Contributed article to NMSS quarterly newsletter (published 03/98), "The Licensing Process for Dry Cask Storage Systems;" and contributed article on SFPO interim staff guidance (next newsletter).
Information provided to Decommissioning Board (11/19/98) and IMNS Licensing Streamlining working group (11/23/98). Will r.ontinue to inform staff at NMSS regional conference ct:1 (12/11/98) and at other times as deemed wppropriate.
NRR/ADPR Awareness Complete by Communications Plan presentation on October 5, Management October 5,1998. SFPO staff has direct contact points - 1998 (DRPE, DRPW C. F. Lyon, DRPW, and P. Ray, DRPM - for I
& DRPM) communications and assistance purposes.
OEDO Buy-in Comple'te by Communications Plan presentation on October 5, October 5,1998. Maintain as-needed contact with OEDO 1998 staff.
October 5, !
OGC. Buy-in Complete by Communications Plan presentation on October 5,1998. Maintain as-needed contact with E. N. 1998 Jenson.
OCA . Awareness Complete by Communications Plan presentation on October 5, l October 5,1998. 1998 OCFO Awareness Complete by Communications Plan presentation on October 5, October 5,1998. 1998
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w VI. TOPIC AREA: Other Agency Programs and Are:.s of Focus g C.1-7 SPECIFIC ISSUE: Dual-Purpose Cask Reviews internal Stakeholder Goal Activity Date OCM Ownership Pending until completion of Holtec HISTAR 100 Pending !
rulemaking and subsequent cask rulemakings. OCM has
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approved streamline rulemaking process to allow for direct / final rulemaking for certified casks in an SRM dated August 26,1998, regarding SECY-98-188.
Other SRMs related to SFPO activities have been issued;
, i.e., revise 10 CFR 72.48 (similar to Section 50.59) in j SRM dated September 25,1998 (SECY-96-171); clarify i general vs. site-specific license requirements in SRM dated July 17,1998 (SECY-98-148); expand scope of Part 72 for enforcement piogram in SRM dated June 30, 1998 (SECY-98-113); revise geologic and seismologic criteria for dry cask storage in SRM dated June 24,1998 (SECY-98-126); and eliminate 30-day wait between pre-operational testing and fuel load in SRM dated April 27, 1998 (SECY-98-056).
SFPO is considering an information briefing of the OCM l Commissioner's Assistants during the first half 1999.
1 OPA Awareness Complete by Communications Plan presentation on October 5, '
October 5,1998. Participated in 1998 NRC Media 1998 i Briefing on dry cask storage issues and maintain designated storage and transportation media briefing papers for OPA. Assist in press releases as-needed.
Planning to participate in 1999 NRC Media Briefing.
SFPO response to Chairman's Tasking Memorandum on i NRC web site; submitted SFPO information on licensing approach for web site to OEDO.
OSP Awareness Complete by Communications Plan presentation on October 5, October 5,1998. 1998 Regions I-IV Awareness Complete by Communications Plan presentation on October 5, Management October 5,1998. SFPO has designated contact points in 1998 (DRS, DRP & regional offices. SFPO staff will supported the upcoming DNMS) Region 111 resident inspector meeting (12/9/98), and will continue with other regional contacts and briefing as appropriate (such as the upcoming 12/11/98 IMNS regional call).
RES Awareness Complete by Communications Plan presentation on October 5, Management October 5,1998. 1998 (DRA & DET) 2
1 VI. TOPIC AREA: Other Agency Programs and Arrs cf Focus C.1-7 SPECIFIC ISSUE: Dual-Purpose Cask Reviews Internal Stakeholder Goal Activity Date l
ACNW Awareness Pending until December 15,1998, briefing on SFPO December 15, activities. 1998 Pending CRGR Buy-in Pending until completion of Holtec HISTAR 100 January 12, rulemaking and subsequent cask rulemakings. SFPO will 1999
, brief on SFPO activities CRGR on 01/12/98 to raise Pending l awareness; subsequent briefings on specific rulemakings I willindicate buy-in. l l
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VI. TOPIC AREA: Other Agency Progrtms and Arms of Focus C.1-7 SPEdlFiC ISSUE: Dual-Purpose Cask Reviews External- ,
Stakeholder - Goal Activity Date Industry _ Ownership Pending. Although significant efforts have been made to 1999 Applicants "get the message out," at conferences (07/98, 09/98), l (including = workshops with NEl, and numerous meetings with vendors, applicants and utilities, it remains unclear whether or not fabricators, the message has been fully received. The goal of SFPO f 1 licensees & CoC is to receive an initial application for s ' dual-purpose cask holders) design of high quality that precludes requests for i additional information. $FPO staff recently supported the l ANS conference (11/17/98) and the NEl Decom'missioning meeting (12/7/98). SFPO will continue -
to monitor this activity and support other venues to com unicate the SFPO message; e.g., upcoming NRR RIC ( /99) and planned NEl workshop (3/99). [See next two external stakeholder items below.)
Industry Owner's Buy-in This is considered complete. This group has the October 1998 Group motivation to grasp the SFPO initiatives as soon as practical since they represent the reactor licensees interest in utilizing the dry storage option. Also, this message has been a theme at the NRC RIC (most recently on 4/15/98), and will be in 1999. [ Considered an important subgroup of Industry Applicants.]
NEl Buy-in This is considered complete with the interaction with NEl August 1998 during workshops (04/16/98, 07/01-02/98,' 08/26/98) and .
several NEl-sponsored conferences that SFPO '
management supports. Informally met with NEl on 12/03/98 (to discuss next workshop in 03/99). ;
[ Considered an important subgroup of Industry j Applicants.)
Congress Awareness This is considered complete as indicated by the budget November testimony, subsequent congressional questions and staff 1998 responses, and legislative language. On an as-needed ;
basis, NRC will apprize'the Congress of SFPO activities.
Also, held two briefings with J. Cannon of Senator Domenici's staff, and provided information to K.
Hunsicker of Senator Murkowski's staff in 11/98.
State and Local Awareness This is considered complete. SFPO has supported the September Governments recent National Association of State Legislators meeting 1998 (09/98), and will continue to do so. On an as-needed basis, SFPO will apprize state and local governments of SFPO activities.
4
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. VI. TOPIC AREA: Other Agency Programs cnd Ar:Is of Focus C.1-7 SPECIFIC ISSUE: Dual-Purpose Cask Reviews External Stakeholder Goal Activity Date Public (General Awareness Pending. While information has been disseminated to Continuous Interest' Groups) people and groups, it is unclear whether or not public l acceptance and confidence in dual-purpose dry cask storage technology has been achieved. SFPO will continue to appropriately respond as needs dictate.
SFPO response to Chairman's Tasking Memorandum on NRC web site; submitted SFPO information on licensing approach for web site to OEDO.
Media Awareness This is considered complete. Participated in 1998 NRC October 1998 Media Briefing on dry cask storage issues and maintain i designited storage and transportation media briefing papers for OPA. Assist in press releases as-needed. l Planning to participate in 1999 NRC Media Briefing. i SFPO response to Chairman's Tasking Memorandum on NRC web site; submitted SFPO information on licensing approach for web site to OEDO. Staff contacts with the trade press have been good.
International Awareness This is considered complete. Staff has increased efforts November in the international community. SFPO supported IAEA 1998 symposium on storage issues in Vienna, Austria (11/98),
and will support future activities as appropriate.
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Designation: D S144 - 97 Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants' This standard is issued under the fixed designauon D .414J the number immediately following the designation indicates the year < l onginal adoption or. In the case of renuon. the seat oflast reusion A number in parenthews indicates the year o(last reapproval , i superscnpt epulon M indicates an cdstonal change since the last rension or re.ipprosal !
INTRODUCTION Protective coatings (paints) have been used extensively in the nuclear industry to protect the surfaces of facilities and equipment from corrosion and contamination by radioactive nuclides in accordance with ALARA. In the absence of a standard method of selecting, testing, and evaluating j coatings, many sites evaluated paints by empirical tests to determine which were useful in their I particular operation. Understandably, the methods'of testing were not uniform throughout the t industry. It has been very difficult, consequently, to compare the results obtained at one site with those obtained at another. Standard tests whereby industrial (nuclear) users of paints systematically prepare specimens and mbject them to selected evaluations, thus permitting uniform comparisons, I are advantageous, internationally as well as domestically. l The designer oflight water-moderated nuclear reactor systems must consider the possibility of a i j Design Basis Accident (DBA) and the subsequent events which might lead to the release or expulsion of a fraction of the fission product inventory of the core to the reactor containment i facility Engineered safety features. principally a reactor containment facility, are provided to i prevent the release of fission products to the biological environment during and after this i I improbable event. The design, fabrication, quality assurance, and testing of these engineered safety features ensure reliable operation and safety under all anticipated conditions. ;
Large areas of the reactor-containment facility are painted with a protective coating. If severe !
delamination, peeling, or flaking causes significant portions of the coating to be discharged into the common water reservoir, the performance of the safety systems could be seriously compromised by the plugging of strainers, flow lines, pumps, spray nozzles, and core coolant channels. ,
/~ The safety requirement for protective coatings is to ensure that failure of the coatings under DBA conditions does not adversely affect the performance of post accident fluid systems.
Therefore, coatings must be qualified to the environmental exposures anticipated during normal plant operation, and during DBA conditions.
This guide is the result of a comprehensive examination of the experience and data that have been developed on protective coatings in the nuclear industry over approximately 40 years.
Standards pertaining to nuclear coatings have historically been covered by ANSI N5.12, N101.2, and N101.4. Responsibility for updating, rewriting, and issuing appropriate ANSI replacement standards has been transferred to ASTM. specifically ASTM Committee D-33, on Protective Coating and Lining Work for Power Generation Facilities.
Quality assurance in the nuclear industry is a mandatory requirement for all aspects of safety related nuclear coatings work. The objective of this guide is to provide a com:1on basis on which to define and specify the performance requirements for the coatings which will be used in Service I Level I and !! areas of a nuclear facility. Regulation 10CFR50.65 defines the requirements for an effective program for maintenance of nuclear power plants. This guide may be used both for coatings applied to new nuclear power plants and to facilitate implementation of the coating
(. aspects of 10CFR50.65. s
- 1. Scope evaluation tests. This guide also provides guidance for 1.1 This guide provides a common basis on which protec- application and maintenance of protective coatings. Under tive coatings for the surfaces of nuclear power generating the environmental operating and accident conditions of facilities may be qualified and selected by reproducible nuclear power generation facilities, encompassing pressur-tzed water reactors (PWR's) and boihng water reactors (BWR's), coating performance may be afTected by exposure
' Tius swde is under the jurudacuon of ASTM Comnunce D43 on Protecuve to any one, all, or a combination of the following conditions:
I Contias and Uning Work for Power Generauon Facdiues and is the direct ionizing radiation; contamination by radioactive nuclides Cuma ed no MarN o$99 and subsequent decontamination processes; chemical and ue blished mbSeEonsi.
) aany pubhahed as D 514 - 9 8. Last prewous ediuon D 5 t 4 - 91. Water sprays; high temperature high-pressure steam; and 461
- 7. ;
Designation: D 3843 - 93 Standard Practice for i Quality Assurance for Protective Coatings Applied to Nuclear f Facilities Ia Tlus standard is issued under the fixed designauon D 3843, the number immediately following the designauon indicates the year of onganal adopuon or, in the case of revtsson, the year oflast revision. A number in parentheses indicates the year o(last reapproval. A supenenpt epstlon (e) indicates an editonal change since the last revision or reapproval.
I . Scope 1
1 2.4 Code ofFederal Regulations:'
10 CFR 50, Appendix B: Title 10, Chapter 1. Energy, Pan l.1 This practice provides a common basis for, and 50, Domestic Licensing of Production and Utilization specifically comprises quality assurance requirements appli- Facilities, Appendix B, Quality Assurance Criteria for cable to, safety related protective coating work in Coating e Nuclear Power Plants and Fuel Reprocessing Plants Service level I areas of nuclear facilities. 10 CFR 21 Reporting of Defects and Noncompliances ,
1.2 Applicable portions of this practice may be used as the basis for limited quality assurance for protective coating 3. Terminology work in Coating Service level !! areas of nuclear facilities. 3.1 Description of Terms Specific to This Standard:
- i.3 This standard does not purport to address-all of the , 3.1.l certification-the written documentation of the safety problems, if any, associated with its use. It is the qualification of personnel or material.
responsibility of the user of this standard to establish appro- 3.1.2 coating applicator-an organization or individual priate safety and health practices and determine the applica- responsible for applying a protective or decorative coating bility ofregulatory limitations prior to use. system.
3.1.3 coating (paint)-a liquid, liquifiable, or mastic com; position that is converted to a solid protective or functional
- 2. Referenced Documents adherent ftim after application as a thin layer.
3.1.4 coating manufacturer-an organization responsible 2,1 ASTAf Standards:
for manufacturing coating materials.
D 3842 Guide for Selection of Test Methods for Coatings 3.l.5 coating system-a polymeric protective film con-for Use in Light Water Nuclear Power Plants 2 ..
sisting of one or more coats, applied in a predetermmed D4227 Practice for Qualification of Coating Applicators rder by prescribed methods.
for Application of Coatings to Concrete Surfaces of 3.1.6 coatmg work-an all-inclusive term to define all Safety-Related Areas in Nuclear Facilities: operations required to accomplish a complete coating job.
D4228 Practice for Qualification of Coating Applicators The term shall be construed to include materials, equipment, for Application of Coatings to Steel Surfaces of Safety- labor, preparation of surfaces, control of ambient conditions.
Related Areas in Nuclear Facilities: application and repair of coating systems, and msoection.
D4537 Guide for Establishing Procedures to Qualify and 3.1.7 Code of Federal Regulations (CFR)-the rules and Certify Inspection Personnel for Coating Work m. Nu- regulations of the United States Federal Government. The code is subdivided into titles, with Title 10 (10 CFR) clear Facilities 2.2 ANSI Standards ~ applying to energy.
N45.2 Quality Assurance Program Requirements for Nu- 3.1.8 deviation-a departure of a characteristic from es-clear Power Plants 2
tablished procedures or from specified requirements.
NQA 1 (86) Quality Assurance Program Requirements for 3.1.9 documentation-any wrinen or pictorial informa-Nuclear Facilities' tion describing, defining, specifying, reporting, or certifying 2.3 ASAfE Standard: activities, requirements, procedures, or results.
NQA-1 (89) Quality Assurance Program Requirements for 3.1.10 inspection-a phase of quality control which by Nuclear Facilities
- means of examination, observation, or measurement deter-mines the conformance of materials, supplies, components, parts, appurtenances, systems, processes, or structures to 8 Thts pracuce is under the Junndicuon of ASTM Committee D H on Eredetermined quality requirements. ,
Protecuve Comung and Linmg work for Pown Generanon Factbues and is the 3,1.11 inspection agency-a person or persons authorizg direct responubihty of D33.03 on Quahty Systems.
Cunent edition approved Feb. is, l993. Pubitshed Apnl 1993. Onginally by the owner or owner's designee to verify conformance pubhsbed as D 3:43 - 80. Last previous edicoa D 3 43 - 89. the coating work.
3 Annual Book of ASTM Standards. Vol 06.02.
3 Available from Amencan Nauonal Standards Institute.13th Floor,11 w.
42nd St., New York NY 10036. $ Available from the Supenntendent of Documents. U.S. Government Pnnons
- Avatlable from the Amencan Society of Mechamcal Engineers,345 E. 47th Office. Washington. DC 20402.
St., NY 10017. .
4
c ._ , .
- El
~
Designation: D 3911 - 95 i
Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) Conditions This standard is issued under the fined designation D 3911; the number immediately fonowmg the designa I onginal adopuon or in the case of rension, the year oflast revision. A number in parentheses indicates the year ofl supersenpt epssion M andicates an editonal change since the last revision or reapprovat INTRODUCTION During a design basis accident (DBA) in nuclear power plants, conditions in the reactor containment will be characterized by elevated temperature and pressure, as well as the presence ,
' o a radiation environment. Water sprays, with or without chemical additives, may be used in the primary containment to suppress the consequences of the incident, to scavenge radioactive i products, and to return the containment to near-ambient conditions. I
- 1. Scope I
- , than the steam turbine pressure. I l.1 This test method establishes procedures for evaluating 3.1.3 chemical spray-a solution of chemicals, such as protective coating systems test specimens under simulated those contained in Table I, which could be used during a loss DBA conditions. Included are a description of conditions of coolant accident (LOCA) to suppress the incident. to and apparatus for temperature-pressure testing, conditions scavenge fission products, and to return the facility to for radiation testing, and procedures for preparing, exam, near-ambient conditions.
ining, and evaluating the samples.
3.1.4 coating f paint) system-a polymeric protective film 1.2 The values stated in inch-pound units are to be consisting of one or more coats applied in a predetermined regarded as the standard. The values given in parentheses are order by prescribed methods to a defined substrate.
gfor information only. j 3.1.5 cracking-a break or a split in the coating (paint) 1.3 This standard does not purport to address all of the system extending through the (nim or to the substrate.
safety concerns, if any, associated with its use. It is the 3.1.6 curing-the transformation of a coating or other responsibility ofthe user of this standard to establish appro- material into a solH phase or film.
priate safety and heahh practices and determine the applica.
bility of regulatory limitations prior to use. 3.1.7 DBA-a generic term for any one of a family of accident conditions which can result from postulated events.
- 2. Referenced Documents These conditions are generally associated with the rupture of high energy piping. The more commonly recognized acci- {
t 2.1 ASTM Standards dent conditions used to evaluate coating systems for primary D714 Test Method for Evaluating Degree of Blistering of c ntainment are the LOCA or main steam pipe break. {
i Paints 2 3.1.8 derom:ed water-water prepared by an ion ex-D4082 Test Method for EfTects of Radiation on Coatings change process meeting the requirements of Specification )
Used in Light-Water Nuclear Power Plants 3 D 1193, Types 11 and Ill. i j
D 5139 Specification for Sample Preparation for Qualifica- 3.1.9 delammation-separation of one coat or layer from tion Testing of Coatings to be Used in Nuclear Power another coat or layer, or from the substrate. ;
Plants 3 ,
3.1.10 engineered safety system-a system designed to mitigate the effects of a design basis accident.
- 3. Terminology 3.1.11 irradiation-exposure to ionizing radiation.
3.1.l2 light water nuclear reactor-an apparatus, using
.l.1 i n -the formation of bubbles in a coating (paint) film. @ watu as a moderator, in wMd MonaW map ,n ,
arrayed so that controlled nuclear fission may be sustained in 3.1.2 boiling water reactor (BWR)-a reactor in which the a self-supp rting chain reaction.
water moderator-coolant is boiled directly within the reactor 3.1.13 LOCA-the specific conditions anticipated fol-core. The pressure in the reactor vessel is only slightly greater 1 wing a loss of coolant accident that would expose the <
TABLE 1 Typical Spray Sohdons ;
'This method is under the junsdicuon of ASTM Committee D.33 on Composition Chemical compotnd Protecove Comung and Laning work for Power Generauon Facthues and as the Concentraton (in Deioruzad Water) direct responsitulity of Subcommittee D33.02 on service and Matenal Parameters' A e 2000 to 4000 ppm boron Current edition approved Oct.10. I995. Published December 1995. Onsinally Sodium hydroxide adiust solution to pH 9 0 to 10.0 published as D 3911 - 80. Last previous ediuon D 391! - 89. B Bonc acid 8 2000 to 4000 ppm baron Annual BaA of ASTAf Standards. Vol 06.01. Hydrazine 50 ppm unreacted excess 5
Annual Bork ofASTAf Standards. Vol 06 02. Sodium phospnate. dibasac adpust solution pH to 6.8 to to 0 212
)
4
- g. *
~
( . f Designation: D 4537 - 91 (Rrpproved 1996)
V l he quahtatne i measures a irator of Ten
'e level of the ned probe or Standard Guide for i
'f the deepegg Establishing Procedures to Qualify and Certify inspection
,*'**"',*d a ,j Personnel for Coating Work in Nuclear Facilities
'C0pe for the
, methods art This standard is issued under the thed deugnation D n", the number immediately following the designauon indacates the tear of
' ope and for l onginal adopuon or, in the case of reviuon. the > car o(last reuuon. A number in parentheses indicates the year of last reapproval. A l il valley, the supersenpa epsilon M indicates an editonal change unte the last revision or reapprovat Ithe tape or !
(
- l. Scope 3 e'xecute the responsibilities of the appropriate certificattor j f 1.1 This guide delineates the requirements for develop- level. j tiern; sus ment of procedures for the qualification of personnel who 3.1.4 training-the program developed to ensure that '
perform inspection of coating work. These activities are penonnel receive the knowledge and skills necessary for accomplished to verify conformance to specified require- qualificadon.
ments for nuclear facility coatings work whose satisfactory performance is required in order not to compromise systems
- **"#' I used to mitigate the consequences of postulated accidents. 4.1 The requirements of this guide apply to penonnel 1.2 This guide provides a uniform interpretation of the who perform inspections of coating work during (1) fabrica-requirements in ANSI /ASME N45.2.6-1978 for the inspec. tion, (2) receipt of items at the construction site, 0) tion of coating work in nuclear facilities. construction, (4) pre-operational and startup testing, and d) 1.3 This guide meets the intent of ANSI /ASME NQA-l. operational phases of nuclear facilities.
1.4 It is the intent of this guide to provide a recommended 4.2 It is the responsibility of each organization partici-basis for qualification, not to mandate a singular basis for all pating in the project to ensure that only those personnel qualifications. Variations or simplifications of the qualifica. within their respective organizations who meet the require-tions described in this guide are appropriate for special ments of this guide are permitted to perform inspection coating work outside of safety-related areas, activities covered by this guide.
1.5 This standard does not purport to address ali erthe 4.3 The organization (s) responsible for establishing the safety concerns if any, associated with its use. h is the applicable requirements for activities covered by this guide responsibility of whoever uses this standard to consult and shall be identified, and the scope of their responsibility shall establish appropriate safety and health practices and dete,. be documented. Delegation of this responsibility to other mine the applicability ofregulatory limitations prior to use. qualified organizations is perTnitted and shall be docu-mented.
4.4 It is the responsibility of the organization performing
- 2. Referenced Documents these activities to specify the detailed methods and proce-2.1 ANS//AS.ifE Standards: dures for meeting the requirements of this guide, unless they ANSI /ASME N45.2.6 Qualifications of Inspection. Exam. are otherwise specified in the contract documents.
ination, and Testing Personnel for Nuclear Power Plants2 ANSI /ASME NQA-1 Quality Assurance Program Re. 5. General Requirements for inspection Personnel quirements for Nuclear Facilities.2 5.1 Provisions shall be made for the indoctrination of personnel as to the technical objectives of the project, the
- 3. TennMogy codes and standards that are to be used, and the quality assurance elements that are to be employed.
3.1 Definitions of Terms Specific to This Standard.
5.2 The need for formal training programs shall be 3.1.1 certification-written documentation of qualifica- determined, and such training activities shall be conducted tion.
3.1.2 coating work inspection-a phase of quality control as required to qualify personnel who perform inspections. {
On-the-job participation shall also be included in the pro- I which, by means of examination, observation, or measure-gram, with emphasis on first-hand experience gairied through !
ment, determines the conformance of coating work to actual performance ofinspections. I predetermined quality requirements.
5.3 A candidate's qualifications for certification shall be 3.1.3 quahfications-skills, training, and experience re- initially determined by a suitable evaluation of the candi- 4 quired for personnel to perform properly the duties and date's education, experience, training, examination results, and capability demonstration.
' This sunde is under the junsdicuan of ASTM Comnunce D 33 on Protecuve 5.4 The job performance of coating work inspection Coating and tining work for Power Generanon Factht es and is the direct personnel shall be reevaluated at periodic intervals not to responatehty or subcomaunce o33 04 on inspecuan. exceed three years. Reevaluation shall be by evidence of current edinon approved Aus is, swi. Pubbsbed ociober swi. onantally pubiuhed as D 4537 - 86. tmt prevwus editon D 4537 - 86. continued satisfactory performance or redetermination of j 3Available from A a suonal standards losutute. It W. 42nd street, capability in accordance with 5.3. If, during this evaluation 1 or at any other time, it la determined by the responsibile i organization that the capabilities of an individual are not in 315 -
9
Designation: D 5163 - 91 (Reapproved 1996)
~
Standard Guide for i
Establishing Procedures to Monitor the Perforrnance of Safety Related Coatings in an Operating Nuclear Power Plant This standard is issued under the fined designanon D 5163 : tbc nurnber immediately followmg the designation mdicates the ) car of onginal adoption or. m the case of revision. the year oflast revision A number in parentheses mdicates the year oflast reapproval A superienpt epsdon N indicates an editonal change since the last revivon or reapproval I SCOPE d F 1133 Practice for Inspecting the Coating System of a k 1.1 This guide covers procedures for establishing a pro. Ship's Undenvater Hull and Boottop During gram to tronitor Senice level I coating systems in operating Drydocking 8 nuclear power plants. Monitoring is an on going process of 2.2 ANSIStandard:
evaluating the condition of the in-service coating systems. N45.2.6--Qualification of Inspection, Examination, and 1.2 It is the intent of this guide to provide a recommended Testing Personnel for Nuclear Power Plants' basis for establishing a coatings monitoring program, not to 2.3 SSPCStandard; i mandate a singular basis for all programs. Variations or SSPC-PA2-Measurement of Dry Paint Thickness With simplifications of the program described in this guide may be Magnetic Gages 7 appropriate for each operating nuclear power plant de. 2.4 NACE Standard; pending on their licensing commitments. Similar guidelines RP0188-88-Standard Practice Discontinuity (Holiday) may be applicable for Senice Level 11 and other areas Testing of Protective Coatings 8 l outside containment.
% l.3 This standard does not purport to address all of the ' 3. Significance and Use safety concerns, if any, associated with its use. It is the responsibihty ofthe user ofthis standard to estabhsh appro- 3.1 Establishment of an in-senice coatings monitoring priate safety and health practices and determine the apphca. program permits planning and prioritization of coatings bility of regulatory limitations prior to use, maintenance work as needed to maintain coat integrity and performance in nuclear Senice Level I coating systems. For
- 2. R:ferenced Documents additional information on nuclear maintenance coating 2.1 ASTM Standards; w rk, refer to ASTM Manual on Maintenance Coatings for D6 0 est Meth s for Evaluating Degree of Rusting on m rkitoring program enables early identifi-3 A oat D 714 Test Method for Evaluating Degree of Blistering of cati n a d detection of potential problems m coating sys- ,
pg3 tems. Some Senice Level I coating systems may be known in advance to be suspect, deficient, or unqualified. Monitonng D 1186 Test Methoils for Nondestructive Measurement of Dry Film Thickness of Nonmagnetic Coatings Applied coating performance will assist in developing follow-up p ires to resolve any significant deficiency relative to to a Ferrous Base 3 D3359, Test Methods for Measuring Adhesion by Tape 33 a ed coatings may generate debris under design t est D4121 Practice for Photographic Documentation of basis accident conditions that could adversely affect the Coating and Limng Failures and Defects' performance of the post-accident safety systems. A coatings monitoring program may be required to fulfill safety analysis D4537 Guide for Establishing Procedures to Qualify and report commitments for Senice Level I coating work in a l Certify Inspection Personnel for Coating Work in Nu-nuclear power plant facility.
clear Facihties2 D4541 Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers 2 4. Responsibility F 1130 Practice for Inspecting the Coating System of a 4.1 The owner / operator shall identify the department or Ship 5 group within the organization to be responsible for estab-F 1131 Practice for Inspecting the Coating System of a lishing the applicable requirements for activities or proce-Ship's Tanks and Voids 5 dures covered by this guide and shall document the scope of F 1132 Practice for Inspecting the Coating System of a their responsibility, Owner / operator delegation of this re-Ship's Decks and Deck Machinery 5 sponsibility to other outside qualified organizations is per-8 Ttus guade is under the Junsdicuon of ASTM Committee D 33 on Protecuve
- Avadtble from Amencan Nabonal Standards losutute,11 W. 42nd Street, Comung and taning Work for Power Generation facthties and is the direct 13th Floor, New York, NY 60036.
responsitxhty of Subcommittee D33.04 on Inspecuon. ' Avadable from Steet Structures Painting Council,4400 Fath Ave., Pittsburgh.
Current edition approved Oct. 3,1991. Pubbshed December 1991. PA 15213.
a Annual Book ofASTM Standards, Vol 06.02. 8 Avadable from National Assocsauon of Corronon Engmeers, P. O. Boa 8 Annual Book ofASTM Standards, Vol 06 01. 218340, Houston. TX 77288.
- Disconunued; see 1992 Annual Book of ASTV Standards Vol 06 01. ' Avadab6e from ASTM Headquarten, 100 Barr liarbor Dr., West s Annual Book ofASTM Standards, Vol of.07. Conshobocken. PA 19428-2959 485
V O osies mitted and shall be documented. trolled, and vital areas, and escorted or unescorted clearance 4.2 It is the responsibility of the owner / operator or his as required, -
g designee performing these activities to specify the detailed 7.2.2 Radiological history including prior radiation expo- g methods and procedures for meeting the applicable require- sure for all personnel involved, mt ments of this guide. 7.2.3 Heahh physjes classroom training in the use of cra
} 4.3 The owner / operator or his designee shall assign a radiation detection and monitoring devices and procedures me i
coordinator to be responsible for supervising coating inspec- for wearing anticontamination clothing, tw tion activities, data collection and documentation, and for 7.2.4 A radiation work permit based on health physics y ensuring that inspection personnel are adequately trained radiological survey of the work location, pro and qualified. 7.2.5 Compliance with radiation work permit require-Car l 4.4 The, owner / operator shall assign responsibility for ments and other special radiation controls unique to each the l
cvaluating the results of inspection activities carried out work location, and under the coatings performance rnonitoring program. 7.2.6 Issuance of dosimetry. inst 9
7.3 The safety requirements of the facility owner / operator Test
- 5. Frequency must be met when performing allinspection operations.
to d 5.1 Frequency ofin-service coating inspection monitoring caus shall be determined by the owner / operator. In operating 8. Personne) Requirements, Qualifications, and Training g nuclear power plants certain monitoring activities may be 8.1 The facility owner / operator shall specify the require- 'and '
restricted to major maintenance outages or refueling outages.. ments and guidelines for qualification and training of 9. . ,
It is a good practice to perform inspections during each inspection personrie! involved in the program. However, Defe ;
refueling outage or during other major inaintenance outages inspectors and the coordinator shall be knowledgeable coat- 9.. l as needed. ~
ings personnel meeting the requirements of ASTM Guide the D 4537 or ANSI N45.2.6. The coordinator shall, as a aloni l
- 6. Records and Past IIIstory minimum, be a Lesel !! Coatings inspector. duett 6.1 Coating performance will depend on the operating 8.2 The evaluaur shall be a person knowledgeable and 9.:
conditions experienced by the coating systems. Records of experienced in nuclear coatings work. coati these conditions shall be obtained for each operating unit. and These may include, but not be limited to, ambient condi- 9. Inspection Plan facili tions, temperatures, humidity, immersion, splash and 9.1 The owner / operator shall develop a plant specific inspe spillage, chemical exposures, radiation exposures, previous inspection plan to accomplish the objectives of the moni. F i 12 decontamination procedures, abrasion and physical abuse, toring program. A generaf visual inspection shall be con. Pract and stan-up/ shutdown frequency. Any change in service ducted on all readily accessible coated surfaces during a comr criteria or modifications of the physical design must be walk-through. Aller the walk-through, thorough visual in- ,
9.4 identified and dated. spections shall be carried out on previously <iesignated areas tive o 6.2 The last two performance menitoring reports per- and on areas noted as deficient during the walk-through. A thickt taining to the coating systems shall lv reviewed prior to the thorough visual inspection shall also be carried out on all ! (Test m:nitoring process Other past coatings history data to be coatings near sumps or screens associated with the Emer.
RP01 1 reviewed may include: gency Core Cooling System (ECCS). The inspection plan ator. !
6.2.1 Copies of coating specifications, manufacturer's shall address the following based on specific owner / operator defect i product data sheets, and application procedures for in-place requirements: 95 !
coatings. 9.1.1 A pre-inspection briefing to farniliarize all inspec. may i i 6.2.2 Quality control documentation for the existing in- tion personnel with objectives of the inspections, procedures , markt I place cc" ting systems and their application, to be followed, and precautions to be taken, 35 mr; 6.2.3 Copies of previous inspection or monitoring reports. 9.1.2 Monitoring team (s) assignments to specific areas for >lene )
6.2.4 Documentation pertaining to any maintenance inspection (s), and i work performed on existing coating systems. 9.1.3 Location maps dividing the plant into identifiable 10. Ri !
areas for inspection activities to be issued to inspection 10'i i
- 7. Premonitoring Procedure teams. The maps shall also identify items / areas requiring uation 7.1 Prior to conducting an inspection of the coating special testing, if any. The locations of all defects and of all ments systems, the responsible organization shall ensure that the tests performed shall be recorded on the maps so that Coatin necessary services and equipment required for inspection are additional testing, recoating, and further monitoring may be inform provided. Factors that must be considered while planning the performed. lo.i inspection activities include, but are not limited to, lighting, 9.2 During walk-through, visually examine coated sur- ration.
access to coated surfaces, cleaning surfaces of any deposit or faces for any visible defects, such as blistering, cracking. 10.1 build up, ventilation and, where necessary, special under- flaking / peeling, rusting, and physical damage. .
repaire!
water inspection requirements. 9.2.1 Blistering-Compare any blistering found to the bepod 7.2 Station access procedures for Service Ixvel I coating blistering pictorial standards of coatings defects (refer to Test surseill systems monitoring shall be followed. While access proce- Method D 714) and record size and frequency. If the blisters 10.1 dures may vary from plant to plant, specific station access are larger than those on the companson photographs, given i procedures may include: measure, record size and extent, and photograph. Report if io,;
7.2.1 Security clearance for protected, radiation con blistered portions are intact. map fd 4%
F q.,.
O o sies
- ""C' 9.2.2 Cracking-Cracking can be limited to the one layer "P* of coating or extend through to the substrate. Measure the ce*rau mea-a uma=c *accm length of the crack or if extensive cracking has occurred. "'~"" ~~- "" ' " *~
- I measure the size of the area alTected. Determine if ~"~'*""
the ~
l dures cracking is isolated or is part of a pattern. Record measure.
~~
ments and describe crack depth and pattern on the inspec. ~r t === = = _
ysics tion report. Photograph the area affected. "
9.2.3 Flaking / Peeling / Delamination-Measure the ap.
l proximate size of the peels and note the pattern formed. g,g ( ,, f y y ~ 7 , = = 2 each , Carefully test to see if lifting can be easily achieved beyond the obvious peeled area. Note all observations on the I
' inspection report and photograph the area alTected.
rator 9.2.4 Rusting-Compare with the pictorial standards of Test Method D 610 to determine the degree of rusting. Try to determine the source of rusting (that is, is it surface stain I caused by rusting elsewhere, or is it a failure of the coating
! aire- allowing the substrate to rust). Photograph the affected area .
I of - and record observations on the inspection report. i ver, 9.2.5 If no defects are found, mark " Coating Intact, No cat- Defects" on the inspection report.
, ade 9.2.6 If portions of the coating cannot be inspected, note I sa i the specific areas on the location map-inspection report, along with the reason why the inspection cannot be con-ducted.
and 9.3 Written or photographic documentation, or both of
{ coating inspection areas, failures, and defects shall be made __
and the process of documentation standardized by the facility owner / operator. Written documentation practice for ific inspection of coating system as given in Practices F 1130. FIG. 1 Inspeccon Dets Sheet ni.
m.
F !!31, F 1132, and F 1133 may be adopted as a guideline.
Practice D4121 provides one method to obtain consistent,
- a comparable close-up photographs.
in- ,, f, ',,
9.4 For coating surfaces determined to be suspect, defec- ,,,,,,,,,,,,,,,c
- as .. . i .no A tive or deficient, one or more physical tests, such as dry-a film $~" 1i i i i i i i i ii iiiir thickness (Test Methods D 1186 and SSPC PA 2), adhesion 6"",', , , , , , , , ,,,E all =-
la,,
- tr-(Test Methods D 3359 and D 454l), and continuity (NACE- lllll DF RP0188-88), may be performed when directed by the evalu- " " " "
l 2n ator. Samples may be gathered, and the size and extent of or defective patterns may be described.
9.5 Instruments and equipment needed for inspection f'~*""
{
f[
- c. '"
may include, but not be limited to, flashlights, spotlights. . *"rU~,=/+'
es marker pen, mirror, measuring tape, magnifier, binoculars.
a YLg ',if** _ IM ~'"'
)r 35-mm camera with or without wide angle lens, and polyeth-ylene zip lock sample bags.
3 1
v~
M w ,
- e / -,
- 10. Reporting and Documentation ,7/,, ,
" (,,, .m. j' 10.1 Inspection reports for submittal to responsible eval- '
'f, E "'
' uation personnel based on specific owner / operator require- _- . ,,,. g '
5
, 4 ments should be prepared by a qualified Level II or Level !!! . '
9 j , -~-
- Coatings inspector and should include at least the following information: ' 3 . !, ' ,
' 10.1.1 A list and location of all areas evidencing deterio- . .
ration, n 6 '
'.u,..,..
" g""",
10.1.2 Prioritize the repair areas into areas that must be ' .
l repaired during the same outage and areas where repair can ge y; g n Jlr m * 'd
$ j.
i '4f,7, b ,.. .
be postponed to future outages, keeping the coating under """"?' '**~~"~
surveillance in the interim period,
.10.1.3 Inspection Data Sheets-A typical data sheet is given in Fig.1, aid 10.1.4 Photogic.phic Documentation-A typical location ""*'""
map for photographic identification is given in Fig. 2. The FIG. 2 M ,, Documentagon Loceton Map 487
' . ,e 6 D 5163 location and direction of all photographs shall be recorded would include an analysis of the reasons or suspected reasons on the maps for comparison with past and future photo- for failure. The repair work should be prioritized into major graphs and to record existing conditions. Numbers 3-1 and minor defectise areas. A recommended corrective plan through 3-13 in Fig. 2 depict the location of the photogra- of action must be provided for the major defective areas so pher and the directions of the view, that the plant can repair these areas, if appropriate, during the same outage.
- 11. Evaluation
!!,1 The inspection report shall be evaluated by the 12. Keywords responsible evaluation personnel. The evaluator shall pre- 12.sl coatings monitoring program; coating peiformance; pare a report that includes a summary of findings and inspection; maintenance; nuclear power plant; safbty related recommendations for future surveillance or repair; this coatings; Service Ixvel I; surveillance the Amerman Socoety for Testong and Matenals takes no position respectvng the vasodity d any patent oghts asserted un connection wth any Rem mentnaned kt !!us standard. Users d ttus standard are expreesty advssed that determonetsort d the vahdty d any such treent nghts, and the rak d Witnngement d such rnghts, we entsrely theor own responstbrity.
Thos standard tu subsect to revoston at any time by the responsible technocal committee and must be revnwed every trve years and it not revned, enhor reavoved or wthdrawn. Your comments are vsvted eetter tor rovason d stus standard or for addsonal standards and shoukt be addreised to ASrM Headquarters Your comments will rocerve carotut consoderettort at a tseetitsg d the respctlsibk techrucat Commttee, whch you may attend of you feel that your Ctr1ments have not recerved a fair beenng you should snake your vows known to the ASrM Committee on Standards.100 Barr Harbor Ovve. West Conshohocken. PA t9428 l
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PRESENTATION MATERIAL USED BY THE STAFF l l
ATTACHMENT 3-B
a RELATIONSHIP BETWEEN ~
GENERIC LETTER 98-04
' (COATINGS AND DEBRIS IN CONTAINMENT)
AND DG-1076 i Presented by :
J. A. Davis -
EMCB/DE/NRR Generic Letter 98-04 ,
Team J. A. Davis and C. L. Lauron, EMCB/DE/NRR L. L. Campbell, HQMB/DRCH/NRR R. M. Lobel, SCSB/DSSA/NRR
e
\
.~
2 RELATIONSHIP BETWEEN GENERIC LETTER 98-04 (COATINGS AND DEBRIS IN CONTAINMENT)
AND DG-1076 1
The GL Requests information on Current Coatings Programs l Relative to Design Licensing Basis The Staff has Started the Review on about 10 Submittals About Half of the Submittals State that the Licensee has Committed to RG 1.54 All Meet Their Licensing Basis Almost all Have Committed to 10 CFR 50, Appendix B for all Future Containment Coating Work Use of DG-1076 is an Acceptable Method for Complying i With NRC Regulations !
The Staff has not Determined if Design / Licensing Bases are Adequate I
- s. ,
3 NRR USES FOR DG-1076 a' Future Updates of the SRP for Coatings Can be Referenced in new Applications for Construction Permits and Operating Licenses Can be used to Satisfy 10 CFR 50, Appendix B Requirements for Future Coating Work.if Used With the Owners QA Program Potential use in NRC Oversight of DOE i
i
/ l Minutes of CRGR Meeting No. 335, January 12,1999 I
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CRGR ENDORSEMENT OF DG-1076
\
I ATTACHMENT 3-C i
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{ } R_aji Tripathi- CRGR ENDORSEMENT OF D'G-1076 Ea~g[1 From: Raji Tripathi j To: Jack Strosnider, John Craig '
Date- Wed, Feb 17,1999 1:13 PM
Subject:
CRGR ENDORSEMENT OF DG-1076 )
On January 12,1999, the Committee To Review Generic Requirements (CRGR), at its 335th meeting
. reviewed the subject draft guide presented for the Committee's endorsement. Subsequently, Al. Serkiz (RES) provided a revised version of the guide which appears to have addressed the Committee's comments and recommendations. Specifically, we note that the guide now is forward-fit only; the Reg.
Analysis has been modified accordingly and duly concurred by the sponsoring Division Directors and OGC. Furthermore, the implementation section has been revised to include the applicability of the guide to the applicants for combined licenses. Additionally, the CRGR staff made one minor editorial change to the wording used in the Regulatory Analysis, as noted in the (red-line/ strike-out) text in the attached file.
The CRGR Chairman has determined that there is no need for circulation of the revised proposal to the Committee members, and has endorsed this guide for issuance for public comments. !
I Please call me if you have any questions... Raji (415-7584) i l
CC: Aleck Serkiz, Brian Sheron, Dennis Dambly, Garm.. l l
. l l
4 4-
U.S. NUCLEAR REGULATORY COMMISSION February 1999
[gmg\
OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1
- y j* Draft DG 1076 DRAFT REGULATORY GUIDE a% .eee./
Contact:
A.W. Serkiz (301)415-6563 DRAFT REGULATORY GUIDE DG-1076 (Proposed Revision 1 to Regulatory Guide 1.54)
SERVICE LEVEL I, ll, AND lli PRdTECTIVE COATINGS APPLIED TO NUCLEAR POWER PLANTS A. INTRODUCTION in Appendix A to 10 CFR Part 50, " General Design Criteria for Nuclear Power Plants,"
Criterion 1, " Quality Standards and Records," requires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Appendix A also requires that a quality assurance program be established and implemented in order to provide adequate assurance that these structures, systems, and components will satisfactorily perform their safety functions, in Appendix A to 10 CFR Part 50, Criterion 4, " Environmental and Dynamic Effects Design Bases," requires that structures, systems, and components (SSCs) important to safety be designed to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents.
In 10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," establishes overall quality assurance program requirements for the design, fabrication, construction, and operation of safety-related nuclear power plant SSCs.
The maintenance rule,10 CFR 50.65, " Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," includes in its scope all safety-related SSCs and those non-safety-related SSCs: (1) that are relied upon to mitigate accidents or transients or are used in plant This regulatory guide is being issued in draf t form to involve the pubhc in the deveinpment of a regulatory position in this area. As a draf t being issued for pubhc comment, it does not represent an offcial NRC statf position.
Public comments are being solicited on the draf t guide (including any implementation schedule) and its associated regulatory analysis or value/ impact statement. Comments 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. Copies of comments received may be examined at the NRC Public Document Room,2120 L street NW., Washington, DC, Comments will be most helpfulif received ,
by Requests for sangle copies of draft or active regulatory guides (which may be reproduced) or for placement on an automatic distribution list for single copies of future draf t guides in specife divisions should be made in writing to the u.s. Nuclear Regulatory Commission. Washington DC 20555-oo01, Attention: Reproduction and Distribution services section, or by f ax to (3011415 2289; or email to DISTRIBUTION @NRC Gov.
i-e emergency operating procedures; (2) whose failure could prevent safety-related SSCs from fulfilling their safety-related function and (3) whose failure could cause a reactor scram or an actuation of a safety-related system. To the extent that protective coatings meet these criteria, they are within the scope of the maintenance rule. The maintenance rule requires that licensees monitor the effectiveness of maintenance for these protective coatings (as discrete systems or components or as part of any SSC) in accordance with 10 CFR 50.65(a)(1) or (a)(2), as appropriate. Further guidance is provided in Revision 2 of Regulatory Guide 1.160, " Monitoring the Effectiveness of Maintenance at Nuclear Power Plants" (Ref.1).
This revision to Regulatory Guide 1.54 is being developed in accordance with Public Law 104-113, OMB Circular A-119, and NRC's Strategic Plan for FY 1997 - 2002, which encourages industry to develop codes, standards, and guides that can be endorsed by the NRC and carried out by industry. The ASTM standards cited in the Regulatory Position of this guide for the selection, qualification, application, and maintenance of protective coatings in nuclear power plants have been reviewed by the NRC staff and found to be acceptable with the exceptions noted.
Regulatory guides are issued to describe to the public methods acceptable to the NRC staff for implementing specific parts of the NRC's regulations, to explain techniques used by the staff 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. Regulatory guides are issued in draf t form for public comment to involve the public in developing the regulatory positions and, therefore, such draft regulatory guides do not represent official NRC staff positions.
The information collections contained in this draft regulatory guide are covered by the requirements of 10 CFR Part 50, which were approved by the Office of Management and Budget, approval number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a current!y valid OMB control number.
B. DISCUSSION Protective coatings (paints) have been used extensively in nuclear power plants to i protect the surfaces of facilities and equipment from corrosion and contamination from 2
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-:' 7 radionuclides and for wear prot'ection during plant operation and maintenance activities. For plants that have a design basis that includes a commitment to Regulatory Guide 1.54, the regulations cited above require that protective coatings be qualified and capable of surviving a design basis accident (DBA) without adversely affecting safety-related SSCs needed to mitigate the accident.
In July 1973, Regulatory Guide 1.54, " Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants," was issued to describe an
- acceptable method for complying with the NRC's quality assurance requirements with regard to protective coatings applied to ferritic steels, aluminum, stainless steel, zinc-coate'd (galvanized)' steel l concrete, or masonry surfaces of water-cooled nuclear power plants. The
~
presumption was that protective coatings that met these guidelines would not degrade over
. the design life of the plant. However,- operating history has shown that undesirable
' degradation, detachment, and othdr types of failures of coatings have occurred (Ref. 2).
Detached coatings from the suostrate that are transported to emergency core cooling shstem intake structures may make those systems unable to satisfy the' requirement in 10 CFR 50.46(b)(5) to provide long-term cooling.
- Regulatory Guide 1.54 conditionally endorsed ANSI N101.4, " Quality Assurance for Protective Coatings Applied to Nuclear Facilities," and indirectly endorsed guidance provided in ANSI N101.2, " Protective Coatings (Paints) for Light Water Nuclear Reactor Containment.
Facilities." ANSI N101.4 and N 101.2 were formally withdrawn in 1988: responsibility for ,
updating, rewriting, and issuing appropriate replacement standards was transferred to the
' American Society for Testing and Materials (ASTM), specifically ASTM Committee D-33 on Protective Coating and Lining Work for Power Generation Facilities. However, Regulatory Guide 1,54 was not revised as new ASTM Standards were developed for the application and maintenance of NPP protective coatings.
ASTM D 3843 93, " Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities" (Ref. 3), was approved and issued by ASTM as a partial replacement for ANSI N101.4. ASTM D 3911-95, " Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA)
Conditions". (Ref. 4), has been approved and issued by ASTM to replace the DBA test standard that was referenced in ANSI N101.4 and Regulatory Guide 1.54.
ASTM D 5144-97, " Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants" (Ref. 5), has been developed and issued by the ASTM to provide a 3
( .
I !
common basis on which protective coatings for the surfaces of nuclear power generating I facilities may be qualified and selected by reproducible evalua' tion tests. This ASTM standard ,
I provides guidance for the application and maintenance of protective coatings under the expected environmental, operating, and postulated accident conditions for pressurized water ]
reactors (PWRs) and boiling water reactors (BWRs).
I
- c. REGULATORY POSITION l
- 1. GUIDANCE IN ASTM STANDARDS 1
' l ASTM D-5144-97 (Ref. 5) and the other ASTM standards discussed below provide '
l guidance on practices and programs that are acceptable to the NRC staff for the selection, application, qualification, inspection, and maintenance of protective coatings applied in i
nuclear power plants.
The quality assurance provisions and guidance contained in the standards in this Regulatory Position are generally acceptable and provide methods acceptable to the NRC staff for complying with the pertinent quality assurance requirements of Appendix B to 10 CFR Part 50 subject to the following two exceptions. .
(1) When using this regulatory guide, NRC licensees should meet the quality assurance provisions and guidance contained in the standards in this regulatory guide and must also meet the commitments and provisions contained in their Quality Assurance Program Description.
(2) Service Level 1,11, and lit coatings are defined as:
Service Level I coatings are used in areas where the coating failure could adversely affect the operation of post-accident fluid systems and thereby impair safe shutdown.
With few exceptions, Service Level 1 applies to coatings inside primary containment.
Service Level 11 coatings are used in areas where coatings failure could impair, but not prevent, normal operating performance. The functions of Service Level 2 coatings are to provide corrosion protection and to improve the ability to decontaminate those areas outside primary containment that are subject to radiation exposure and radionuclide contamination.
Service Level 111 coatings are used on any exposed surface area located outside containment whose failure could adversely affect normal plant operat ion or orderly and safe plant shutdown.
4
s., .-
ASTM D-5144-97_ (Ref. 5) addresses by reference the preparation of test specimens, radiation tolerance testing, decontaminability of coatings, physical properties, chemical resistance tests, fire evaluation tests, DBA testing, surface preparation, coating application and. inspection, and thermal conductivity _ testing. Therefore,' ASTM D 5144-97 can be
. viewed as a top-level ASTM standard that incorporates by reference other key ASTM !
standards as shown in Figure 1.
' 2.
QUALIT ASSURANCE-
~
ASTM D 3843-93 (Ref. 3) provides quality assurance practices that are acceptable to
.s -
the NRC staff and are applicable to safety-related protective coating work in coating Service '
Level I areas of nuclear facilities.' Applicable portions of practices described may be used as the basis for limited quality assurance for protective coating work in coating Service Lebel 11 areas of nuclear facilities.
ASTM D 5139-96 (Ref. 6) provides guidance that is acceptable to the NRC staff on the size, composition, and surface preparation for test samples of protective coatings for use in qualification testing of coatings to be used in nuclear power plants as described in ASTM D 3911-95 and D 4082 95 (Refs. 4 and 7). ,
ASTM D 3911-95 (Ref. 4) provides guidance that is acceptable to the NRC staff on l procedures 'for evaluating protective coating systems test specimens under simulated DBA !
conditions. ASTM D 3911-95 also provides guidance on conditions and test apparatus for temperature-pressure testing, conditions for radiation testing, and procedures for preparing, examining, and evaluating samples.
ASTM D 4082-95 (Ref. 7) provides' a standard test method that is acceptable to the NRC staff for evaluating the effects of _ gamma radiation on the lifetime radiation tolerance of Service Level I and ll coatings.
ASTM D 4537-96 (Ref. 8) provides guidance that is acceptable to the NRC staff on the qualification'and certification of personnel who inspect protective coatings in nuclear facilities.' This standard provides guidance on inspection of the education, training, experience, qualifications, and' certification of Level I,11, and lil coating inspectors.
5
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- 3. TRAINING AND QUAllFICATION OF PROTECTIVE COATINGS INSPECTORS AND COATING APPLICATORS
, i ASTM D 5498-94 (Ref. 9) provides guidance acceptable to the NRC staff for persons responsible for developing a training program for the indoctrination and training of personnel ,
for inspecting coating work in nuclea.r facilities and also recommends areas of proficiency that are embodied in the ASTM standards shown in Table 1 in ASTM D 5498-94.
ASTM D4227-95 (Ref.10) provides guidance acceptable to the NRC staff for the l
\
qualification of coatings applicators to verify that they are proficient and eble to attain the I
{
quality required for applying specified coatings to concrete surfaces, including those in a i 1
nuclear facility. )
ASTM D4228-95 (Ref.11) provides guidance acceptable to the NRC staff for the qualification of coatings applicators to verify that they are proficient and able to attain the
~
quality required for applying specified coatings to steel surfaces, including those in a nuclear facility.
ASTM D4286-96 (Ref.12) provides criteria and methods that are acceptable to the NRC staff to assist utility owners, architects, engineers, and contractors in determining the overall qualifications of a coatings contractor to execute coating work for the primary containment and other safety-related facilities of nuclear power plants. The criteria and requirements for contractors address the contractor's essential basic capability to execute nuclear coating work.
- 4. MAINTENANCE OF COATINGS ASTM D 5163-96 (Ref.13) provides guidelines that are acceptable to the NRC staff for establishing an in-service coatings monitoring program for Service Level ! coating systems in operating nuclear power plants and for Service Level 11 end other areas outside containment (as applicable).
ASTM D 4541-95 (Ref.14) provides guidance oceeptable to the NRC staff for a procedure for evaluating the pull-off stre.ngth of coatings using fixed-alignment adhesion testers.
6
i' ASTM D 3359 95, Revision A (Ref.15), provides guidance that is acceptable to the NRC staff on test methods for measuring adhesion using tape tests.
ASTM D 5962 96 (Ref.16) provides guidance that is acceptable to the NRC staff on maintaining unqualified coatings (paints) within Level I areas,of a nuclear power facility.
5, ASTM STANDARD TERMINOLOGY ASTM D4538-95 (Ref.17) defines standard terms related to protective coating and lining work for power generation facilities that are acceptable to the NRC staff and that are also applicable to protective coatings employed in nuclear power plants.
- 6. ADDITIONAL INFORMATION 1
, Additional information on the selection, application,' inspection, and maintenance of nuclear plant safety-related protective coatings is provided in EPRI Report TR-109937 (Ref.
18), which provides a detailed discussion of important considerations related to protective I
coatings and can be used to supplement the ASTM Standards guidelines as deemed 1 necessary.
D. IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.
This proposed revision has been released to encourage public participation in its development. Except in those cases in which an applicant proposes an acceptable alternative method for complying with the portions of the NRC's regulations specified in this guide, the methods and guidance to be described in the final guide will reflect public comments received and will be used in the evaluation of submittals in connection with applications for construction permits, operating licenses, and combined licenses. Current licensees may, at their option, comply with the guidance in this regulatory guide. Any applicable requirements for changing the licensing basis to reflect the change must be followed.
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ASTM D5144 97 ASTM D4538 95 Protective Coating 4 - > Protective Coatings Standards in NPPs Terminology L "
-~---- ~. - - . . . . . _ . _ _ _ __ __ , _ _ _ __
i
. ..Y _. -. _._Y _ _ y ASTM D3843 93 j ASTM D4537 96 Procedures to Qualify & ASTM D5163 96 QA Practices for NPP Establishing Procedures to Protective Coatings l Certify inspection
- Personnelin NPPs Monitor Performance of t
. A ASTM D5139 96 1 ,'
ASTM D5498 94
~
p Sample Preparation l Developing a Training for Coating Tests I *i Program for Coating Work ASTM D4541-95 Inspectors in NPPs > Coatings Adhesion Testing
. _ . ASTM D391195 - 733fD'i286' 9F
- - > Simulated DB A > Contractor Qualif.
Coatings Testing NPP Coatings ASTM D3359 95 ASTM D4082 95~ -- -
. > Rev. A , Tape Adhesion
> Irradiation of ASTM D4227-95 Coatings Tests Test Samples > Applicator Quahf. -
Concrete Surfaces .
ASTM D5962-96 ASTM D4228 95 - -
> Maintaining Level 1
> Applicator Qualif. - Unquahfied Coatings Steel Su rfa ce s ;
Figure 1, ASTM Standards Relevant to NPP Class I, ll and lil Protective Coatings 1
1 1
8 1
2 REFERENCES
- 1. . USNRC, " Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,"
Regulatory Guide 1.160, Revision 2, March 1997.
- 2. USNRC, " Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment," Generic Letter 98-04, July 14,1998. i
- 3. Arnerican Society for Testing and Materials, " Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities," ASTM D 3843-93.
- 4. American Society for Testing and Materials, " Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) Conditions," ASTM D 3911-95.
- 5. American Society for Testing and Materials, " Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants," ASTM D 5144-97.
- 6. American Society for Testing and Materials, " Standard Specification for Sample Preparation for Qualification Testing of Coatings To Be Used in Nuclear Power Plants,"
ASTM D 5139-90 (Reapproved 1996).
- 7. American Society for Testing and Materials, " Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Light-Water Nuclear Power Plants," ASTM D4082-95.
- 8. American Society for Testing and Materials, " Standard Guide for Establishing Procedures To Qualify and Certify inspection Personnel for Coating Work in Nuclear Facilities," ASTM D 4537-91 (Reapproved 1996).
- 9. American Society for Testing and Materials, " Standard Guide for Developing a Training Program for Coating Work Inspectors in Nuclear Facilities," ASTM D 5498-94.
- 10. American Society for Testing and Materials, " Standard Practice for Qualification of Coating Applicators for Application of Coatings to Concrete Surfaces," ASTM D4227-95.
- 11. American Society for Testing and Materials, " Standard Practice for Qualification of Coating Applicators for Application of Coatings to Steel Surfaces." ASTM D4228-95.
12i American Society for Testing and Materials, " Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities,"
ASTM D4286 90 (Reapproved 1996).
9
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- 13. American Society for Testing and Materials, " Standard Guide for Establishing Procedures To Monitor the Performance of Safety Related Coatings in an Operating Nuclear Power Plant," ASTM D5163-96.
i
- 14. American Society for Testing and Materials, " Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers," ASTM D 4541-95.
l'
- 15. American Society for Testing and Materials, " Standard Test Methods for Measuring Adhesion by Tape Test," ASTM D-3359-95, Revision A.
- 16. American Society for Testing and Materials, " Standard Guide for Maintaining Unqualified Coatings (Paints) Within Level i Areas of a Nuclear Power Facility," ASTM D 5962-96,
- 17. American Society for Testing and Materials, " Standard Terminology Relating to Protective Coating and Lining Work for Power Generation Facilities," ASTM D 4538-95.
- 18. Electric Power Research Institute, " Guidelines on the Elements of a Nuclear Safety-Related Coatings," EPRI Report TR-109937, March 1998.
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'. i REGULATORY ANALYSIS The guidance in Regulatory Guide 1.54, " Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants," has become outdated because the ANSI standards endorsed by the guide have been withdrawn and replaced by ASTM standards. Public Law 104-113, OMB Circular A-119, and NRC's Strategic Plan for FY1997-2002 encourage the use of industry developed consensus codes, standards, and guides that have been develeped by lndue;iy end thet can be endorsed by the NRC-aftd seri;ed out by ladustry. The most' cost-beneficial method to update the guidance in Regulatory Guide 1.54 would be to issue a revision of Regulatory Guide 1.54 that endorses updated ASTM standards. l f
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BACKFIT ANALYSIS The proposed regulatory guide does not require a backfit analysis as described in 10 CFR 50.109(c) because this regulatory guide will not require backfitting as described in 10 CFR 50.109(a)(1); rather, this regulatory guide will provide guidance that the licensee may choose to use.
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