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Category:Memoranda
MONTHYEARML23129A6062023-05-0404 May 2023 Special Inspection Team Charters to Evaluate the Circumstances Surrounding the Ground Settling at the Davis-Besse Nuclear Power Station ML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III ML21096A2282021-03-30030 March 2021 FEMA Disapproval of Davis-Besse Exercise Exemption ML19182A3562019-07-23023 July 2019 Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019 ML19162A0102019-06-0707 June 2019 Memorandum to File Environmental Assessment and Finding of No Significant Impact for Firstenergy Nuclear Operating Company'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(B) and 72.30(C) for Davis Besse ISFSI ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML15205A1692015-08-0707 August 2015 ACRS Review of the Davis Besse Nuclear Plant LRA - Transmittal of the Sser ML15182A1912015-07-16016 July 2015 Annual Financial Test for a Parent Company Guarantee Given by Firstenergy Solutions Corporation and Firstenergy Corporation ML15089A1642015-04-27027 April 2015 Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis IR 05000334/20004122014-07-0808 July 2014 NRC Staff'S Spot-Check Review of First Energy Nuclear Operating Company'S Ownership Interest in Beaver Valley, Units 1 and 2, Perry, and Davis-Besse, Docket No. 05000334, 05000412, 05000440, and 05000346, on June 10, 2014-Finding of No Pote ML14099A4642014-05-0606 May 2014 Summary of Public Meetings to Discuss Draft Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Davis-Besse Nuclear Generating Station, Unit 1 ML13280A9062013-10-21021 October 2013 Forthcoming Meeting with Firstenergy Nuclear Operating Company (FENOC) to Discuss Voluntary Risk Informed Fire Protection Amendment for Davis-Besse ML13142A5122013-07-0202 July 2013 Summary of Telephone Conference Call Held on May 21, 2013, Between NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station, LRA ML13171A2922013-06-13013 June 2013 LTR-13-0540 - Bill Hawkins and Vinod Arora Email San Onofre Nuclear Generating Station (SONGS) Lessons Learn for Davis-Besse ML13154A4442013-06-0404 June 2013 Rai'S Following Ifib Analysis of Fenoc'S 2013 Decommissioning Funding Status Report for Davis-Besse and Perry ML12199A2072012-07-17017 July 2012 Public Meeting Notice to Discuss the 2011 End-of-Cycle Performance Assessment ML12158A4002012-06-0808 June 2012 6/26/2012 Forthcoming Meeting Firstenergy Nuclear Operating Company (FENOC) ML1206901652012-03-0909 March 2012 Memo - Summary of Public Meeting with Industry Regarding Pwrog'S Boric Acid Corrosion Test Program ML12018A1652012-01-27027 January 2012 Summary of Telephone Conference Call Held on November 9, 2011, Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, LRA ML14028A5462012-01-25025 January 2012 NRC Telecon Regarding Davis-Besse License Renewal Severe Accident Mitigation Alternatives Analysis Questions ML11363A1712012-01-23023 January 2012 Summary of Telephone Conference Call Held on December 12, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Request for Additional Information ML11355A0952011-12-29029 December 2011 Summary of Telephone Conference Call Held on December 8, 2011, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning RAIs Pertaining to the Davis-Besse Nuclear Power Station, LRA ML11348A0212011-12-21021 December 2011 Summary of Telephone Conference Call Held on November 1, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis Besse Nuclear Pow ML11341A1182011-12-14014 December 2011 Summary of Telephone Conference Call Held on June 15, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power ML11339A0862011-12-13013 December 2011 Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning RAIs Pertaining to the Davis-Besse Nuclear Power Station LRA ML11327A0082011-12-0202 December 2011 Summary of Telephone Conference Call Held on September 29, 2011, Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, LRA ML11327A0792011-12-0202 December 2011 Summary of Telephone Conference Call Held on Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis Besse Nuclear Power Station ML11327A0872011-12-0202 December 2011 Summary of Telephone Conference Call Held on July 27, 2011, Between the NRC and Firstenergy Nuclear Operating Company Concerning RAI Pertaining to the Davis-Besse, LRA ML11279A2182011-10-0606 October 2011 Memo - Task Interface Agreement - Evaluation of Compliance with Code for Examination of Flange Stud Holes on the Replacement Vessel Head at the Davis-Besse Nuclear Power Station (TIA 2011-015) ML11242A0032011-09-12012 September 2011 Summary of Conference Call Held on August 4, 2011, Between the NRC and FENOC Concerning Requests for Additional Information Pertaining to the Davis-Besse License Renewal Application ML1122701392011-08-15015 August 2011 Request for Additional Information Response Clarification from Davis-Besse Nuclear Power Station in Support of License Renewal Application Review ML11173A2002011-08-0101 August 2011 Summary of Public Scoping Meetingsconducted Related to the Review of the Davis-Besse Nuclear Power Station, Unit 1, LRA ML11193A2032011-07-26026 July 2011 Final Response to TIA 2011-001, Davis-Besse Nuclear Power Station Safety-Related Batteries Electrical Separation Design and Licensing Bases ML11174A2322011-06-21021 June 2011 for the Record-06-21-2011: NRC Ensures Public Safety Through Rigorous Oversight of Nuclear Power Plant Safety Standards ML1108202762011-06-0303 June 2011 Summary of Site Audit Related to the Review of the License Renewal Application for Davis-Besse Nuclear Power Station, Unit 1 ML11174A2472011-05-31031 May 2011 for the Record-05-31-2011: NRC Chairman Gregory B. Jaczko'S Statement on Nrc'S Commitment to Safety ML1110806902011-04-20020 April 2011 Notice of Meeting with First Energy Nuclear Operating Company (FENOC) to Discuss a Proposed LAR to Delete Technical Specification 5.5.8g, Steam Generator (SG) Program Auxiliary Feedwater Header Inspections ML1028702612010-10-22022 October 2010 11/04/10 Notice of Meeting to Discuss the License Renewal Process and Environmental Scoping for Davis-Besse Nuclear Power Station License Renewal Application Review ML1029106182010-10-14014 October 2010 Documentation of Telephone Conversation Between Mr. David Lochbaum Regarding Follow-Up Questions Related to NRC Letter Dated July 28, 2010 (ML102040807) ML1028503032010-10-12012 October 2010 Acceptance of License Renewal Application, Davis-Besse Nuclear Power Station ML0935101922009-12-14014 December 2009 Completion of Davis-Besse Lessons Learned Task Force Recommendation 3.3.4(8) ML0825606772008-09-15015 September 2008 Presentation Disc ML0814207532008-05-20020 May 2008 Summary of Public Meeting with Firstenergy Nuclear Operating Company to Discuss the 2008 Davis-Besse End-of-Cycle Performance Assessment ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0723302222007-08-28028 August 2007 09/12/2007 Notice of Meeting with Firstenergy to Discuss the August 3, 2007 License Amendment Request for Conversion to Improved Technical Specifications for Davis-Besse, Unit 1 ML0722108432007-08-0707 August 2007 Request for Renewal of Deviation to the Reactor Oversight Process Action Matrix for Davis-Besse Nuclear Power Station ML0717103462007-06-21021 June 2007 Revised Notice of Meeting with Firstenergy to Discuss Response to Nrc'S 05/14/2007, Demand for Information Regarding Fenoc'S Re-analysis of the Timeline and Root Causes for the 2002 Davis-Besse Reactor Pressure Vessel Head Degradation Event ML0716202122007-06-13013 June 2007 Notice of Meeting with Firstenergy Regarding May 14, 2007 Demand for Information Davis-Besse ML0712803322007-05-18018 May 2007 April 2007 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations (10 Cfr), Section 2.206 2023-05-04
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MEMO DATE: 4 October 2002 TO: M.T.Kirk FROM: P. T. Williams and B. R. Bass
SUBJECT:
Status Report on Davis-Besse Analyses The attached Figs. 1-6 provide a summary of the Davis-Besse analyses performed to date under the new Task 9 of JCN Y6533. In Fig. 1, the cladding properties used in the current study are presented:
(a) true stress versus true strain and (b) thermal expansion coefficient versus temperature. The remaining figures address a specific sub-task described in the workscope for Task 9.
Sub-task 9.1D requires an estimate for crack driving forces as a function of flaw size and applied membrane stress in cladding.
Figure 2 depicts the first step carried out in preparation for the J-integral analyses, i.e., calculation of an updated estimate of the exposed cladding "footprint" based on the recent "dental mold" cast from the D-B cavity. That footprint area was estimated to be 28.23 in2 . Comparisons of the latest "footprint" statistics with previous ORNL interpretations are given in the table of Fig. 2(b).
The newly calculated "footprint" area was used to define a burst disk having the same cross-sectional area.
Table I presents ductile tearing data for three-wire series-arc stainless steel weld overlay cladding published in NUREG/CR-5511 [1]. The ductile-tearing data presented in Table I are plotted as a function of temperature in Fig. 3.
Figure 4 presents the three finite-element models developed for this phase of the analysis. For a constant flaw length, surface breaking flaws were centrally located in each burst disk. The three relative flaw depths investigated were 0.5, 0.25, and 0.05. The constant total flaw length was 2.0 inches (50.8 mm).
Each of the three models were loaded with an increasing lateral pressure until the solution approached a numerical breakdown. The resulting J-integral loading paths for the three models are shown in Fig. 5. Figure 5 also presents a value of J1, for a temperature of 318.3 'C (605 'F) estimated by extrapolating from the data in Fig. 3a using a 4th order polynomial curve-fit.
Figure 6 compares the critical pressures (determined from the results shown in Fig. 5) for two potential failure modes of the burst-disk models. The ductile-tearing critical pressure is calculated from the point at which the load path for each flaw crosses the J1, line in Fig. 5. The plastic-collapse critical pressure was estimated from the load at which each model began to approach a numerical instability in the analysis. From the curves in Fig. 6, the controlling failure mode for the two larger flaws in the current study was ductile tearing. The shallow flaw (aft = 0.05) was close to the J1, line when it began to fail by plastic collapse. An estimate of the applied tearing modulus was calculated using the data from the three flaws at a pressure of 6.4 MPa (0.928 ksi).
As indicated by the comparison in Fig. 3b, this estimate of the applied tearing modulus indicates a stable ductile tearing for the largest flaw, thus implying stable tearing for the smaller flaws as well. C 1
References
[1] F.M. Haggag, W. R. Corwin, and R. K. Nanstad, IrradiationEffects on Strength and Toughness of Three-Wire Series-Arc Stainless Steel Weld Overlay Cladding, NUREGICR-55 11 (ORNL/TM-1 1439), Oak Ridge National Laboratory, February 1990.
2
Table 1. Ductile Tearing Data Extracted from Table 13 of NUREG/CR-5511.
Tests.-.
CA . s Terin UnirradiatedSpecimens A13G -75 117 64 H2 -75 137 49 Al1Ba 20 165 270 A13D 20 134 209 AlOG 20 171 176 AlOE 120 128 246 H5 120 119 229 H3 120 120 232 A13Fa 120 159 359 H6 200 90 240 H4 200 111 231 A15D 288 77 267 A13C 288 66 170 H1 288 82 192 Irradiated Specimens A15F -75 78 40 A15G -75 56 36 A13A 30 144 177 A15C 50 124 146 AlOF 120 94 175 Al5A 288 25 191 aSpecimen was not side-grooved, while all other specimens in table were side-grooved 20%.
3
80 70 l '500 7n 70 G=94.36£ (ksi) 2000 IL 20 'i E = 25570.85 ksil 1100 0 io0 0 0.05 0.1 0.15 0.2 00 (a) Total Strain (- 09'2712002.K3 ptw 1.5 104 r- --- ;_ ------ ~ ~-- -----
L 1.4 105~-
u 1.314 1.1 i ii 0 500 1000 1500 2000 2500 3000 0912712002 K2 ptw (b) Temperature (0F)
Fig. 1. Cladding properties used in the current study: (a) true stress vs true strain and (b) thermal expansion coefficient.
4
I 3
II "Footprint 9/2312002 1 Area = 28.23 in.2 /
R31 .712 (a)
.... t ,.,$.,.-.. l = T a w I Sowing FM" I 7I t I -
IdM HI
'Y.
IPIMXVWElhudaxa I. , -r " ,
't , 4 -,, 1
- 4I
,,-,: f~ -sr l~w7 i')><*<m C- -If It 1-1) >b r.I , e <^:.- '> n. n1 ->f Ai-FomdFoolmm 1 3536 3036 164122 -01194 9889 9699.33 -11716 75.26 19741 <09004..04351> <04351,09004>
Adj.sIed Foolpnnt 0.25In 40 06 31 78 16.4301 4..1255 12902 11031.S1-14135 99 00 245 71 <0.8943-04476> <04476,08943>
for Boundmig "ocpon A.-Found Foopuns 1 28 23 24.55 IS 332 40189 95.56 670863 -50 52 54 01 11307 IO.SSS 0.8301 1408300 SSSI 912Vo2 .1 Foolpnnt centroid is in glbbl coordinales Gbbal coordmnawe ristem has .-s alizgned h thefneeca] c-meee of rhe seosel The -y plane of the global coordinte sysiem is a hMIzontal plae (b) wth te xn-ss along She hoe between theceotsnocs of Nozzles 3 and II Fig. 2. Latest footprint estimated from "dental mold".
5
Temperature (°F) 0 200 400 600 180 -- ______,,___.__.__ ____._...____,_...._. ..... __. ------- - --'-T ------- ----
10 0.96 Data from Table 13 160 -- (unirradiated) IN NUREG/CR-5511 I-0.88 C I(_
Nm i en E 140 - -' 0.8 .2 0
0 x
I',
.9 - 0.72 r-120 - 0 a
0.6 ii-1 0.64 _>1 100 -
, 0.48 80 -
-1 0.4 60 ----
-100 0 100 200 300 400 10/0412002 K2 pt'w (a) Temperature (°C)
Temperature (°F) 0 200 400 600 400
. Data from Table 13 350 - (unirradiated)
NUREG/CR-551 1 (n 300 L 0
250 -
0)
- /
.j_
150 , / Applied Tearing Modulus at 6.4 MPa (0.928 ksi) 100 2L = 50.8 mm (2.0 inches) -
t = 6.35 mm (0.25 inches) 50 H o0
-100 0 100 200 300 400 10/0412002.K3 ptw (b) Temperature (°C)
Fig. 3. Ductile tearing data for three-wire series stainless steel weld overlay cladding from Table 13 of NUREG/CR-5511: (a) J1, data from unirradiated specimens and (b) tearing modulus data from unirradiated specimens 6
Fixed-Grip Boundary on Outer Edge
-3 175 .. (U 125.) 2LI -16
L 254 .m (10 In.)
11- 76 IhXI .m (2 9g76 In)
An-. - 18226.4 mm 2.23X"bW)
(a) ' irv,-
Fixed-Grip Boundary on Outer Edge
~~~~~
1 . 1 052.2 502 E 2U.s- 32 IM75 mm (0 0625 Ii).
z x\Ma*t6.34 "n, tu 2CIn)
If -701615mm (2L.961n A(b - IU224 mm! (282124In ')
Fixed-Grip Boundary on Outer Edge pL.- 16202 0.10llS, lt mm(02125 A. _2,22i.4 ._ (22H-7h I1.)
5zA_ A l22&4mn'12.25 1.)
__W Fig. 4. Finite-element models used in calculating applied J-integrals produced by pressure loading of burst disk: (a) Model 1 (alt = 0.5, 2L/a = 16) (b) Model 2 (alt = 0.25, 2LIa =
32), and (c) Model 3 (a/t = 0.05, 2Lla = 160) (Task 9.1D) 7
Pressure (ksi) 0 1 2 3 4 5 6 7 8 600 F 3.2 500 2.8 N
N 2.4 -
E 400 2 I on 300 1.6 X
'a c-1.2 C 200 0.8 100 0.4 0 0 0 10 20 30 40 50 60 10/0412002.K1 ptw Pressure (MPa)
Fig. 5. J-integral driving forces from three finite-element models as a function of applied pressure.
8
60 I i i 2L = 50.8 mm (2.0 inches) t = 6.35 mm (0.25 inches) -
8 50 H I_,
7 ^
0
.b_
0
- v. Plastic Collapse 6 C 401-
'I 0 0 (a
a.
0~ 5 0e-AL 30 I- ,.
a., 4 Ii ra-U 20 Set-point pressure T.aOperatrnipressure J 3 U 10 1 -- _-.
Ductile Tearing
- i 2 1
0 0 0 0.1 0.2 0.3 0.4 0.5 0.6 alt 1AI/I'l2nnA2 VA nthA Fig. 6. Comparison of critical pressures for two failure modes as a function of relative flaw depth. The same flaw length (50.8 mm) is used for all current analyses.
9