ML15266A544
| ML15266A544 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/23/2015 |
| From: | Lahey R Rensselaer Polytechnic Institute |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 28315, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR | |
| Download: ML15266A544 (9) | |
Text
NYS000576 Submitted: September 23, 2015 1 UNITED STATES 2 NUCLEAR REGULATORY COMMISSION 3 BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 4 -----------------------------------x 5 In re: Docket Nos. 50-247-LR; 50-286-LR 6 License Renewal Application Submitted by ASLBP No. 07-858-03-LR-BD01 7 Entergy Nuclear Indian Point 2, LLC, DPR-26, DPR-64 8 Entergy Nuclear Indian Point 3, LLC, and 9 Entergy Nuclear Operations, Inc. September 23, 2015 10 -----------------------------------x 11 PRE-FILED SUPPLEMENTAL TESTIMONY OF 12 DR. RICHARD T. LAHEY, JR.
13 REGARDING CONTENTIONS NYS-25, 14 NYS-26B/RK-TC-1B, AND NYS-38/RK-TC-5 15 On behalf of the State of New York (NYS or the State),
16 the Office of the Attorney General hereby submits the following 17 testimony by RICHARD T. LAHEY, JR., Ph.D. regarding Contention 18 NYS-25.
19 Q. Please state your full name.
20 A. Richard T. Lahey, Jr.
21 Q. Dr. Lahey, you have previously summarized your 22 educational and professional qualifications and submitted 23 testimony in this proceeding, correct?
Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 1
NYS000576 Submitted: September 23, 2015 1 A. Yes. I previously have submitted testimony and 2 reports in this proceeding. My education and professional 3 qualifications and experience are described in my Curricula 4 Vitae and that testimony.
5 Q. I show you what has been marked as Exhibit NYS000574 6 and NYS000575. Do you recognize those documents?
7 A. Yes. These are copies of documents that Entergy 8 disclosed to the parties in this proceeding. The first document 9 is a report published by the USNRC and is entitled NUREG/CR-10 7184, ANL-12/56, "Crack Growth Rate and Fracture Toughness Tests 11 on Irradiated Cast Stainless Steels," by Y. Chen, et al. The 12 second document is a report that is also published by the USNRC 13 entitled NUREG/CR-7185, ANL-14/10, entitled "Effects of Thermal 14 Aging and Neutron Irradiation on Crack Growth Rate and Fracture 15 Toughness of Cast Stainless Steels and Austenitic Stainless 16 Steel Welds, by O. K. Chopra, et al.
17 Q. In those titles, do you know what ANL signifies?
18 A. Yes. The abbreviation ANL stands for the Argonne 19 National Laboratories, and the designation ANL-14/10 and ANL-20 12/56 signifies, in my experience, that the documents were 21 developed by Argonne National Laboratories for the USNRC.
22 Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 2
NYS000576 Submitted: September 23, 2015 1 Q. Does NUREG/CR-7184, ANL-12/56 (NYS000574) indicate 2 what the USNRCs role was, if any, in developing the document?
3 A. Yes. Among other things, the documents bibliographic 4 data sheet (frame 177) reports that the USNRCs Division of 5 Engineering was the sponsoring organization.
6 Q. Does NUREG/CR-7185, ANL-14/10 (NYS000575) contain 7 similar information?
8 A. Yes, the cover page states that the document was 9 prepared for the USNRCs Division of Engineering, Office of 10 Nuclear Regulatory Research, and that A.S. Rao was the USNRC 11 Technical Monitor and Project Manager.
12 Q. Have you now had an opportunity to review NYS000574 13 and NYS000575?
14 A. Yes.
15 Q. Have these documents caused you to change the 16 testimony and opinions that you have previously submitted in 17 this proceeding in connection with Contention NYS-25 and 18 Contention NYS-26B/RK-TC-1B or Contention NYS-38/RK-TC-5?
19 A. No. In fact, the documents support the concerns, 20 opinions, and testimony that I have presented in this 21 proceeding.
22 Q. Please explain.
Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 3
NYS000576 Submitted: September 23, 2015 1 A. The document, "Effects of Thermal Aging and Neutron 2 Irradiation on Crack Growth Rate and Fracture Toughness of Cast 3 Stainless Steels and Austenitic Stainless Steel Welds, 4 [NUREG/CR-7185, ANL-14/10, NYS000575], contains analysis and 5 conclusions that are relevant to and supportive of the opinions 6 and testimony that I have presented. To briefly summarize, 7 among other things, the document reports that:
8 Both CASS and austenitic stainless steel welds (but not the 9 heat affected zones (HAZ)) have a duplex structure (i.e.,
10 they contain both ferritic & austenite phases), and both 11 may experience thermal embrittlement (TE). This 12 degradation mechanism applies to CASS structures, 13 components and fittings and the stainless steel welds for 14 reactor vessel internals (RVIs);
15 While thermal embrittlement (TE) may increase the hardness 16 and tensile strength of a material, it also decreases 17 ductility, fracture toughness (i.e., the resistance to 18 crack propagation), and, it decreases the impact strength 19 (i.e., due to significant shock loads) of CASS, its welds, 20 and the welds of austenitic stainless steel. In addition, 21 irradiation also causes embrittlement (IE) in these 22 components for fluences > 2.0 x 1020 n/cm2 (i.e., material 23 damage > 10 dpa), and irradiation makes CASS, its welds, Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 4
NYS000576 Submitted: September 23, 2015 1 and the welds of austenitic stainless steel also more 2 susceptible to irradiation-assisted stress corrosion 3 cracking (IASCC);
4 Significantly, IASCC increases the crack growth rate of 5 cracks induced by stress corrosion cracking. However, the 6 document also reports that there is virtually no data above 7 10 dpa -- even though during the period of extended 8 operation some of the reactor vessel internals may 9 experience several hundred dpa; 10 Transgranular brittle cleavage was observed for embrittled 11 materials (and in particular for the CASS tests reported in 12 the other USNRC document, NUREG/CR-7184 [NYS000574];
13 Possible synergy was noted between thermal embrittlement 14 and irradiation embrittlement, although the report stresses 15 the need for more information to develop reliable J-R 16 failure curves. The other USNRC document, NUREG/CR-7184, 17 also notes this same type of synergism.
18 Q. Do you believe that this report, NUREG/CR-7185, is 19 significant?
20 A. Yes, it is. As mentioned, this USNRC report supports 21 my opinions and testimony presented in this proceeding. In Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 5
NYS000576 Submitted: September 23, 2015 1 addition, this report, which was prepared by Argonne National 2 Laboratories and the USNRC Staff, contains information that 3 I have not seen in previous USNRC reports. In particular, the 4 susceptibility of stainless steel welds to TE and, for the first 5 time ever, the detrimental effect of this embrittlement on 6 impact strength (i.e., for withstanding significant shock loads) 7 and the potential for brittle fracture due to various impulsive 8 loads.
9 Q. Can you summarize the other USNRC document, NUREG/CR-10 7184, Exhibit NYS000574?
11 A. Yes. That document, "Crack Growth Rate and Fracture 12 Toughness Tests on Irradiated Cast Stainless Steels,"
13 [NYS000574], also contains analysis and conclusions that are 14 relevant to and supportive of the opinions and testimony that I 15 have presented. For example, as noted previously, the document 16 reports that for CASS materials, synergies exist between thermal 17 embrittlement (TE) and irradiation embrittlement (IE). Also, it 18 is significant that transgranular brittle cleavage was observed 19 for embrittled materials, as was ductile tearing (i.e.,
20 dimpling).
21 Q. In your opinion, what is the significance of that 22 information?
Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 6
NYS000576 Submitted: September 23, 2015 1 A. The observation of both of these failure mechanisms 2 and the synergies between the various aging-related degradation 3 mechanisms is supportive of my previous opinions and testimony.
4 That is, realistic safety and fatigue analyses need to take into 5 account the age-related degradation of materials. For example, 6 the finding in NUREG/CR-7185 that CASS and austenitic stainless 7 steel welds are subject to thermal embrittlement (TE), and that 8 this reduces their impact strength, means that the welds 9 associated with the pressurizer spray nozzle, for example, are 10 particularly vulnerable to significant seismic and 11 thermal/pressure shock loads. Moreover, it appears that 12 vulnerability to early failure of the various RVI welds, which 13 are subject to TE, IE, IASCC, and shock loads, have not been 14 adequately analyzed.
15 Q. I show you what previously was marked as NYS00488A-B 16 and ask you to compare it to NYS000575.
17 A. NYS00488A-B is entitled Crack Growth Rate and 18 Fracture Toughness Tests on Irradiated Cast Stainless Steels, 19 NUREG/CR-7184, ANL-12/56 and it appears that this document is a 20 revised manuscript and it bears a manuscript date of December 21 2014. I referred to that earlier manuscript in my previous 22 testimony [e.g., NYS000482], and the State previously presented 23 the document as Exhibit 488. It appears that Argonne National Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 7
NYS000576 Submitted: September 23, 2015 1 Laboratory and the USNRC have subsequently made some edits and 2 republished the document, which is now NYS000574.
3 Q. It that the end of your supplementary testimony today?
4 A. Yes it is. However, I reserve the right to supplement 5 my testimony if new information is disclosed or introduced.
6 Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 8
NYS000576 Submitted: September 23, 2015 1 UNITED STATES 2 NUCLEAR REGULATORY COMMISSION 3 BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 4 -----------------------------------x 5 In re: Docket Nos. 50-247-LR; 50-286-LR 6 License Renewal Application Submitted by ASLBP No. 07-858-03-LR-BD01 7 Entergy Nuclear Indian Point 2, LLC, DPR-26, DPR-64 8 Entergy Nuclear Indian Point 3, LLC, and 9 Entergy Nuclear Operations, Inc. September 23, 2015 10 -----------------------------------x 11 DECLARATION OF RICHARD T. LAHEY, JR.
12 I, Richard T. Lahey, Jr., do hereby declare under penalty 13 of perjury that my statements in the foregoing testimony and my 14 statement of professional qualifications are true and correct to 15 the best of my knowledge and belief.
16 Executed in Accord with 10 C.F.R. § 2.304(d) 17 18 _________________________
19 Dr. Richard T. Lahey, Jr.
20 The Edward E. Hood Professor Emeritus of Engineering 21 Rensselaer Polytechnic Institute, Troy, NY 12180 22 (518) 495-3884, laheyr@rpi.edu Pre-filed Supplemental Testimony of Richard T. Lahey, Jr.
Contentions NYS-25, NYS-26B/RK-TC-1B, NYS-38/RK-TC-5 9