ML20043D636

Closeout of NRC Bulletin 88-05:NONCONFORMING Materials Supplied by Piping Supplies,Inc.,At Folsom,New Jersey,And West Jersey Manufacturing Company at Williamstown,New Jersey

ML20043D636
Person / Time
Issue date:	05/31/1990
From:	Office of Nuclear Reactor Regulation
To:
References
IEB-88-005, IEB-88-5, NUREG-1402, NUDOCS 9006110010
Download: ML20043D636 (79)

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{{#Wiki_filter:, s NUREG-1402 i Closeout of NRC Bulletin 88-05: Nonconforming Materials Supplied by Piping Supplies, Inc., at;Folsom, New Jersey, and West Jersey Manufacturing Company I at Williamstown, New Jersey 1 h U.S. Nuclear Regulatory Commission l Office of Nuclear Reactor Regulation o t O 'I}N

f AVAILAB:LITY NOTICE Availability of Reference Materials Cited in NRC Publications ' Most documents cited in NRC publications will be available from one of the following sources: The NRC Public Document Room 2120 L Street, NW, Lower Level Washington, DC 1. 20555' The Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082, 2. Washington, DC 20013 7082 1 The National Technical Information Service, Springfield, VA 22161 3. Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investi-gation notices; Licensee Event Reports; vendor reports and correspondence Commission papers; and applicant and licensee documents and correspondence. The following documents in the NUREG series are availabla for purchase from the GPO Seles formal NRC staff and contractor reports, NRC sponsored conference proceed-Program: ings, and NRC booklets and brochures. Also available are Rogulatory Guides, NRC regub-tions in the Code of Federal Regulations, and Nuclear Regulatory Commission issuances. Documents available from the National Technical information Service include NUREG reports and technical reports prepared by other federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal and periodical articles, and transactions. Federal Register notices, federal and state legislation, and congressional reports can usually be obtained from these libraries, Documents such as theses, dissertations, foreign reports and translations, and non NRC conference proceedings are available for purchase from the organization sponsoring the publication cited. Single copies of NRC draft reports are available froe, to the extent of supply, upon written request to the Office of Information Resources Management Distribution Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Coples of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library,7920 Norfolk Avenue, Bethesda, Maryland, and are available there for reference use by the public. Codes and standards are usually copy-righted and may be purchased from the originating organization 'or, if they are American National Standards, from the American National Standards institute,1430 Broadway, New York, NY 10018.

NUREG-1402 Closeout of NRC Bulletin 88-05: Nonconforming Materials Supplied by Piping Supplies, Inc., at Folsom, New Jersey, and West Jersey. Manufacturing Company at Williamstown, New Jersey ate I u ished ay g I Omce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 'i t w

i ABSTRACT l. This report documents the activities that led to the closeout of U.S. Nuclear L Regulatory Commission (NRC) Bulletin 88-05, which was issued on May 6, 1988. The bulletin required that licensees submit information on materials supplied by Piping Supplies, Inc. (PSI) and West Jersey Manufacturing Company (WJM) and requested that they (1) ensure that these materials complied with the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code) and design specifications or were suitable for their intended service or (2) replace such materials. Supplements 1 and 2 were issued on June 15 and August 3, 1988, respectively. In Supplement 2, another affiliated supplier, Chews Landing Metal Manufacturers, Incorporated (CLM), was identified. The staff concluded that (1) the analytical procedures used to qualify the nonconforming parts and the analysis results provide an adequate basis for resolving the staff's concerns regarding fittings and flanges; (2) even though the materials supplied by PSI, WJM, and CLM with falsified certified material test reports do not meet the ASME Code, their use is an acceptable alternative in accordance with Section 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Reculations; (3) activities in response to Bulletin 88-05 regarding fittings anc flanges can be closed for all operating plants; and (4) licensees should evaluate the use of product forms other than fittings and flanges. 4 NUREG-1402 iii D

t CONTENTS P_a2_e AUSTRACT.........,.................................................... iii 1 INTRODUCTION..................................................... 1-1 2 DISCUSSION....................................................... 2-1 2.1 Issuance of NRC Bulletin 88-05 and Supplements 1 and 2...... 2-1 2.2 Receipt and Review of Licensee Responses.................... 2-2 2.3 NUMARC's Programs for Testing and Generic Analysis.......... 2-3 2.4 NRC Visit to Alvin W. Vogtle Nuclear Plant.................. 2-6 2.5 NRC Meeting With NUMARC, EPRI, and Bechte1.................. 2-7 2.- 3 NUMARC's Supplemental Generic Analysis Report............... 2-8 27 Staff Evaluation of Other Product Forms..................... 2-9 2.8 Staff Evaluation of Hardness Correlation.................... 2-10 f.9 Brookhaven National Laboratory's Independent Testin Ac t i v i t i e s.......................................... g 2-11 2.10 Responses From Near-Term Operating License Applicants....... 2-13 3 CONCLUSIONS...................................................... 3-1 4 REFERENCES....................................................... 4-1 APPENDIX A - NRC BULLETIN 88-05 AND SUPPLEMENTS 1 AND 2 APPENDIX B -

SUMMARY

OF SIGNIFICANT LICENSEE RESPONSES TO NRC BULLETIN 88-05. APPENDIX C - CHRON0 LOGY OF MEElINGS, TRIPS, CORRESPONDENCE, AND DOCUMENTS PERTAINING TO NRC BULLETIN 88-05 AND -ITS SUPPLEMENTS APPENDIX D - PRINCIPAL CONTRIBUTORS APPENDIX E - ABBREVIATIONS TABLE 2.1 Status of License Activities..................................... 2-3 NUREG-1402 y

1 INTRODUCTION In early 1988, the U.S. Nuclear Regulatory Commission (NRC) obtained copies of certified material test reports (CMTRs) for material supplied to the nuclear industry by Pipeline Supplies, Inc. (PSI), Folsom, New Jersey, and West Jersey Manufacturing Company (WJM), Williamstown, New Jersey, that contained false i information. A domestic forging company's letterhead was used for a number of CMTRs to certify that commercial grade, foreign steel met the requirements of Section III, Subar icle NCA-3800, of the American Society of Mechanical Engi-l neers, Boiler and F.' essure Vessel Code (ASME Code). No evidence existed that PSI or WJM had performed or had a subcontractor perform the testing required by Section III to upgrade the commercially produced steel designated on these l falsified CMTRs. The information available indicated that WJM had started sup-plying ASME Code components to the nuclear industry in 1976, both directly as well as through intermediaries, and that PSI had started supplying ASME Code components to the nuclear industry, directly and through intermediaries, in i 1985. In addition, WJM held an ASME Quality System certificate (QSC-385) as a material manufacturer from November 30, 1979, to November 30, 1985. The NRC concluded that potential generic safety implications existed at facil-ities that either had received direct shipments of pipe fittings and flanges furnished by PSI or WJM or had received piping subassemblies and other compo-nents from holders of ASME certificates of authorization or other subcontrac-tors that had incorporated materials supplied by PSI or WJM. In response to these developments, the NRC initiated an in-depth program to evaluate the potential generic safety implications resulting from the use of material supplied by PSI or WJM in safety-related systems of the licensees' plants by issuing NRC Bulletin 88-05 and Supplements 1 and 2 between May and August of 1988. Thisreportpresentsthestaff'ssafetyevaluationoflicenseeprogramsto locate, test, and analyze these materials and to resolve the staff s concerns A regarding the qualification for service of nonconforming material described in NRC Bulletin 88-05. Appendix A contains copies of NRC Bulletin 88-05 and its supplements. Appendix B contains the summary of significant licensee responses to NRC Bulletin 88-05 that was prepared by the NRC staf f and its consultant, Brookhaven National Laboratory. Appendix C is a chronology of meetings, trips, correspondence, and documents pertaining to the bulletin and its supplements. Appendix D lists the principal contributors to this report. Appendix E lists the abbreviations used in the report. NUREG-1402 1-1

2 DISCUSSION 2.1 Issuance of NRC Bulletin 88-05 and Supplements 1 and 2 The NRC issued NRC Bulletin 88-05 on May 6,1988, to all holders of operating licenses and construction permits for nuclear power reactors requiring that li-censees submit information on materials supplied by PSI and WJM and requesting that they (1) take actions to ensure that these materials complied with the ASME Code and design specifications or were suitable for their intended service or (2) replace such materials. The NRC staff issued Supplement 1 to NRC Bulletin 88-05 on June 15, 1988, after Carolina Power & Light (CP&L) informed the staff on June 10, 1988, that two flanges from the warehouse that had been supplied by WJM had been tested at the Shearon Harris Nuclear Power Plant. The CP&L test results did not match those reported on WJM's certified material test reports (CMTRs) and did not meet the tensile and yield strength requirements delineated in the SA-105 specification of the ASME Code for SA-105 material. The required minimum tensile strength is 70 kips per square inch (ksi); the measured tensile strengths, however, were 45 ksi and 46 ksi. The tensile strength reported on the CMTR was 77 ksi. The required minimum yield strength is 36 ksi; the measured yield strengths, however, were 27 ksi and 31 ksi. The yield strength reported on the CMTR was 50 ksi. Measured chemistry composition also did not comply with the specification; nota-bly, perc'ent carbon was very low - 0.045, and percent manganese was 0.32 (the required range is 0.6 to 1.05). Supplement 1 narrowed the scope of review from ASME and American Society for Testing and Materials (ASTM) " materials" to ASME and ASTM fittings and flanges. Because it had been verified that flanges that did-not comply with ASME and ASTM specifications had been supplied to the nuclear industry, the time frames for certain actions were also modified by this supplement. Licensees were requested to retain nonconforming materials until advised further by the NRC. Nonconform-ing materials were to be segregated to ensure that they were not inadvertently used. Licensees also were encouraged to report the results of tests of flanges and fittings supplied by PSI and WJM to the Institute of Nuclear Power Operations Nuclear Network for dissemination to the industry. The NRC staff issued Supplement 2 to NRC Bulletin 88-05 on August 3,1988, after it met with representatives of the Nuclear Management and Resources Coun-cil (NUMARC) on July 22, 1988, to discuss the status of licensees' actions in response to Bulletin 88-05 and Supplement 1. During this meeting, NUMARC pre-sented information on licensee and NUMARC and Electric Power Research Insti-tute testing and evaluation methodology for PSI and WJM flanges. NUMARC summa-rized this information in a letter to the NRC dated July 25, 1988, and submitted a detailed report and proposal on July 29, 1988. On the basis of the reported measurement and analytical results. the NRC staff concluded that it was appropriate for full power licensees to. pend, temporar-ily, the field measurements, testing, records review, and preparation of justi-fications for continued operations (JCOs) that were requested by Bulletin 88-05 NUREG-1402 2-1 1

and' Supplement I until further notice. Addressees that had not received a full-power license were requested to continue the in situ testing and the records review. The time frames remained as specified in the original bulletin, that is, January 1,1976, to the present. During the temporary suspension of the requested activities, the NRC staff reviewed the measurement and test data and the results of analyses and determined the extent to which further actions were appropriate to ensure the continued safe operation of nuclear power plants. On July 22, 1988, the NRC staff completed its review of PSI, WJM, and Chews Landing Metal Manufacturers Incorporated (CLM)* purchase order and invoice records. On the basis of this review, the staff determined that PSI, WJM, and CLM had provided product forms in addition to flanges and fittings. The staff identified the additional product forms and compiled a list of nuclear power plants that were possible recipients of PSI, WJM, and CLM material % Copies of NRC Bulletin 88-05 and Supplements 1 and 2 are contained in Appen-dix A. 2.2 Receipt and Review of Licensee Responses Licensees of 110 units located at 73 plant sites submitted responses in accord-ance with the reporting requirements of NRC Bulletin 88-05. The NRC staff and consultants f rom Brookhaven National Laboratory (BNL) reviewed the responses and summarized the significant results in tabular form as shown in Appendix B. In the summary table the licensee responses are categorized into three primary areas of interest: (1) Records Search and Identification (a) Total number of fittings and flanges received from WJM, PSI, and CLM (b) Number installed in safety or non-safety-related systems (c) Number in the warehouse (d) Number unaccounted for (2) Test Results (a) Number of fittings and flanges tested Humber with Brinell hardness number (BHN) less than 137 Number with BHN greater than 187 (b) Number tested for chemical properties and the number found to be acceptable (c) Number tested for physical properties and the number found to be acceptable

• In Supplement-2 of NRC Bulletin 88-05, CLM was identified as being affiliated with PSI and WJM.

NUREG-1402 2-2

(3) Engineering Evaluations (a) Number of JCOs for accessible and inaccessible fittings and flanges L l. (b) Engineering evaluation method used The results of the detailed review of licensee responses indicated that approxi-mately 8000 flanges and fittings had been procured from WJM, PSI, and CLM and L installed in safety-related systems of those plants reporting numerical data. Several of the licensees did not report numerical results because Supplement 2 had suspended search activities. The status of licensee activities reported in each of the three primary areas of interest is shown in Table 2.1. A detailed 1 breakdown for each respon'.e is contained in Appendix B. Table 2.1 Status of licensee activities Records search l and Engineering Status identification Testing evaluations Number of plant sites for which .35 reporting is complete 53 40 Number of plant sites for which reporting is incomplete 20 33 38 The review of the responses indicated that, in general, most licensees were I responsive to the requirements of NRC Bulletin 88-05. The NRC staff and its consultants concluded that most licensees were concerned about nonconforming material at their plants and were engaged in activities requested by the bul-letin and Supplement 1 before Supplement 2 was issued. 2.3 NUMARC's Programs for Testing and Generic Analysis At a meeting held at NRC headquarters at One White Flint North, Rockville, Maryland, on July 22, 1988, NUMARC presented its program to address NRC Bulle-tin 88-05 relative to the NRC requirements for field testing and justifications for continued operation (JCOs). In response to the staff's concern about the proper use of Equotip hardness readings taken on material at elevated temperature, EPRI reported that it had developed a correlation to correct the Equotip results to the equivalent values at normal room (70'F) temperature. This correlation was developed through test-ing performed by EPRI and was promulgated to the industry by NUMARC on July 12, 1988. After reviewing the methodology of the correlation, the NRC staff and its consultants were satisfied that the concern with respect to the proper use of elevated-temperature Equotip readings had been resolved. NUMARC also reported that Bechtel had developed, through the NUMARC program to address llRC Bulletin 88-05, a generic quantitative analysis methodology support-ing permanent installation of ferritic components that cannot be shown to meet the current NRC requirement of a Brinell hardness number (BHN) of 137 for SA-105 material. The Bechtel report provided allowable values on a case-t'y-case basis for different types of flanges and fittings, schedules, and sizes. NUREG-1402 2-3 .A------.

NUMARC and EPRI stated that the purpose of the generic analysis and evaluation report (the Bechtel report) was to provide a basis for justification of suita-bility for indefinite service without replacement of potentially substrength material supplied by WMJ or PSI as identified in NRC Bulletin 88-05 and its sup-plements. Licensees had conducted field tests to identify substrength components among these suspect items. When properties could not be confirmed, determina-tion of suitability for indefinite service was based on conservatively assuming lower than specified strength values for suspect material and demonstrating that code design rules were satisfied with the assumed values. If generic accepta-bility of certain items could not be established by the tables of the generic report or other elements of the NUMARC programs, the report provided guidance on plant-specific evaluations. The methodology used in the generic report was based on the following assumptions: Conservative strength values of suspect material that are lower than specified code minimum values were assumed for the purpose of the generic analysis. Compliance with code design rules was generically established using con-servative bounding assumptions. When identification of a material could not be confirmed by field tests, the analysis assumed lower strength material properties. In the meeting held on July 22, 1988, NUMARC also presented an analysis of util-ity and laboratory test data obtained to date and, in a letter to Dr. Thomas Murley of the NRC dated July 25, 1988, requested that licensee activities rela-tive to NRC Bulletin 88-05 and Supplement 1 be suspended. In the letter, NUMARC committed to provide a written report to the NRC staff reflecting the test data and conclusions presented at the July 22 meeting and to provide quantitative statistical evaluations relative to the conclusions presented at the meeting. On July 29, 1988, NUMARC provided the report to the NRC staff; it was included as Attachment-1 to NRC Bulletin 88-05, Supplement 2. NUMARC's generic testing program in response to NRC Bulletin 88-05 included comprehensive laboratory testing of suspect items contributed by utilities and utility generated data of destructive laboratory tests and in situ tests of installed suspect items. NUMARC laboratory test methods followed ASTM standards for tensile testing to produce values for ultimate tensile strength, yield stress, percent elongation, and percent reduction of area. Tensile strength correlations were developed on the basis of Equotip testing. For the chemical analysis, spectrographic analy-sis and portable X-ray fluorescence analysis methods were used. All laboratory testing equipment was calibrated to appropriate standards. Utilities principally used the Equotip device to conduct hardness testing of installed or warehouse items. Other hardness test devices also were used in a few instances. For austenitic stainless steel items, the principal test method was a simple magnetic check. Some alloy analysis and replication metallography also were performed. NUREG-1402 2-4 1

At the time of the July 22, 1988, meeting, NUMARC had developed generic labora-tory test data for 123 items. The utilities provided data on 1334 items that had undergone field hardness testing and 108 tensile strength results. NUMARC also provided the NRC staff with computer discs and printouts of the results. The NRC staff and its consultants reviewed the Bechtel generic analysis and evaluation report submitted by NUMARC at the meeting. Results of the. review indicated the following: (1) The generic analysis methodology is acceptable to the NRC staff for pres-sure and moment qualification of American National n ?ndards Institute (ANSI) B16.11 fittings. (2) The generic analysis methodology is acceptable to the NRC staff for pres-sure qualification of ANSI B16.5 flanged joints. (3) The generic analysis methodology is not acceptable to the NRC staff for moment qualification of ANSI B16.5 flanges, other than blind flanges. The staff's concerns with respect to the applicability of the generic analysis methodology to moment qualification of ANSI B16.5 flanges were subsequently resolved by NUMARC in its supplemental report discussed in Section 2.6. NUMARC presented its final report to the NRC staff at a meeting held at NRC headquarters at One White Flint North on October 27, 1988. The report summar-ized the results of field testing, laboratory testing, and stress analyses per-formed in response to NRC Bulletin 88-05. The report summarized the results of approximately 7100 field tests as well as performance or analysis of more than 1300 laboratory tests of samples of the suspect components and showed that for a large percentage of the components tested, test results indicated that they were the correct materials as speci-fled in the ASME Code or ASTM standards. The report identified 25 carbon steel blind flanges (out of 404 tested) that did not meet material specifications for tensile strength. These blind flanges exhibited tensile strengths (in some cases inferred from hardness testing) of about 45 ksi rather than the ASME Code requirement of 70 ksi for SA-105 carbon steel. Metallurgical analysis indicated that these flanges were made of low carbon steel plate rather than the required SA-105 forgings. For blind flanges, the stresses of concern are limited to pressure and boltup loads. The generic analysis and evaluation report prepared by Bechtel under the NUMARC program and previously submitted to the NRC staff stated that, for blind flanges, tensile strengths of about 45 ksi are sufficient to accommodate stress allowable values with margin. The staff and its consultants reviewed the generic analysis and evaluation report and found that NUMARC had resolved the concern with respect to acceptability for service of the low-material-strength blind flanges. The staff and its consultants concluded that sufficient testing had been per-formed by NUMARC and the licensees to develop confidence that the scope and nature of the problem had been identified and addressed. NUREG-1402 2-5

2.4 NRC Visit to Alvin W. Vogtle Nuclear Plant The NRC staff and its consultants from BNL visited Georgia Power Company's Vogtle plant located in Waynesboro, Georgia, on August 22-23, 1988. More non-conforming material had been found at the Vogtle plant than at any other plant site. The purpose of the visit was to observe field procedures relative to that licensee's capability to respond to NRC Bulletin 88-05 and to discuss other pertinent problems and concerns. The NRC staff and its consultants discussed the licensee's plan for Vogtle in response to NRC Bulletin 88-05 and requested details about the status and pro-cedures of its records search and identification, testing, and engineering eval-uations programs. In response, Vogtle personnel demonstrated the Equotip hard-ness measuring equipment and conversion-to-tensile-strength procedure. The staff and its consultants visited the diesel generator building where field per-sonnel demonstrated the procedure and took hardness readings on several flanges. They went to the containment of Unit 2 where they inspected fittings supplied by PSI and WJM that had been installed in a Class 1 piping system. The NRC consultants reviewed several JCOs and stress calculation packages. For fittings, such as half couplings, the procedure used at Vogtle is to determine the ultimate tensile strength (UTS) from Equotip measurements. The adjusted allowable value, which was assur..ed to be one-fourth of the UTS, was compared to the allowable value used in the analysis of the pipe (SA-106, Grade B) at oper-ating temperature. If the adjusted allowable value was found to be greater than that used in the analysis, the fitting was ruled to be acceptable; if the adjusted allowable value was found to be less than that used in the analysis, the calculated stresses in the pipe at the fitting from ASME Code, Section III equations were compared to the lower adjusted allowable value. The licensee reviewed flanges for acceptability in regard to both pressure and moment capacity. The NRC e aff found that the procedure for assessing flange pressure capacity was simiiar to that described above for fittings. The proce-dure used for assessing flange moment capacity was the same as that proposed by NUMARC where the flange moment capacity is calculated using the equations in Subarticle NC-3658.3 of Section III of the ASME Code and compared to actual values. The NRC staff and its consultants found that the engineering evaluations reviewed appeared to be consistent with NUMARC's methodology and that documentation and traceability were good. Where values of stresses in the pipe were calculated by computer, the values shown in the evaluation sheets were obtained from the com-puter output and were relatively low even when compared with the adjusted (re-duced) allowable values. As a result of their visit to Vogtle, the staff and its consultants obtained a more detailed understanding of the scope, procedures, and methodology used at Vogtle in response to NRC Bulletin 88-05. They observed personnel locating, identifying, and testing nonconforming material and were shown the analytical procedures and JCOs used at Vogtle to evaluate nonconforming couponents and to demonstrate adequacy for service in safety related systems. The information collected by the staff and its consultants at Vogtle provided additional data points for evaluating and verifying NUMARC's testing and generic NUREG-1402 2-6

analysis progroms. The staff and its consultants found that the test and engi-neering evaluation resuits at Vogtle were consistent with and confirmed the findings reported by NUMARC. 1 l 2.5 NRC P.eeting With NUMARC, EPRI, and Bechtel NUMARC presented Bechtel's generic analysis and evaluation report and methodology to the staff at meetings held on July 22 and October 27, 1968. After reviewing the report, the NRC staff and its consultants generated la questions in regard to the report. To resolve these technical issues, the staff and its consultants conducted an audit at the Bechtel office in San Francisco en November 16 and 17, 1988, to review in detail Bechtel's e ncric analysis and naluation report and the results of tests sponsored by Bechtal and EPRt. On November 16, 1988, the staff met with representatives of Bechtel, NUMARC, and EPRI. At that meeting Bechtel provided respnnses to the 14 staff questions. The staff was shown typical calculations that demonstrated the methodology and assump-tions used by Bechtel in generating the tabular values. In addition, the staff was shown typical flange evaluations from three near-term operating license plants: Limerick Generating Station Unit 2; South Texas Project, Unit 2; and Vogtle, Unit 2. The staff questioned Bechtel about its assumption that the yield strength of the tested material is one-half of the ultimate tensile strength. Bechtel deter-inined the yield-to-ultimate strength ratio from the results of tests on the non-conforming material. The results showed that of 489 tests, the ratio was great-er than 0.5 for 446 specimens and slightly less than 0.5 for 43 specimens. For those specimens with ratios less than 0.5, the lowest ratio was 0.43 and the average was approximately 0.47. The responses provided by Bechtel to the staff's questions increased the staff's concerns with regard to the adequacy of the ee umptions and conservativeness of the methodology in the generic analysis and evaluation report to provide assur-ance that the nonconforming material is suibble for service. In partictlar, the staff and its consultants raised additional questions with regard to (1) several non-bounding assumptions that appeared to be nonr.oilservative, (2) the exclusion of abnormal loading evaluations, and (3) the basis for the evaluation (e.g., rules given in the ASME Code that were adjusted for below-minimum material properties). The staff and its consultants determined that the responses and information provided by Bechtel at the meeting were insufficient to demonstrate the adequacy of the generic analysis and evaluation report to evaluate the fitness for service of nonconformir.g components and that additional information was necessary in order to complete the evaluation. The staff decided to concentrate most of the remaining review effort on t.be generic stress analysis of the nonconforming components in order to determine their fitness for the applicable service conditions, In letters to NUMARC dated December 9, 1988, and February 15, 1989, the NRC staff described the remaining major areas of concern in addition to several lessor issues, which the staff requested that NUMARC resolve in a revised report or supplement. The staff's major areas of concern were (1) acceptability of NUREG-1402 2-7 4

nonconforming components for known actual plant service loadings, (2) conurva-tiveness of the basic assumptions used to develop the methodology, and (3) ade-quacy of the generic analysis for abnormal loadings such as maximum internal fluid pressure and operating basis and safe shutdown earthquakes. With regard to assessing the acceptability of substrength components for known actual service loadings at operating plants, the staff requested that NUMARC evaluate a repre-sentative cross-section of nonconforming components from at least three plants: one high seismicity plant, one plant of older design (circa 1960's), and one plant with many suspect components, and that all three plants be designed by different architect / engineer firms. The letter to NUMARC dated February 15, 1989, also contained the NRC staff position regarding the use of nonconforming warehouse material. The NRC staff stated that before installation in safety-related applications, warehouse material must be screened by hardness testing and must be qualified by tensile and chemical tests of material from the same heat. 2.6 NUMARC's Supplemental Generic Analysis Report As discussed previously, on the basis of its review of the generic analysis and evaluation report and associated analytical procedures, its meeting with NUMARC, EPRI, and Bechtel, and its review of licensee responses from operating and near-term operating license plants, the staff determined that the information that had been provided by NUMARC was insufficient to demonstrate the adequacy of the nonconforming components. The letters to NUMARC from the staff dated December 9, 1988, and February 15, 1989, contained specific comments and requests for addi-tional information. NUMARC responded to these requests on August 30 and Novem-ber 28, 1989, with a supplemental generic analysis report. In response to the staff's request that a representative cross-section of non-conforming components from three plants be evaluated using the generic analy-sis methodology in order to assess the acceptability of suspected components. NUMARC analyzed 153 flanges selected from one high seismicity plant, one plant of older design (circa 1960's), and one plant with many suspect components. Diablo Canyon '4uclear Power Plant, Units 1 and 2, Zion Nuclear Power Station, Units 1 and 2, and Limerick Generating Station, Unit 2, were chosen as being representative of these cases, respectively, while satisfying the requirement that all three plants be designed by different architect / engineer firms. For the purpose of this analysis, each evaluated flange was conservatively assumed to possess the lowest bound of tensile strength determined from the NUMARC laboratory tests (61.6 ksi for non-blind flanges). Of the 153 flanges, 134 were qualified directly by application of the generic analysis methodology and 19 were qualified by specific analysis using ASME Code design rules (as specified by the generic analysis methodology). No concerns regarding stress were revealed by this analysis. Moreover, the 134 flanges that were evaluated by direct application of the generic analysis methodology were also re-evaluated using ASME Code design rules to provide additional verification of the applica-bility of the generic analysis methodology. Again, no concerns regarding stress were revealed. Additional conservatism is reflected in the fact that the 95/95 statistical confidence level could have been maintained with up to three devia-tions in the selected population, but zero deviations were observed. In addition, in the letters dated December 9, 1988, and February 15, 1989, the NRC staff requested that NUMARC evaluate certain assumptions used to calculate moment loads in its generic stress analysis methodology and show that they were NUREG-1402 2-8

\\ bounding with a 95 percent confidence level. These assumptions were evaluated in NUMARC's supplemental report and, after review, the staff found them to be conservative with the rW uired level of confidence. In the letters dated December 9, 1988, and February 15, 1989, the NRC staff also requested that NUMARC evaluate abnormal loadings and demonstrate that they met appropriate ASME Code service stress limits. The staff found that the generic analysis methodology was conservative in this regard with the specified 95/95 confidence level. In a letter to NOMARC dated November 2, 1989, the NRC staff submitted the results of its detailed review of the supplemental generic analysis report, which was provided in response to the NRC staff concerns outlined in the letters dated December 9, 1988, and February 15, 1989. The staff and its consultants deter-mined that the report was generally responsive to the staff concerns. The staff, however, requested that HUMARC do the following: j 1 (1) Show that 3 unacceptable flanges out of a population of 153 flanges provide a 95/95 statistical confidence level as stated throughout the supplemental generic analysis report. (2) Provide the correct design pressure for flanges 33-36 in Table 3-2 (Zion). These flanges were identified as 150 pound-class flanges used for a design pressure of 600 pounds per square inch gauge (psig). NUMARC responded to the NRC letter of November 2, 1989, on November 28, 1989. It responded to Item I with an enclosure that orovided the calculational methodology ~ used to' arrive at the stated conclusion. Using this methodology, NUMARC deter-mined that the chosen sample size was acceptable for a population of more than 10,000 items, with an acceptance criterion of up to three deviations. In re-sponse to Item 2, NUMARC reported that the 600 psig provided as the design pres-sure in the report is the highest design pressure for the system in which these flanges are located. The design pressure for these specific flanges is 192 psig. The staff found NUMARC's responses satisfactory and determirsd that all questions with respect to the supplemental generic analysis report and associated analyti-r cal procedures had been resolved. The staff is satisfied that application of the generic analysis to nonconforming fittings and flanges provides a 95 percent confidence that 95 percent of the components are structurally adequate for their intended service. 2.7 Staff Evaluation of Other Product Forms In addition to fittings and flanges, Supplement 2 of the bulletin listed other product forms that were supplied by PSI, WJM, and CLM. Included were items, such as lugs, that could have been welded or otherwise attached as a support to a plant safety-related piping system. This is of potential concern to the l staff because any substrength material in the piping supports could degrade the overall piping system. The supplemental generic analysis report discussed in Section 2.6 considered only fittings and flanges and did not include these other product forms. How-ever, the staff believes that additional generic stress analysis is not warranted for the following reasons: NUREG-1402 2-9 -x.

i (1) The design rules for piping supports provide for lesser allowable stresses with respect to the specified material yleid stress than do the design rules for piping. Since the design rules for piping were used for the evaluation of fittings and flanges, the determination of the reliability of the suspect fittings and flanges should ensure an equal or better reliability of the other suspect product forms. (2) These other product forms are not part of the pressure boundary. If a few piping support components yield or fail, there would most likely be suffi-cient margin in the other supports and piping to ensure the pressure bound- 'ry integrity of tho system. This is not true for the piping components, .ich as fittings and flanges, that actually form the pressure boundary. I use of these other product forms in safety-related piping systems appears e be much less widespread than the use of fittings and flanges. The list pro-vided in Supplement 2 indicates that unique or special orders of some of these materials were shipped to two plant sites, Perry Nuclear Power Plant and Palo Verde Nuclear Station. Other plants may have received relatively small quanti-ties of these materials. With the exception of Perry and Palo Verde, licensees who determine that these materials were received at their plant sites should determine the location of these materials and confirm their acceptability for service where they were used in safety-related applications. These evaluations do not have to be submitted to the NRC for review and should be performed in accordance with Section 50.59 of Title 10 of the Code of Federal Regulations (10 CFR). Perry and Palo Verde both received large ouantities of shear lugs and other product forms supplied by WJM, PSI, or CLM. The staff will require that the licensees for these two plants perform an evaluation of the application of these other product forms and submit the evaluation for staff review. 2.B Staff Evaluation of Hardness Correlation The staff evaluated the relationship between measured hardness and tensile strength for material supplied in accordance with the SA-105 specification of the ASME Code, which represented the largest portion of the carbon steel mate-rial supplied by PSI, WJM, and CLM. Other carbon steel materials supplied in accordance with the SA-181, SA-234, or SA-350 specifications are similar to SA-105 material with regard to the hardness-to-tensile-strength relationship. The SA-105 specification requires that the material conform to the chemical requirements and that an analysis of each heat of steel be performed. The pur-chaser is allowed to make a product analysis of supplied forgings, in which case i the chemistry requirements must be met. The specification requires that speci-mens for mechanical property testing be obtained from production forgings hfter heat treatment; separately forged test blanks are allowed. One tension Wst must be made for each heat and for each heat-treating furnace charge. In the case of forgings too small to permit obtaining a sub-size specimen, hardness testing is permitted, in which case the hardness should be in the range of Brinell hardness number (BHN) 137 to 187 inclusive. Since it was not possible to obtain tensile test specinens from installed items without destroying the components, the approach used by NUMARC was to perform in situ hardness tests as a screening test for potentially substandard materials. The basis for the validity of this approach was provided by the industry-wide NUMARC program, under which approximately 7100 field hardness test results, NUREG-1402 2-10 s

540 tensile strength results, and 770 chemical analyses were considered. The staf f accepted this approach but required a more conservative correlation of hardness to tensile strength than that sugge..ad by NUHARC, as discussed below. The staff's objective was to develop a critstion for identifying all potentially substandard carbon steel flange and fitting material and for determining its acceptability for service in safety-related systems. The staff evaluated the NUMARC and industry data together with confirmatory tests conducted by the staf f's contractor, Brookhaven National Laboratory, of samples selected by the staff from the NUHARC test material. Rather than adopting the best-fit NUHARC Equotip-to-tensile-strength correlation, which overpredicts the tensile strength in many cases, the staff adopted the more conservative correlation specified by ASME Code, SA-370, " Specification for Mechanical Testing of Steel Products." This correlation has been shown to be conservative for the NUHARC-sponsored Bechtel laboratory tests and the independent tests discussed in Section 2.9. 2.9 Brookhaven National Laboratory's Independent Testing Activities On September 12, 1988, the NRC placed a contract with Brookhaven National Laboratory (BNL) to provide assistance to the NRC staff in reviewing both field and laboratory test data and to independently test 13 flanges supplied by PSI and WJM. The 13 flanges were received at BNL on August 22, 1988 (from Bechtel Power Corporation) for independent testing. The following testing protocol was followed for each of the flanges: Hardness testing (both Brinell and Equotip) Tensile testing (one specimen per flange) Chemistry testing for the following elements: carbon, manganese, phos-i e phorus, sulfur, silica, chromium, nickel, molybdenum, vanadium, and copper Of the 13 flanges tested,12 appeared to be carbon steel; 1 flange (identified as PP-6) was stainless steel. The testing of the 13 flanges yielded the following results: Flange identification no. Comments V0GT 1-4 Meets SA-105 specification requirements. SEA 1-54 Meets SA-105 specification requirements. RB 1-17 Meets SA-105 specification requirements. CAL-1 Meets SA-105 specification requirements. OC 1-3 Meets SA-105 specification requirements. NUREG-1402 2-11 A

F1ance identification no. Comments WF 3-4 Meets SA-105 specification requirements. PP-7 Meets SA-105 specification requirements. LIM 2-32 Meets SA-105 specification requirements. RGE 1-1 Meets SA-105 specification requirements. RB 1-14 Meets SA-105 chemistry requirements; does not meet required minimum reduction of area. PER 1-33 Meets SA-105 chemistry requirements; one hardness value is too high; elongation does not meet the specification minimum. SEA 1-31 Meets SA-105 chemistry requirements; both elonga-tion and reduction of area do not meet the specifi-cation minimum. PP-6 (stainless steel) Meets mechanical requirements for SA-182 Type F304 material; neither chromium nor nickel meets the specification minimum. With regard to the three carbon steel flanges that did not meet the mechanical requirements, both the reduction of area and elongation for SEA 1-31 were below the specification minimum. The reduction of area was 20 percent (22 percent required), and t.he elongation was 29 percent (30 percent required). With regard to PER 1-33, one hardness value (of three taken) exceeded the 187 Brinell maxi-mum (192 BHN), and the elongation was measured at 16 percent, instead of the 22 percent required by specification. With regard to RB 1-14, the reduction of area was 28 percent, instead of the 30 percent minimum required by specification. Although these three flanges did deviate from the specification requirements to a minor degree, it is probable that the variances are small enough so that the flanges would perform their intended function during service. - Both the nickel and chromium content of the stainless steel flange (PP-6) measured at levels below the specification minimum. The mechanical properties significantly exceeded the specification minimum. It is probable that this flange would also perform its intended function during service. The review of the NUMARC and Vogtle Unit 2 data coupled with the independent testing of the WJM and PSI flanges has led the staff and BNL to conclude the following: (1) The 13. flanges tested (12 carbon steel,1 stainless steel) had test results that were indicative of the specified materials, although some deviations were noted. All specimens exceeded the minimum tensile requirements of the appropriate specifications. (2) -The Equotip hardness test method can be a valuable tool in estimating the tensile strength of materials if the limitations (temperature dependence, NUREG-1402 2-12 r

i i relative relationship to Brinnell hardness, etc.) are understood and compensated for. l (3) The independent tests confirmed the test results of NUMARC and those for Vogtle Unit 2. 2.10 Responses From Near-Term Operating License Applicants t Five near-term operating license (NTOL) applicants responded to NRC Bulletin E8-05 and its supplements by submitting the following to the NRC: Georgia Power Company, Alvin W. Vogtle Nuclear Plant, Unit 2, Docket No. 50-425, letters to the NRC dated November 30 and December 15, 1988, and January 5,1989 Houston Lighting & Power Company, South Texas Project, Unit 2, Docket i No. 50-499, letters to the NRC dated November 1, November 17, and December 6, 1988 Long Island Lighting Company, Shoreham Nuclear Power Station, Docket No. 50-322, letters to the NRC dated September 9 end December 21, 1988 Philadelphia Electric Company, Limerick Generating Station, Unit 2, Docket No. 50-353, letters to the NRC dated March 31 and June 2, 1989 Public Service Company of New Hampshire, Seabrook Station, Unit 1 Docket No. 50-443, letters to the NRC dated August 25 and October 14, 1988 The staff and its consultants reviewed e6ch submittal in detail. The responses contained descriptions of the following: the methodology used to identify, test, and evaluate material supplied by WJM, PSI, and CLN; the document and procurement review and testing programs; and an engineering evaluation and analysis of the nonconforming items. In all cases, the NRC staff sent requests for additional information and clarification to the NTOL applicants. After it had reviewed the responses, the staff prepared safety evaluation reports (SERs), each of which contained an overview summary of the actions taken by the applicant and the eval-untion of the applicant's response. In the SER the staff also discussed its review of the applicant's submittal, with particular emphasis on the analytical methods used to demonstrate suitability for service of the nonconforming flanges and fittings, and its conclusions. On the basis of its review of the submittals, the staff found that the NTOL applicants had conducted adequate material property tests and structural analyses of the nonconforming flanges and fittings using acceptable and conservative analytical methods and evaluation criteria. The staff also found that the applicants were responsive to the action and reporting requirements of NRC Bulletin 88-05, Supplements 1 and 2, and had qualified all nonconforming parts as being suitable for the intended service. The reports submitted by the NTOL applicants provided the staff and its consul-tants with additional data and confirmatory analyses demonstrating that the NUMARC generic analysis methodology was acceptable for determining the adequacy of nonconforming components for service. After reviewing the reports, the staff found that the nonconforming components in these five NTOL plants are fit for service even though the staff does not NUREG-1402 2-13 n.

consider the nonconforming parts to be material that confo ms to the ASME Code. However, the staff finds that the NT0L applicants have satisfied the criteria for meeting the requirements in NRC Bulletin 88-05 and, therefore, the use of this material is an acceptable alternative in accordance with 10 CFR 50.55a(a)(3)(ii) because full compliance with all specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality or safety. NUREG-1402 2-14 a

i 3 CONCLUSIONS The NRC staff and its consultants conducted an in-depth review program to re-solve the potential generic safety concerns at facilities that had received (1) direct shipments of materials furnished by PSI, WJM, or CLM or (2) piping subassemblies and other components from holders of ASME certificates of authori-zation or other subcontractors that had incorporated materials supplied by PSI, WJM, or CLM. Activities included receipt and review of licensee responses to NRC Bulletin 88-05; multiple meetings with NUMARC, EPRI, and Bechtel; a visit to the Vogtle plant; review of the NUMARC testing program, generic analysis and evaluation report, and methodology; independent testing and analysis; and pub-lication of SERs pertaining to the responses to NRC Bulletin 88-05 from five near-term operating license (NTOL) applicants. On the basis of the activities listed above and its findings, the staff concludes the following: (1) The analytical procedures used to qualify the nonconforming material and the results of the analyses provide an adequate basis for resolving the staff's concerns with respect to demonstrating the adequacy of the material for service. (2) The materials supplied with falsified certified material test reports do not meet ASME Code requirements. (3) Warehouse stock shall be screened, hardness tested, and qualified by ten-sile and chemical tests as stated in the staff's letter to NUMARC dated February 15, 1989. (4) Activities in response to NRC Bulletin 88-05 can be closed for fittings and flanges for all operating plants. (5) Activities in response to NRC Bulletin 88-05 can be closed for product forms other than fittings and flanges for operating plants that did not receive such material. For operating plants that did receive such material, licen-sees should determine its location and perform an engineering evaluation where it was used in safety-related applications. Licensees for Perry and Palo Verde will be required to submit their evaluations for NRC staff review. For other operating plants, these evaluations are to be performed in accord-ance with 10 CFR 50.59 and are not required to be reviewed by the NRC for approval Nowever, these evaluations are subject to audit and inspection l at the discretion of the NRC staff. l (6) Activities in response to NRC Bulletin 88-05 will remain open for unreviewed NTOL plants. A plant-specific evaluation must be performed for each NTOL plant before it is licensed. (7) The use of installed PSI, WJM, or CLM fittings and flanges is an acceptable alternative in accordance with 10 CFR 50.55a(a)(3)(ii) because full compli-ance with all specified requirements would result in hardship or unusual dif-ficulties without a compensating increase in the level of quality or safety. NUREG-1402 3-1 2

l l 4 REFERENCES American National Standards Institute, B16.5, " Steel Pipe Flanges and Flanged Fittings," 1981. 1 --, B16.11. " Forged Steel Fittings, Socket-Welding and Threaded," 1973. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, SA-105, " Specification for Forgings, Carbon Steel, for Piping Components," 1985. --, SA-181, " Specification for Forgings, Carbon Steel, for General-Purpose Piping," 1985. --, SA-234, " Specification for Piping Fittings of Wrought Carbon Steel and Alloy Steel for Moderate and Elevated Temperatures," 1985. --, SA-350, " Specification for Forgings, Carbon and Low Alloy Steel, Requiring Notch Toughness Testing for Piping Components," 1985. --, SA-370, " Specification for Mechanical Testing of Steel Products," 1977. --, Section III, Subarticle NC-3658.3, 1986 Edition. 3 --, Section III, Subarticle NCA-3800, 1986 Edition. I

-k, j \\{. I APPENDIX A NRC BVlLETIN 88-05 AND SUPPLEMENTS 1 AND 2 I l 4 1 ) l l I i NUREG-1402

OMB No.i 3150 0011 NRCR 88-05 i UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 May 6, 10PB NRC BULLETIN NO. 88-05: NONCONFORMING MATERIALS SUPPLIED BY PIPING SUPPLIES, INC. AT FOLSOM, NEW JERSEY AND WEST JERSEY MANUFACTURING COMPANY AT WILLIAPSTOWN. NEW JERSEY i Addressees: All holders of operating licenses or construction pemits for nuclear power reactors.

Purpose:

The purpose of this bulletin is to require that licensees submit infomation regarding materials supplied by Piping Supplies, Incorporated (PSI) at Folsom, Jersey and to request that licensees 1)g Company (WJM) at Williamstown, New New Jersey and West Jersey Panufacturin take actions to assure that inaterials comply with ASPE Code and design specification requirements or are suitable for their intended service, or 2) replace such materials, i Description of Circumstances: The NRC has obtained copies of certified material test reports (CMTRs) for material supplied by PSI and WJM that contain false information about material supplied to the nuclear industry. A number of CMTRs were apparently used to certify that commercial-g'rade, foreign steel meets the requirements of ASME Code Section III, Subarticle NCA-3800, by using a demestic forging company's letterhead. There was no evidence that PSI or WJM perfomed or had a subcon-- tractor perfom the testing required by Section III to upgrade the comercially produced steel for these falsified CMTRs. The information available to date indicates that WJM started supplying ASME Code components to the nuclear industry in 1976, both directly as well as through intemediaries, and that l PSI started supplying ASME Code components to the nuclear industry directly and through intermediaries in 1985. In addition, WJM held an ASME Quality System Certificate (QSC-385) as a rnaterial manufacturer from November 30, 1979 to November 30, 1985. The NPC has concluded that there are potential generic safety implications at facilities that either have received direct shipment of materials furnished by PSI or WJM (i.e., pipe fittings and flanges) or received piping subassemblies and other components frem holders of ASME Certificates of Authorization or other subcontractors which incorporated materials supplied by PS1 or WJM. 8804290255 NUREG-1402 A-1

NRCB CF.n$ May 6, 19R8 Page 2 of a Actions Recuested: 1. Review purcl.asing records for your facility and detemine whether any WJP-or PSI-supplied ASME Code or ASTM materials have been furnished to your facility. The lists of purchasing and receivirp companies given in Attachments 1 and 2 have been developed through the NRC's partial review of PSI and WJM documents. It is emphasized that the NRC has not reviewed all documents; therefore, the review of records should not be limited to the companies cn these lists. The records review for PSI-supplied material should cover the period since January 1, 1985. The WJP review should cover the period since January 1, 1976, 2. For ASME Code and ASTM materials furnished by PSI or WJP that are either not yet installed in safety-related systems at your facility or are in-stalled in Safety-relat3d systems of plants under construction, the followin (perform action a and either action b or c) g actions are rouested: 4. Provide a list of WJM-and PSI-supplied materials that are found not to be in conformance with the applicable code requirements or procure-ment specifications and identify the applications in which these materials are used or will be used. Include the material specifi-cation, the nature of the component (e.g., pipe flange), size and pressure rating; also indicate the chain of purchase, and either b. Take actions that provide assurance that all received materials comply with ASME Code Section III, ASTM, and applicable procurement specifica-tion requirements, or that demonstrate that such materials are suitable for the intended service. For example, this program should include specific verification that austenitic stainless steels have been received in a non-sensitized condition, or, c. Replace all questionable fittings and flanges with materials that have been manufactured in full compliance with ASPE Code Section !!!, ASTP, and the applicable procurement specification reouirements.

3. ' For ASME Code and ASTM materials furnished by WJM or PSI already installed in safety-related systems in operating plants, the following actions are requested:

a. Provide a list of the WJM-and PSI-supplied materials that are found not to be in conformance with the applicable code reouirements or pro-curement specifications and identify the applications in which the traterials are used. Include the material specification, the nature of the component (e.g., pipe flance), size, and pressure ratingt also indicate the chain of purchase, b. Take actions requested in 2b or 2c above. However, an evaluetion should be undertaken prior to replacing questicnable material in accordance with 2c above that considers the occupational radiation NUREG-1402 A-2

NRCB 88-05 May 6, 1988 Pace 3 of 4 exposure that would be received during the replacement process. This . evaluation should be considered in developing the method and timino l of material replacements. c. Document and maintain for inspection a basis for continued plant operation if the procram requested in item 3b has not been completed within 120 days of the date of receipt of this bulletin. 4 For any PSI-or WJM-supplied materials having suspect CMTRs and used in systems that are not safety-related, take actions comensurate with the function to be performed. 5. Maintain for inspection the documentation of the specific actions taken l for the identified materials. 6 For operating plants, al; scheduled actions should be completed before a restart from the next major outage starting after 180 days from the date of receipt of this bulletin. For plants under construction all scheduled actions and-the reporting recuired by 2 below should be completed prior to the planned fuel load date. If any addressee cannot meet this schedule, they should justify to the NRC their proposed alternative schedule. Reporting Reouirements: 1. Provide a written report within 120 days of the date of receipt of this bulletin that either: a. States that no WJM-or PSI-supplied materials have been furnished for your facility for use in safety-related systems, if such is the case, or b. Provides the information requested in items 2a and 3a above that indicates which materials have been found not to be in conformance with the applicable code reovirements or procurement specifications, confirms completion of otbar actions requested in items 2b or c. 3b and 4, and provides a schedule for completing any remaining actions. l 2. Confirmation of completion of all scheduled actions shall be submitted l to the NRC Within 60 days of completion for operating plants and prior to the fuel load date for plants under construction. The written reports, required above, shall be addressed to the U.S. Nuclear Regulatory Comission, ATTN: Document Control Desk Washington, D.C.

20555, under oath or affirmation under the provisions of Section 18?a, Atomic Energy Act of 1954, as amended.

In addition, a copy shall be submitted to the appro-priate Regional Administrator. This requirement for information was approved by the Office of Management and Budget under clearance number 3150-0011. NUREG-1402 A-3 4

) NRCB 88-05 May 6, 1988 Page 4 of 4 If you have any questions regardino this matter, please contact one of the technical contacts listed below or the Regional Administrator of the appro-priate NRC Regional Office. ( les E. Rossi, DirectorC K Thar J Division of Operational Events Assessnent Office of Nuclear Reactor Regulation Technical Contacts: Ray C111mbeg, NRR i (301)4923220 Ed Baker, NRR (301) 492-3221 Attachments: 1. Table 1 - Known and Intended Recipients of Carbon Steel Materials furnished by PSI or WJM 2. Table 2 Known and Intended Recipients of Stainless Steel Materials furnished by PSI or WJM 3. List of Recently Issued NRC Bulletins h M ] NUREG-1402 A-4 i N Naw-vre--g .-r-, ,..,,,,. 9 -

1 NRCB 88-05 1 May 6, 1988 Page 1 of 2 l TABLE : - KNOWN AND INTENDED RECIPIENTS OF CARBON STEEL MATERIALS FURNISHED BY PSI AND WM i Purchaser Receiving Company Nuclear Plant (if known) Padnor Alloys, Inc. Bechtel Power Corp. Pilgrim Capitol Pipe & Steel Rechtel Power Corp. Midland Pullman Power Products Pullman Power Products Palo Verde Pullman Power Products Daniel Wolf Creek Pullman Power Products Cleveland Electric Perry Pullman Power Products Bechtel Power Corp. South Texas Pullman Power Products Pullman Power San Onofre Pullman Power Products Pullman Power Vogtle Tyler Davison Rechtel Power Corp. Grand Gulf Osborne Brothers Welding j Supply General Electric Perry i HUB Incorporated Duke Power Oconee HUB Incorporated Bechtel Power Corp. Arkansas HUB Incorporated Bechtel Power Corp. WNP-? Chicago Tube & Iron Omaha Public Power Fort Calhoun ] District i Chicago Tube & Iron Comonwealth Edison Braidwood Chicago Tube & Iron Cherne Construction Co. Marble Hill Chicago Tube f. Iron Northern States Power Chicago Tube & Iron Consumer Power Palisades i Dravo Corp. Dravo Corp. Seabrook .loliet Yalves, Inc. Joliet Valves, Inc. j McJunkin Bechtel Power Corp. San Onofre Guyon Alloys Babcock & Wilcox ITT Grinnell ITT Grinnell Guyon Alloys, Inc. Bechtel Power Corp. Limerick Guyon Alloys, Inc. Northeast Nuclear Energy Millstone e Company Guyon Alloys, Inc. Bechtel c/o PP&L Susquehanna Guyon Alloys. Inc. Duke Power Catawba Guyon Alloys Inc. Bechtel Power Corp. Hope Creek e Guyon Alloys Inc. WNP-2 Guyon Alloys, Inc. Carolina Power & Light Rrunswick Guyon Alloys, Inc. Baldwin Associates Clinton i Guyon Alloys. Inc. South Carolina Electric V.C. Sumer and Gas Guyon Alloys, Inc. Carolina Power & Licht Shearon Harris Guyon Alloys, Inc. Gulf States River Rend Bellows American Standard American Standard Louis P. Canuso Bechtel/Public Service Hope Creek 4 NUREG-1402 A-5 I o o I NRCB 88 05 May 6, 1988 Page 2 of 2 TABLE 1 - KNOWN AND INTENDED RECIPIENTS OF CARBON STEEL MATERIALS FURNISHED BY PSI AND WJM (continued) Purchaser Receiving Company Nuclear Plant (if known1 Capitol Pipe & Steel Bechtel Hope Creek Gulfalloy Pechtel Power Corp. Palo Verde Public Service Electric and Gas PSE&G Salem Conax Conax Consolidated Power

• Pechtel Powtr South Texas Consolida+ed Power
• Duke Power McGuire Consolidated Power
• Boston Edison Pilgrim Consolidated Power
• Niagara Mohawk Nine Mile Point Consolidated Power
• Philadelphia Electric Limerick Louis P. Canuso Bechtel Corp.

Hope Creek Dubose Toledo Edison Davis-Besse Dubose Florida Power Crystal River Dubose TVA Sequoyah Dubose TVA Watts Bar Dubose PP&L Susquehanna Dubose SMUD Rancho Seco Dubose Rochester Gas & Electric Ginna Dubose Duke Power Oconee Dubose Power Authority State FitzPatrick of N.Y. Dubose South Carolina Electric and Gas

• Consolidated Power is also known as Consolidated Piping and Supply located in Birmingham, Alabt.ma, Furlong, Pa., and Charlotte, N.C.

NUREG-1402 A-6 i

i Attachment ? NRCB 88-05 May 6, 1988 1 Page 1 of 1 TABLE 2 - KNOWN AND INTENDED RECIPIENTS OF STAINLESS STEEL MATERIALS FURNISHED BY PSI AND WJM i i Purchaser Receivino Company Nuclear Plant (if known) 1 HUB Incorporated Bechtel Power Corp. Limerick J Radnor Alloys Radnor Alloys i Pullman Power Products Pullman Power Dravo Corp. Dravo Corp. Seabrook Louis P. Canuso, Inc. Philadephia Electric Peach Bottom L. P. Canuso, Inc. Rechtel Power Corp. I 4 L n l NUREG-1402 A-7 b

DMB No.: 3150-0011 NRCB B8 05, Supplement 1 ? UNITED STATES NUCLEAR REGULATORY COMM15510N t OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 June 15, 1988 NPC BULLETIN NO. PP 05, SUPPLEMENT 1: NONCONFORMING MATERI ALS SUPPLIED BY f PlPING SUPPLIES, INC. AT FOLSOM, NEL' JERSEY AND WEST JERSEY MANUFACTURING COMPANY AT WILL4SMSTOWN, NEW JERSEY j i Addressees: All holders of operating licenses or construction permits for nuclear power reactors.

Purpose:

The purpose of this supplement is to 1) provide additional information con. Jersey Manufacturing Company (WJM)g Supplies, Incorporated (PSI) and Wes cerning material supplied by Pipin, 2) reduce the scope of the requested materials rev.iew to only flenges and fittings. 3) delineate actions licensees are requested to take to identify these materials and to determine whether the materials comply with ASME and ASTM design and material specifications, and 4) clarify what actions licensees are requested to take once they identify material that does not comply with the above material specifications. Description of Circumstances: On June 10, 1988 the NRC staff was informed by Carolina Power & Light (CP&L) that the Shearon Harris Nuclear Plant had tested two flanges from their ware-house that had been supplied by WJM. The two flanges were identified as belonging to Heat No. 7218, SA-105 material. The CP&L test results did not match those reported on WJM's Certified Material Test Reports (CMTRs) and did not meet the tensile and yield strenoth requirements for SA-103 material. Required minimam tensile strength is 70 KS! whereas the measured tensile strengths were 45 KS! and 46 KSt. The tensile strength reported on the CMTP was 77 KSt. Required minimum yield strength is 36.KS! whereas the peasured yield strengths were 27 KS! and 31 KS!. The yield strength reported on the CMTR was 50 KSI. Measured chemistry composition was also out of specification, nutably percent carbon was very low at 0.045 and manganese was measured at 0.32 (required range 0.6 to 1.05). Bulletin 88-05 requires that all PSI and WJM supplied material be identified and that a determination be made as to its suitability for the intended or B806150186 NUREG-1402 A-8 ^

NRCB 88-05, Supplement 1 June 15, 1938 Page 2 of 3 actual application. This supplement narrows the scope of review from ASME and ASTM

• materials
• to ASME and ASTM fittings and flanges.

In view of the recent verification that flanges which do not comply with ASME and ASTM speci-fications have been supplied to the nuclear industry, the time frames for certein actions are also modified by this supplement. Actions Requested: The actions requested in Bulletin 88-05 remain in effect with the following additions: 1. Review of purchasing records may be reduced in scope from ASME and ASTM" materials"toASMEandASTM*fittingsandfijnges"andthe review should be initiated and completed promptly. 2. The scope of paragraph 2 of Bulletin B8-05 is reduced from ASPE and ASTM " materials" to ASME and ASTM

• flanges and fittings." All other provisions of paragraph 2 of Bulletin 88-05 remain in effect.

3. The scope of paragraph 3 of Bulletin 88-05 is reduced from ASME and ASTP " materials" to ASME and ASTM

• flanges and fittings." For ASME and ASTM flanges and fittings furnished by PSI or WJM already installed in tefety-related systems in operating plants, the following actions are requested:

a. Commence appropriate testing of accessible flanges and fittings promptly to identify confomance of materials to ASME and ASTM material specifications. Test results for flanges and fittings reported to be from the same heat should be compared for consist-ency and for conformance to the ASME/ASTP specifications and to values listed on material CMTRs. Any deviation from the specifi-cation requires an appropriate analysis justifying contir.ued operation, b. If any inaccessible flanges or fittings are identified, an analysis must be perfomed justifying continued operation. c. All other provisions of paragraph 3 of Bulletin 88-05 remain in effect. 4 For flanges and fittings already identified as having been supplied by PSI or WJM, the actions requested in 3a and 3b above are to be completed within 30 days of receipt of this supplement. For flanges and fittings identified after receipt of this supplement, the actions requested in 3a and 3b above are to be completed within 30 days of identifying the flanges or fittings as being supplied by PSI and WJM. jf Based on the discovery by CPAL of nonconfoming flanges and on NRC review of records of WJM's production of numerous flanges purportedly from Heat No. 7218, licensees should specifically be alert to identify records for flanges from Heat No. 7218. NUREG-1402 A-9 n

NRCB 88-05, Supplement 1 June 15, 1988 Page 3 of 3 5. Addressees are requested to retain nonconforming materials until advised further by the NRC. Nonconforming materials should be segregated to ensure that they are not inadvertently used. 6. Addressees are encouraged to report the results of tests of PSI and WJW. supplied flanges and fittings to the INPO Nuclear hetwork for dissemi-nation to the industry. Reporting Recuirements: The reporting requirements of Bulletin 88-05 remain in effect with the following additions: f 1. The NRC Operations Center should be notified by telephone, 202 951-0550, of the need for analysis to justify continued operation as required in para-graphs 3a and 3b. Where the need for analysis to justify continued operation results in a requirement for a report under 10 CFR 50.72, the notification to the Operations Center should be in accordance with the reporting times re-quired by 10 CFR 50.72. If the need for analysis to justify continued operation would not result in a requirement for a report under 10 CFR 50.??, 1 the notification to the Operations Center should be made within 48 hours. 1 2. Include the results of all tests of PSI or WJM materials in the written response to Bulletin 88-05. The written reports required.above shall be addressed to the U.S. Nuclear Regulatory Comission, ATTN. Document Control Desk, Washington, D.C. 20555, under oath or af'irmation under the provisions of Section 182a, Atomic Energy Act of 1954, as amended, in addition, a copy shall be submitted to the appro-priate Regional Administrator. This requirenent for infomation was approved by the Office of Management and Budget under blanket clearance number 3150-0011. Coments on burden and dupli-ications should be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C. 20503. If you have any questions about this matter, please contact one of the technical contacts listed below or the Regional Administrator of the appropriate NRC regional office. 1 ~ b Charles Rossi, Director Division of Operational Events Assessmer.t Office of Nuclear Reactor Regulation Technical Contacts: Ray Cilimberg, NRR (301)492-3220 Ed Baker, NRR (301) t.92-3221

Attachment:

List of Recently issued NRC Bulletins j l NUREG-1402 A-10 l n

Attachment NRCB 88 05, Supplement 1 June 15, 1980 LIST OF RECENTLY !$5UED NRC BULLETIN $ i Bulletin Date of No. Sub.iect issuance issued to 88 07 Power Oscillations in 6/15/88 All holders of OLs BoilingWaterReactors(BWRs) or cps for BWRs. 88-06 Actions to be Taken for 6/14/88 All NRC licensees the Transportation of authorized to Model No. Spec 2-T manufacture, j Radiographic Exposure distribute, or 1 Device operate radiographic i exposure devices or source changers. 87-02, Fastener Testing to 6/10/88 All holders of OLs Supplement 2 Detemine Conformance or cps for nuclear with Applicable Material power reactors. Specifications 88-05 Nonconforming Materials 5/6/88 All holders of OLs Supplied by Piping Supplies, or cps for nuclear Inc. at Folsom, New Jersey power reactors, and West Jersey Manufacturing Company at Williamstown, New Jersey 88-04 Potential Safety-Related 5/5/88 All. holders of OLs Pump Loss or cps for nuclear power reactors. 85-03, Motor-Operated Valve Common 4/27/00 All holders of OLs Supplement 1 Mode Failures During Plant or cps for BWRs. Transients Due to Improper Switch Settings B7-02, Fastener Testing to 4/22/88 All holders of OLs Supplement 1 Determine Conformance or cps for nuclear with Applicable Material power reactors. Specifications 88-03 Inadequate Latch Engagement 3/10/88 All holders of OLs in HFA Type Latching Relays or cps for nuclear Manufar.tured by General power reactors. Electric (GE) Company OL = Operating License CP = Construction Pemit NUREG-1402 A-11 n m

i f OMB No: 3150 0011 hRC8 68 05. Supplement 2 Uhlit0 $1Afts i h0 CLEAR REGUL ATORY COMM15510h OFFICE OF NUCLEAR REAtf0R REGULAT10h WASHlhG10h. 0.C. 20555 August 3. 1968 i NRC 80Litfik h0. 88 05. SUPPLEMENT 2: h0ht0NFORMING MATERIAL 5 $UPPLIED BY PlPING SUPPLit5. Iht. Al FOLSCM NEW JER5[Y AND Wtst JERSET MANUFACTURING COMPAhY At WILLIAMSTOWN. htW JER5tY a Accressees: All bolders of operating licenses or construction permits for nuclear power reactors. Purcose: The purpose of this supplement is to (1) modify the schedule for actions addressees vere requested to perform in Sulletin 88 05 and Supplement 1 and (2) provide additional information concerning materials supplied by Pipin'; Supplies. Incorporated (PSI). West Jersey Manuf acturing (WJM). and a recently identified af filiated company. Chews Landing Metal Manu. facturers Incorporated (CLM). Descriotion of Circumstances: On July 22. 1906, the NRC staff met with representatives of the Nuclear Manage-ment and Resources Council (huMARC) to discuss the status of licensees' actions in response to Bulletin 88 05 and Supplement 1. During this meeting. NUMARC presented information on licensee and NUMARC/ Electric Power Research Institute (EPRI) testing and evaluation methodology of P51/WJM flanges. This information was sumarized in a letter to the NRC from NUMARC dated July 25.1988 and a detailed report and proposal was subsequently submitted on July 29, 1988 (Attachment 1). Based on the reported measurement and analytical results to date, the hRC has concluded that for full power licensees it is appropriate to suspend. tempo-j rarily, the field measurements, testing. records review, and the preparation 1 of justifications for continued operations (JCOs) that were requested by Bul. letin 88 05 and Supplement I untti further notice. Addressees that have not received a full power license are requested to continue the in situ testing and the records review. The time frames of interest remain as specified in the original Bulletin, January 1, 1976 to present. During the temporary suspension of the requested activities. the NRC will review the measuremer.t anc test data and results of analysis performed and determine the extent to 8808030289 NUREG-1402 A-12 A.

NRCB 68 05. Supplement 2 August 3. 1988 Page 2 of 3 which further actions are appropriate tb assure the continued safe operation i of nuclear power plants. However, addressees should continue to analyze the j test results performed to date. On July 22.19BB. the NRC staf f con.pleted its review of P$1/WJM/CLM purchase order and invoice records. Based on this review, the staff has determine 0 thct PSl/WJM/CLM provided product forms in addition to flanges and fittings. The additic,nal product forms are identified in Attachment 2 and a list of nuclear power plants that were identified as possible recipients of P11/WJM/CLM materials e is provideo in Attachment 3. The NRC staff also identified Certified Materie) Test Reports (CM1Rs) for ASME 5ection 111 materials from CLM. which also should bs considered as suspect. CLP was owned by parties involved in PS) and WJM and the persons signing the CMIRs for CLM also signes the CM1Rs for PS) and WJh. ' provices a listing of additional intermediary suppliers / fabricators of P51/hJM/CLM products. Bulletin 88 05 identified 1976 as the beginning date for suspect sisterials provided by PSI /WJM; however. information available to the NRC now indicates that WJM may have provided ASME materials as early as 1962. The NRC is providing the above information to assist the industry in their understanding of the P51/WJM/CLM issue. Actions Requested: The actions requested in Bulletin 88 05 and Supplement 1 are temporarily sus-penced with the following exceptions: 1. Addressees that have not received a full power operating license' are requested to continue the records review and the in. situ testing of installed flanges and fittings. 2. Addressees are requested to maintain for inspection the documentation of the specific actions taken for the identified materials, 3. Addressets are requested to retain nonconforming materials untti advised i further by the NRC. 4. Addressees are encouraged to report the results of tests of P51 and WJM supplied flanges and fittings to the lhPO Nuclear Network for dissemination to the industry. Reporting Requirements: The reporting requirements of Bulletin 88 05 and Supplement 1 are temporarily suspended with the following exceptions: 1. Holders of full power operating licenses are requ,tred to report the results of their records review testing, and analysis performed as of the date of this supp'ement in accordance with the 120 cay reporting requirement speci-fied in ptregraph 1 of bulletin 88 05. 2. Holders of construction permits are required to report the results of the records re. view testing. and analysis prior to the planned fuel load date. NUREG-1402 A-13 . ~

i NRC6 88 05. Supplement 2 August 3. 1988 Page 3 of 3 3f you have any questions about this siatter, please contact one of the technical contacts listed below or the Regional Administrator of the appropriate NRC regional office. 4 M7 Charles I. Rossi. Director Division of Operational Events Assessment Office of huclear Reactor Regulation Technical Centacts: Ray C111mberg NRR d (301) 492 3220 ) Ed Baker. NRR (301) 492 3221 Atta cher.tr.ts. 3. Ltr to NRC fm NUMRC dtd July 29. 1988 l 2. Product Forms Sold by WJM/PS!/ Chews Landing 3. kuclear Plants Receiving Suspect Material 4. Purchasers Receiving suspect Materia) 5. List of Recently Issued hRC Bulletins j l l I i NUREG-1402 A-14

l I 4 i g Attachment No. 1 NRC8 88-05 Supplement 2 l NucLtAt MANA9fMlWT AND etsoveCis COUNCIL August 3, 1958 l

• • • 1,1-w..'. e f. t 3:: + wo:"p* ::: M* *t H4

n;. !?; *;i:

l i i f July 29,1988 ) Mr. Thomas T. Martin Associate Director for Inspection and Technical Assessment 4 Office of Nuclear Reactor Regulation U. 5. Nuclear Regulatory Commission Washington, D. C. 20555 Dear Mr. Martint in a meeting held July 22 with NRC, NUMARC requested that utility activities relative to NRC Bulletin 88 05 and Supplement 1 be suspended. This suspension request was based on a generic analysis provided to NRC by NUMARC's letter of July 22, in the subject NRC meeting NUMARC also presented an analysis of utility and laboratory test data obtained to date. NUMARC's letter of July 25 to Dr. Thomas Murley formaltreu the request for suspension, l in that letter, NUMARC comitted to provide a written report to NRC reflecting I the test data and conclusions presented in the July 22 meeting, and providing quantitative statistical evaluations relative to the conclusions presented at this meeting. Tt.at report is'hereby provided as an attachment. As noted previously, the NUMARC laboratory testing program will be carried to completion even if utility test efforts are suspended. An update of the attached report will be provided addressing conclusion of the NUMARC laboratory testing program as well as inclusion of field test data not yet reflected, 3 We would like to reiterate the importance of timely action in your consideration of NUMARC's request for suspension. Utility resource expenditures of major proportions are presently continuing without abatement. Continuation of testing is not resource effective and, as documented in the attachment, would not be expected to result in additional insights. Moreover, in conjunction with the generic analysis previously provided, the attachment substantiates that no significant public health and safety concern is represented by this issue. L l NUREG-1402 A-15 i

---

~

<~ Mr. Thomas T. Martin July 29.1988 Page t WpMARC is studying all available information to determine what industry action should be taken to come to final resolution of this issue. We will discuss our intentions with you and your staff in the near future. If you or your staff have any questions, please do not hesitate to contact us at any tire. Sincerely, r4w 4 William H. Rasin Director, Technical Division WHR/ reb Attachment sc: lawrence C. Shao Director, Division of Engineering and System Technology D. J. Mcdonald Executive Director National Board of Soiler and Pressure Vessel Inspectors I NUREG-1402 A-16

i l I WUMARC CENERIC TESTING PROCRAM a i RESPONSE TO NRC SULttTIN 88-05 i i INTERIM REPORT July 29,1986 i 9 l J ) e. Prepared By j l lechtel National, Inc. l San Francisco, California 94105 J i t Prepared For Electric Power 3412 Hillview Avenue Palo Alto. California 94203 t i L s NUREG-1402 A-17

AngTRACT be NRC Britetin 68-05 addressed the alleged f alsification of Certified Materlate Test Reporte (CMTRe) by two suppliers. WM and PSI. of piping flanges and fittings. WMARC. through the technical management of EPK!. developed a multifaceted program to assist utilities in addreselag this bulletin. L4boratory testing of euepect material, the compilation of utility test date and analysia'of that data are reported. % ese data show in general that, except for blind flanges, the swepect asterial meets tenelle strength requiressente and is satisfactory for ASME Code applications. The hardness testing results for the ease seteriale eahibit a broad scatter band which would justify application of a testing tolerance band in comparison to the ASTM A370 conversion free hardness to tensite strength. %e field and laboratery testing results both exhibit the same broad scatter band. A laboratory generated best fit curve ir used to relate measured field hardnese to tensile attength. W e field hardness test date for 1334 itene show the same acatter band as found in laborotory teste, and follove the same general bell shape hardness distribution se laboratory hardnese teste. h e similarity in shapes and the lack of bumps at either the low ende or the high ende of those laboratory and field histograse indicates that there is r.ot a concern for low attength material or high strength asterial. Applying a best fit approach fres laboratory hardness and tenaile data to field hardness det6 eesults in an estie.ste of strength. De best fit approach to the field data indicates that the vast mejerity are acceptable. Based on the laboratory testing and extensive field testing, it is concluded there is no materiale problem, escept possibly for some blind flanges. Slind flanges and other components were addressed analytically in the WMARC generic analysis report, and it was shown that in the majority of cases there would not be a stress concern even if strength in the order of 40 KSI were to be assumed. his interia report concludes that the seterial has acceptable attength and except for some blind flanges is satisfactory for ASMI Code applications. %e continued use of these flanges and fittings does not presen+ e eafety problem. Recoemendations are made for follow-up activities. .g. lit be NUREG-1402 A-18

NUMARC CENERIC TESTINC PRDCRAM RESPONSE TO NRC SULLETIN 88-05 INTERIM REPORT TABLE OT CONTENTS Pare ABSTRACT................................................................ i T ABL E O F CO NTI NG S....................................................... 11 i LI S T O F I LLU S T RAT I O N S................................................... iii INTRODUCTION........................................................ 1 BACKCROUND.................................................... 1 NUMARC M ULTI F ACE TED TR DC RAM................................... 1 CENERIC STRESS ANALYSIS (Ref tr to previous letter of t r a n s mi t t a l t o NRC )........................................ 1 NUMA R C TE S T I N G PR OG RAM............................................. 1 MITHODS....................................................... 1 D AT A CO MP I LATI O N AND RE S U LT S.................................. 2 ANALYSIS........................................................... 2 LA B O RATOR Y TE S T I N C............................................ - 2 E QUOT I P-TE NSI LE CORRE LATI ON................................... 2 UTILITY TESTING............................................... 3 TIELD KARDNESS TO TENSILE..................................... 3 BLIND TLANCES................................................. 3 D AT A QUANTITY AND STATISTICAL $1CNITICANCE.................... 4 4 TE S T I N C S UMMAR Y..................................,............ T OLE RAN CE S LOWE R AND UP PER.................................... 4 STAINLESS..................................................... 5 CONCLUSIONS........................................................ 5 RE C0KKE ND AT I O N..................................................... 5 $ U SP I KD RE CO RD S R E VI EW........................................ 5 CO MP LE T E LA B PROG RAM.......................................... 5 COM71 LE E XI ST I NG T I E LD TE ST D AT A.............................. 5-W R I T E T OLLO W-O H RI PORT........................................ 5 t- -ii-118 5m NUREG-1402 A-19

Lig? 0F !LLUSTRATIONS TABLE S Table 1 Suunsry of Migh Hardness Limite Table 2 Svamary of Stainless Steel Testo FICURE S 4 Figure 1 Mistogram of laboratory Tensile Results Figure 2 Equotip as SHN Compared to UTS and ASTM A370 Figure 3 Best Tit Equotip Compared to UTS' Figure & Histogram of Laboratory Hardness Figure $ Mistogran of Field Hardness ' Figure.4 Best Fit Data Applied to Field Hardness I, -lii-118 5m .NUREG-1402 A-20

1 I I 1NTRODUCT10N SACKCROUND i The NRC issued Bulletin 88-05 regarding allegeh falsification of Certified Materials Test Reports (CMTRs) by West Jersey Manufacturing Co. (WJN) and Piping Systems, Inc. (PSI). Specific actions were required of utilities. Some of these could ef ficiently be addressed by a generic program. NUMARClnitia te d such a program. The NRC issued Supplement 1-to 88-05 subsequent to reports of 1 two blind flanges having low tensile strength. The supplement reeutred utilities to perform field tests on identified installed WJM/ PSI items. The supplement also focused ef fort on piping flanges and fittings. The NUMARC program was modified to coordinate and standardise field testing methods and to compile utility generated data. Concurrently,;the generic NUMARC laboratory testing program has been in progress. i NUMARC MULT!yActTED PRDCKAM 8ecause several actions were required by 88-05 which could be ef ficiently I addressed in a generic manner, NUMARC undertook the activitise described herein as well as the testing and test data analysis which are the subject of this report. A. Review of records to permit scope limitation. '3. Review of records to identify intermediate and secondary supply routes. C. Interface with Authorised Inspection Agencies and the National Board of Soiler and Pressure Vessel Inspectors. D. Generic stress analysis of fittings and flanges. E. Testing, data compilation and evaluation. CENERIC STRESS ANALYS!$ The generic stress analysis has been completed, reviewed with and provided to the NRC. The analysis indicates that there is little concern for the stress integrity of the fittings or flanges even if the asteriale were of substantially lower attength when compared to the attength requirements of S A-10 5. This report was formally transmitted to the NRC by NUMARC on July 22, 1988. 7he testing program is described in the following sections of this report. j NUMARC TESTING PROGRAM NITHODS This program contains two main elements: first, comprehensive laboratory testing of suspect items contributed by utilities; and second, utility generated data of destructive laboratory tests and in situ tests of installed suspect items. 118 5r. NUREG-1402 A-21

MUNARC laboratory test methods follow AFTN standards for tensile testing to produce values for UTS, Y$ 1El and IRA. Tensile strength correlations were developed based upon Equotip testing. Chemical analysis utilises spectrographic analysis and portable X-ray fluorescence analysis methods. All laboratory testing equipment is calibrated to appropriate standards. Utility test data of installed items or warehouse items has principal.ly been portable hardness testing by means of the Equotip device. Other hardness test devices may also have been used in a few instances. The basis for selection of hardness test methods and the NUMARC training / coordination have been described previously. For austenitic stainlese steel items, the principle tests method has been a simple magnetic check. Some alloy analysis and replication metallography have been perf ormed. To the extent that utilities have contributed laboratory test data, these data has been accepted. These data are being reviewed for consistency and errors. DATA COMPILATION AND RES*JLTS Ceneric laboratory test date has been developed for 123 items to date contributed by utilities. To date, the utilities have provided data regarding 1334 field hardness test items and 108 tensile results. The results are discussed in the following analysis. The actual amount of data used in this report is indicated on the plots or charts. Not all data is in the computer data base. NUMARC has provided the NRC with computer discs and printouts as of 7/19/86. Some additional copies were provided during the July 22, 1988 seating. ANALY$l$ LABORATORY TESTING All tensile test results exceed 70 KSI or are within the anticipated tolerance band. Figure 1 shows a histogram of laboratory tensile results. In general, field tests were performed with EQUOTIP testers and the data converted to BHN. For reasons discussed below, EQUOTIP values are used in this report. Figure 2 shows a plot of laboratory tensile results and EQUOTIP hardness expressed as BHN date. Almost all the hardness data points f all at or below the ASTN A370 BHN tensile conversion line, indicating that this is a conservative approach, and that a test tolerance f actor is required to avoid inappropriate rejection of acceptable asterial by field hardness test methods. It is apparent that the BHN tensile conversion approach is no longer appropriate f or this application. EQUOTIP-TINSILE C0bVERSION Another more accurate approach to assess the field hardness data is to develop i a best fit line for the laboratory hardness using the original EQUOTIP (als o re f erred to a s Leeb values) and tensile data. Th a t line, shown in Figure 3, was developed by computer program. The application of the tolerance or the 116 5m NUREG-1402 A-22

best fit' approach are discussed below subequent to a brief analysis of the utility field data. The histogree of Wooratory hardnese data empraesed in EQUC71p values is shown in Figure d.. In!LITY TEg71NC The utility-provided laboratory data is consistent with the generie program tes t data. We utilities have provided one set of data on a blind flange, Heat 7218, which is consistent with the two teste cited in 88-05 Supplement 1. %is data point is not yet in the computer printout. Otter than this, no substrength material has been reported based on tenelle tests. These utilities have reported tensile strength for 108 items. Eight itere slightly below 70 K51 have been reported. he remaining 101 values exceed 70 K51. In one case the utility engineer indicated there was a substae speeleen removed free installed flange and was transverse to the primary working direction rather than parallel. Wese slightly low values are readily explained by the test direction,: and by published data which confirms that tonelle test results fecm - product testing may be se such as 10 percent below the minious speciff sd attength. None of these utilities reported.ettength values are a concern. he utility generated hardnese data is shown in the histogree of Figure 5. This histostas het the same general bell shape as the histogram of laboratory herdnete data. In simple terms, the bell shapes in both laboratory and field histograme and the lack of bumps at the low hardness ends of the histograma indicates that there is not a concern for low strength material. b is means that the vast majority of field itete would exceed.70 R$1 if tested and that the reasinder would be within the expected tolerance band. %e conclusion is that installed items are acceptable and do not present a esterial concern, except for some blind flanges. TIILD RARDhTSS TO TINS!LE It is appropriate to compare the best fit curves of laboratory hardnese and tonelle results and apply the results of that plot to the utility generated hardnese data. When this is done, refer to Figure 6. all itene are shown to be accepteble. It must be realised ; hat a best fit curve of field hardnese should never be used to reject installed itees, because some items which fall below the line can be within the acceptable tolerance band. his is shown by the f act that the original data had some acceptable items below the best fit cu rve. %e best fit curve may be applied to warehouse itese prior to installation, and should not be the sole justification for removal of installed i itete. This curve increases the confidence that the installed items are as initially intended to be. BLIND T1.AN0t$ The best fit curve applied to field data, or a field hardness test tolerance does riot eliminate the fact that there are data in the histograne (but not ye t in the computer data base) which indicates that blind flanges may be a concern f or strength reasons. Howeve r, the s t re e t analytical data provided to the NR; indicates that these substrength blinds are not a str'ess probles for service conditione. 118 k HUREG-1402 A-23 1

i h e lowest hardness test result in either laboratory er field, aside from the suspect blind flanses, is 350 tp. - his is the lowest of a continuous spectrue of values. he 13 suspect blind flanges are at approximately 330 Le and appear to be a unique group separate from the general population of acceptable saterial. DATA QUAN7ITY AND STATISTICAL $1CNIFICANCE Analysis indicate s that there are suf ficient field data upon which to draw conclusions. h ere is no need for additional field hardness data. There is also substantial tonelle test data which perinite interin conclusione. Notr-parametric tolerance limit statistical calculations were used. The laboratory tensile results of 123 If ese provide 95 percent confidence that more than 97 percent of the population esceede 60.600 poi tensile strength. The utility provided 108 tensile test resulte provide 95 percent confidence l that more than 97 percent of the population exceede 66,400 poi tonelle strength. k Assuming the materials come from the same population, combining both sets of l' tenelle data provides 95 percent confidence that more then 98 percent of the population exceed 60,600 poi ultimate tenelle strength. Similarly, there is 95 percent confidence that more than 98 percent of the population is less than 93,200 poi ultimate tensile strength. TESTINC

SUMMARY

The laboratory tenelle data indicates there is no technical corwern for the SA 105 material. The sinitarities between the laboratory hardness distribution histogram and the field hardnese histograms indicates that there should be no concern for installed itees given that the laboratory tensile tests indicate no concern for this saterial. The best fit curve of hardness to tenelle conversions applied to field hardness teste also indicates that there le no concern for SA 105 saterial. TOLERANCES LOVER AND UpptR The data indicate that there is me real concern for SA 105 esterial. The blind flanges of suspect material which have low tensile values have hardness'at approximately 3301c. Regarding high hardness, Table 1 shows the precedent to install materials over ^ 187 SMN to 207 SMN which are cousnon in nuclear plant piping. his table shows that 237 BHN is a value coursonly applied to f abricated items, welds, base metals and MA2, where H 5 stress corrosion cracking ($CC) is a concern in the - 2 petrochemical industry. Such SCC is mot a concern in light water reactor piping and thus a specific upper limit should not be imposed. The Structural Welding Code applies a 265 BHN limit on submerged are welds and MA2 to assure adequate strength, ductility and toughness. When recognised standards apply values such as 237 and 265 3HN to f abricated, welded and installed itene. a specific upper hardness lieit is not justified. This paragraph is discussed in SHH terne because the Code uses SHN terns. he principle high hardnese concern is weldability. If the lastalled iten has acceptable weld inspections, has sustained bolt up loads. hydrostatic teste. proof testing, functional tes t and whatever p31/151 that is applicable, then 3185e -i.. NUREG-1402 A-24

there are objective reasons to use as is. he benefits of replacing installed high hardness items with acceptable welds and MAZ are sinimal. In contrast. the risks in any replacement are greater. he A1 ARA considerations also indicate that high hardness items not be replaced unless there is a 5 plant-unique overriding concern. STAINLESS STEEL here is a relatively small amount of stainless steel installed, and very little in warehouses. To date, all tests performed on stainless steel have been acceptable. Approximately four desen items have been tested. All tensile results are acceptable, all chemical analyses are acceptable and all sensitisation tests are acceptable. Approximately 10 deten magnetic checks were also acceptable. Only one of all these test resulta la slightly low; that is, one yield strength value was 28.5 Ks1 vs. 30.0 KS1, and this difference is insignificant.. hese tests are summarised in Table 2. While the absolute number of test results is not as great as for carbon steel, the results indicate there is no concern. CONOLUSI ONS he strength of sA 105 asterial and stainless steel items which were suspect is not a concern. Rt COMMINDATIONS 1. he test results to date indicate there is no concern for satorials and thus field testing may be suspended as there is suf ficient data for evaluation. he generic stress analysis also indicates there is no concern for plausible low attength esteri&ls because it has been shown that even if substrength materials were installed, the vast majority of these cases would be acceptable. hus, it is appropriate to suspend document reviews and field testing. 2. h e laboratory program should be completed subject to constraints of-available asterial. 3. %e existing utility generated data abould be compiled and analysed in the NUMARC program. 4. A sumary report should be generated. 1185m NUREG-1402 A-25

i l LABORATORY TENSILE RESULTS 1 l 45 " doi 35o 30< NUMBER OF 25 " CASES 20" 15 " ',I;. to o l,' '3 _L y ( s 0 ~ .60 ess >70 >75 meo >s5 eso TENSILE STRENGTH (KSI) Data as of 7/22/58 FIG. 1 HISTOGRAM 0F LABORATORY TENSILE RESULTS 'l NUREG-1402 A-26 =

g - 4 a i-1<> >5 5 5 5 5 5 5 i I 55 -s ~ A m m-yg. gg a s*e em r->g e-

[ <

m gm g ag. z <2 l ,5. g** m> z l "A4 hh xz h l a 4 FIG. 2 EQUOTIP AS BHN MARDNESS COMPARED TO TENSILE & ASTM A370 NUREG-1402 A-27

- - -.-.~...-.- -.-..- -.- ~.. 1 l' Equatip Mardness vs. Uhlmste Tenelle Stength 1.aberstory Test ResuRs l e / E a' ano ./ B B l' a% = s, a i B 'g E e o g . n s _u" - l e a a* us ag a 3 g

g..

g i 3 a = HE '5 a 5 ano aquemen Uf8. mWM. t [5 m. asos t

• ff.48R l

/ EI c wmn mn m.,. om es. ve. w em mse a. o su 3 l h enaco escoe wmo vanno scene asano sanon escoo ponenTenne w W.0 Data as of i 7/22/88 FIG. 3 BEST FIT EQUOTIP VS TENSILE STRENGTH i NUREG-1402 A-28 i-

_ _. _ _ _ _. _._ _ _ _. _.. _ ~

?

ti, k

4 i F

• • • *' d SA 105 LAB EQUOTIP-22 Jufy 1988 45 40 35-30-NUMBER OF 25-CASES 20<

13 10 s-j 0 <348 348 364 381 396 414 424 437 450 443 475 >486 383 300 395 400 423 436' 449 482'474 486 l HARDNESS CATEGORIES Data as of 1/22/88 FIG. 4 HISTOGRAM OF LABORATORY EQUOTIP HARDNESS NUREG-1402 A-29 A .~

c i SA105 FIELD HARDNESS DATA omaasd m.wyises 350 g 300 o 254-3 y l mesesER OF 200-lg cases iso. se see- .a 58' d E g, m see. 3e4. see. ses. 4so. 424-437-456 463 47s. mass 363 300'.."395 489 423 436 449 462 474 '486 ggARD08ESS CATEGOR8ES - %6u E

4 ll

Observations I s -H I 6 I o Md, E II l iprorsawa

we=

3,m g 1 I I Data as of 7/19/88 i FIG. 6 SEST FIT DATA APPLIED To FIELD HARDNESS STRENGTH ESTIMATE NUREG-1402 A-31 1 O V ^

TABLE 1 1 SMARY P' HICH NotDNESS LIMITS i MAX. HARDNESS LIMITS BHN ' SA 350 197 .i SA 105 PRE 1972 N/A SA 105 POST 1972 187' ONLY IF' QUENCHED l SA 234 WPB-SUPPLEMENTARY 197 l SA . 181 N/A ] SA 182 F1 192 F2 192 l F 11. 207 -l F 22 207 ) ) AWS D1.1 WELD & HAZ, HV280-265-l f NACE MR-01 75 Rc22 237 BASE METAL, WELDS, HAZ j i l l NUREG-1402 A-32 1 i j .A a

l -* _ < h.: -TABLE 2 SUHARY OF'STAINbESS STEEL TESTS i i .i 1 STAINLESS RESULTS i 7/19/88 i TENSILE 9 HARDNESS 8 C10DCSTRY 44 l 4 SENSITIZATION 38 MAGNETIC 120 1 4 NUREG-1402 A-33 2-m

I a~ NRCB 88 05. Supplement 2 August 3. 1988 l Product Forms Sold By WJM/P51/ Chews Landina Flanges Half Couplings Full Couplings' Plate kings Penetration Plates . SA516. GR70 - Seal Plates - 5A516. GR79 (Perry)2 - Socket Weld Nozzles (CLM) Long Drain Boss -- A182F11 & F22 Radiograph Plugs (CLM) - Square Bar - 1018 Spacers Sample Probes Class 1 -- SA312. 1304 (Perry) (CLM) Guide: Lugs -- SA240.1304 Socket Welded Half Couplings Class 1 - SA182. F304L- (Vogtle) 15pecial Nozzles Pipe Caps =- SA234 ' Lugs - SA240. T304 (Palo Verce) Lugs.-- SA516. GR70 (Palo Verde) Socket Weld Couplings Plate - SA36 (Perry) Special Boss.-- A234. A105. A739 Solts-- SAlg3. GRB7 (Confrentes/ Spain) instrument' Penetration End Plate'-- SA516. GR70 (Perry) Hanger Lugs -- SA516. GR70 (Dravo / Site unknown) Socket Wela boss -- Class 1.-- SA182. F316 (Seabrook) (CLM) Transition Piece -- SA105 (Vogtle). Thermowells -- A182 (Oravo/ hunter / Site unknown) (CLM) 8ar Stock -- A105 (Dravo / Yellow Creek) (CLM) A This'is a complete list of all product forms identified during the NRC staff's review of available records. '2 Specific nuclear power plants or customers are noted in cases where the product form appeared to be a unique or special order and not wide spread. 3 2ndicates that. material was sold by Chews Landing Metal Manufacturers Inc. NUREG-1402 A-34 i I A--

( 5' NRCB 88 05. Supplement 3 August 3. 1988 huclear Plants Receivino Suspect Materia)I - Beaver Valley.

6ellefonte-i

- Browns Ferry i Calleway-Calvert Cliffs 4 Cock Diablo Canyon I -Duane Arnold = fermi. Hatch. Monticello North Anna-j - Prairie' Island . Quad Cities l- .5horaham-l~ Turkey Point Waterford Yellow Creek ' 2immer ! i 4 i r. I These nuclear power plants are in addition to those previously identified as receiving suspect material. NUREG-1402 A-35 3 .n e

NRCB 88 05. Supplement 2 . August 3. 1988 I .j< Purchasers Receivino $usoect Materia 1 Barr'.'$aunders. Inc. M.W. Kellogg (became Division of Pullman) Lake trie Iron & Metal Co.. Inc. Liberty Equipment. Co. Metal Bellows (listed as Bellows in Bulletin) . Power Piping Co. Standards Fipe & Supply Co. Inc. Tioga Pipe Supply Co.. Inc. . Tyler Oswson (listed-in error as Tyler Davison in Bulletin)' I These purchasers are in addition to those previously identified and are known to have received material for nuclear applications. NUREG-1402 A-36 a n 1 tu

NRC8 88 05. Supplement 2 August 3. 1988 LIST OF RECENTLY ISSUED kkC SULLETINS Bulletin Date of No. Subject issuance Issued to 88 08. Thern.a1 Stresses in Piping 8/4/88 All holders of OLS Supplement 2 Connected to Reactor Coolant or cps for light. Systems water cooled nuclear power reactors. 88 09 Thimble Tube lhinning in 7/26/88 All holders of OLs Westinghouse Reactors or cps for W. designed nuclear power reactors that utilitt bottom mounted instrumentation. 88 08. Thermal $ tresses in Piping 6/24/88 All holders of OLs Supplement 1 Connected to Reactor Coolant or cps for light-Systems water cooled nuclear power reactors. 86 08 Thermal $ttesses in Piping 6/22/88 All holders of OLs Connected to Reactor Coolant or cps for light-Systems water cooled nuclear power reactors. 88 05 Nonconforming Materials 6/15/88 A11 holders of OLs Supplement 1 Supplied by Piping Supplies, or cps for nuclear Inc. at Folsom. New Jersey power reactors, and West Jersey Manufacturing Company at Williamstown. New Jersey 68 07 Power Oscillations in 6/15/88 All holders of OLs boiling Water Reactors (BWRs) or cps for BWRs. BE 06 Actions to be Taken for 6/14188 All hkC licensees the Transportation of authorized to Model No. Spec 2 T manufacture. Radiographic Exposure distribute, or. Device operate radiographic exposure devices or source changers'. OL. Operating License CP = Construction Permit NUREG-1402 A-37

} 1 _4-1 APPENDIX B

SUMMARY

OF SIGNIFICANT LICENSEE RESPONSES TO.NRC SULLETIN 88, 8 { G NUREG-1402

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AP9ENDIX C CHRONOLOGY OF MEETINGS, TRIPS, CORRESPONDENCE, AND DOCUMENTS PERTAINING TO NRC BULLETIN 88-05 AND ITS SUPPLEMENTS May 6, 1988 NRC Bulletin 88-05 issued. June 15, 1988 NRC Bulletin 88-05, Supplement 1, issued. July 22, 1988 Meeting at NRC's One White Flint North office at which NUMARC provided reports entitled " Generic Analysis and Evaluation of Suspect Material Identified in NRC Bulletin 88-05" (prepared by Bechtel Power Corporation) and " Evaluation of Temperature Effects on the Equotip Hardness Tester" (prepared by Electric Power Research Institute (EPRI)). July 22, 1988 Letter from W. Rasin (NUMARC) to T. Martin (NRC) submitting Bechtel's generic analysis and EPRI's Equotip temperature evaluation reports. July 25, 1988 Letter from W. Rasin (NUMARC) to T. Murley (NRC) regarding NRC Bulletin 88-05. [ July 29, 1988 Letter from W. Rasin (NUMARC) to T. Martin (NRC) regarding NRC Bulletin 88-05. l August 3, 1988 NRC Bulletin 88-05, Supplement 2, issued. August 22-23, 1988 Trip to Georgia Power Company's Vogtle plant, Waynesboro, Georgia, to obtain information and observe field procedures relative to licensee's capability to respond to NRC Bulletin 88-05. l September 26, 1988 Summary table of licensee responses to NRC Bulle-- tin 88-05 provided by Brookhaven National Labora-tory (BNL) to the NRC. September 28-29, 1988 Trip by BNL staff to NRC's One White Flint North office to review and summarize licensee submittals in response to NRC Bulletin 88-05. October 7, 1988 Memorandum from L. Shao (NRC) to S. Varga (NRC) regarding criteria for resolving NRC Bulletin 88-05 issues for near-term operating license plants. I NUREG-1402 C-1

\\ October 13, 1988 Status and review meeting between BNL and NRC staffs at NRC's One White Flint North office to review status of activities related to NRC Bulletin 88-05. October 27, 1988 Meeting at NRC's One White Flint North office at which NUMARC presented its final report regarding NRC Bulletin 88-05.- October 27, 1988 Letter from W. Rasin (NUMARC) to F. Miraglia (NRC) submitting NUMARC's final report. i November 3, 1988 Memorandum from L. Marsh and C. Cheng (NRC) to D. Brinkman (NRC) submitting safety evaluation report for Seabrook Unit 1. November 4, 1988 Meeting at NRC's One White Flint North office at which Georgia Power Company provided its response to NRC Bulletin 88-05 for Vogtle Unit 2. November 16 and 17, 1988 Trip to Bechtel Power Corporation office in San Francisco, California, to discuss the generic analysis and evaluation report pertaining to NRC Bulletin 88-05. December 9, 1988 Letter from L. Shao (NRC) to W. Rasin (NUMARC) requesting additional information. December 15, 1988 Memorandum from L. Marsh and C. Cheng (NRC) to G. Dick (NRC) submitting safety evaluation report i for South Texas Project, Unit 2. December 1988 BNL Technical Report MT-3851-6, " Testing in Support of NRC Bulletin 88-05, WJM/ PSI Flange Evaluation," by C. J. Czajkowski, issued. January 9, 1989 Letter from W. Rasin (NUMARC) to L. Shao (NRC) t regarding NRC Bulletin 88-05, i February 3, 1989 Memorandum from L. Marsh and C. Cheng (NRC) to J. Hopkins (NRC) submitting safety evaluation report for Vogtle Unit 2. February 3,1989 Memo,andum from L. Marsh and C. Cheng (NRC) to S. Bren (NRC) submitting safety evaluation report for Shot

• ham.

February 15, 1989 Letter from F. Miraglia (NRC) to J. Colvin (NUMARC) requesting additional information. June 15, 1989 Memorandum from L. Marsh and C. Cheng (NRC) to R. Clark (NRC) submitting safety evaluation report for Limerick Unit 2. I NUREG-1402 C-2

f August 30, 1989 Letter from W. Rasin (NUMARC) to F. Miraglia (NRC) sut,mitting supplemental generic analysis report. November 2, 1989 Letter from F. Miraglia (NRC) to W. Rasin (NUMARC) requesting additional information on NUMARC report. November 28, 1989 Letter from W. Rasin (NUMARC) to F. Miraglia (NRC) responding to request for additional information. l [ NUREG-1402 C-3

y ca., APPENDIX 0 PRINCIPAL CONTRIBUTOR $ NRC staff Ornanisation H. Conrad Office of Nuclear Reactor Regulation G. Hammer Office of Nuclear Reactor Regulation R. Hermann Office of Nuclear Reactor Regulation P.T. Kuo Office of Nuclear Reactor Regulation consultants C.J. Czajkowski Brookhaven National Laboratory W.B. Grossman Brookhaven National Laboratory E.C. Rodabaugh Brookhaven National Laboratory a I } NVREG-1402 0-1 s n n C

APPENDIX E ABBREVIATIONS ANSI American National Standards Institute ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials Bechtel Bechtel Power Corporation BHN Brinell hardness number BNL Brookhaven National Laboratory CFR Code of Federal Regulations CLM Chews Landing Metal Manufacturers, Incorporated CMTR certified material test report CP&L Carolina Power & Light EPRI Electric Power Research Institute JC0 justificationforcontinuedoperation NRC U.S. Nuclear Regulatory Commission NTOL near-term operating license NUMARC-Nuclear Management and Resources Council PSI Piping Supplies, Inc. QSC quality system certificate SER safety evaluation report UTS-ultimate tensile strength 4 WJM West Jersey Manufacturing Company I l -l [ NUREG-1402 E-1 n n o

go.

v. =uci o.. veio=ac -.

ia.*vai~~.ia ru.~. a.. "ll,'".'# BIBLIOGRAPHIC DATA SHEET fMEG.1402 ne naues o.,- .svine I f tf ot AND $uel.f ti 3ggavgggah. Closecut of NRC Dulletin 88-05 Nycanfornirs %terials S@ lied try Pipirg Splies, Irc. at Folsca, NLv Jersey, ard Wst 3cesey maufacturirg Ccrpany at Willianstown, . oan ai oai comino kw Jersey. l 1990 =o ' - 6 'i April ..v v.c $ o&1l htPOMI &.vlo May I 1990 WQh T.e .&AM ,.......,~ o......,...os... o o.....o o.. n u,,,,,, c, .. w. c i n m.o..,~,,.o.... Division of Ergireeriro lechrology Office of Relear Reactor R Jlatim 9 . s. ou.s.ani uvuun U.S. Rclear Regulatry Carmnssion Washirgton,D.C. 2CL55' 1 10 SPONtoMINo 08 Ga%idatqDN ha t AND ait.hG ADD 8ith smese t, cass. It. T VPt op htPDet Divisim of Ergireerirg Techrology pg Office of Rclear ibactor Regulation U.S. Rclear Regualtory Carr'ssion

• " " * " " " ' * " - ~ ~ ' * * '

kashirgton, D.C. 20555 Ny 1938 to April 1990 o. a.. i.., ~on. IJ A.SthaCl 1,do.re a e was This report documnts the activities that led to the closeout of U.S. Rclear Regulatory Ccrmission (NRC) Bulletin 88-05, which was issued cn my 6,1908. The tulletin requimd that licera,es sutnit inforatim cn mterials supplied by Pipirs Supplies, Irc. (PSI) and Wst Jersey mrofacturirg Grpany (KN), and requesttd that ticy (1) ensure'that these mterials corplied with tre herican Society of ftichanical Ergireers, ibiler and Pressure Vessel Rde (ASK Cot) ano design specifications or were suitable for their interded service or (2) mplace such mterials. Supplenents 1 ard 2 were issued on Jme 15 ard August 3,19BB, respectively, in Supplemnt 2, another affiliated supplier, Crews t.arding Ntal Nnufacturers, Incorporated (CLM), was idmtified. The staff corcluded that (1) the analytical precedures used to qualify tie nonconforming parts ard the analysis results provide an adequate basis for resolvirg the staff's cartems regardire fittirgs and flarges; (2) even ' hough tie eterials supplied by PSI, RN, ard CLN with falsified certified eterial test reports do rot met the A9E Code, their use is an acceptable altermtive in accordance with Section 50.55a(a)(3)(ii) of Title 10 of tte Code of Federal Regulatims; (3) activities in response to Bulletin 88-05 regardirg fittings ard flarges can be closed for all operatirg plants; ard (4) licensees stould evaluate the use of pmdtet forms otter than fittirgs and flarges. L .c oocu .~i.s.<n,... ....o o,o.c.,, ion ,.......s.,, Closecut of NRC Bulletin 88-05 "a"* Rnconformiro mterial fittirgs miimited Flarges '. acuaa v etanicasios Pi NS mobi., ashstas "~> iu =oeo naus unclassified a.. .u unclassified a wues.os eaus

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