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Category:Legal-Pre-Filed Exhibits
MONTHYEARML1025100362010-09-0808 September 2010
PIC000001-Christopher I. Grimes Resume
ML1025006142010-09-0707 September 2010
NRC000001-Boric Acid Corrosion Guidebook, Revision 1
ML1025006402010-09-0707 September 2010
NRC000030-Revised Policy Statement on the Conduct of Nuclear Power Plant Operations
ML1025006382010-09-0707 September 2010
NRC000025-Figures 2 Through Figure 6
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NRC000027-The Nature of Safety Cultua Review of Theory and Research
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NSP000061-SER Section 3.0.4
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NSP000050-Revised Prefiled Testimony of Northard/Petersen/Peterson-2009 Corrective Action Program Self-Assessment
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NSP000041-Revised Prefiled Testimony of Northard/Petersen/Peterson-Performance Recovery Plan
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NSP000069-NRC December 21, 2007 PI&R Report
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NSP000070-PINGP Pride Initiative Focus 2010
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NSP000035B-Revised Testimony of Northard/Petersen/Peterson-Root Cause Evaluation Report 01157726
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NSP000020-Revised Testimony of Northard/Petersen/Peterson-Petersen Resume
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NSP000035C-Revised Testimony of Northard/Petersen/Peterson-Root Cause Evaluation Report 01157726
ML1024606242010-09-0303 September 2010
NSP000019-Revised Testimony of Northard/Petersen/Peterson-Northard Resume
ML1024605692010-09-0303 September 2010
Applicant Revised Exhibit NSP000001-Revised Testimony of Steven Skoyen Resume
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NSP000017-Revised Testimony of Steven Skoyen-NUREG-1765 Excerpts
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Northern States Power Co. October 2010 Evidentiary Hearing on Safety Culture Contention, Hearing Exhibits
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NSP000015-Revised Testimony of Steven Skoyen-EFR 1160372-03
ML1024605522010-09-0303 September 2010
NSP000006-Revised Testimony of Steven Skoyen-2006 AES Letter
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NSP000010-Revised Testimony of Steven Skoyen-EFR 1160372-04
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NSP000008-Revised Testimony of Steven Skoyen-Dominion Evaluation R-4448-00-01
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NSP000012-Revised Testimony of Steven Skoyen-EC 15651
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2009/09/03-Applicant-Revised Exhibit NSP000003-PINGP License Renewal Application Excerpts
ML1024605572010-09-0303 September 2010
NSP000013-Revised Testimony of Steven Skoyen-ACRS Letter
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NSP000007-Revised Testimony of Steven Skoyen-CAP 1160372
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NSP000011-Revised Testimony of Steven Skoyen-EC 15044
ML1024605602010-09-0303 September 2010
NSP000016-Revised Testimony of Steven Skoyen-ACRS July 2009 Meeting Transcript Excerpts
ML1024605622010-09-0303 September 2010
Applicant Revised Exhibit NSP000004-Root Cause Evaluation Report 01160372-01
ML1024605632010-09-0303 September 2010
NSP000018-Revised Testimony of Steven Skoyen-CE 01140617-03
ML1024605642010-09-0303 September 2010
NSP000009-Revised Testimony of Steven Skoyen-CE 1233806-2
ML1024605652010-09-0303 September 2010
Applicant Revised Exhibit NSP000002-Schematic Representation of PINGP Containment
ML1022504662010-08-13013 August 2010
NRC Staff Exhibit 63 - Boric Acid Corrosion Guidebook, Revision 1: Managing Boric Acid Corrosion Issues at PWR Power Stations EPRI, Palo Alto, CA (2001) 1000975 Pages 4-25 & 4-26
ML1022504702010-08-13013 August 2010
2010/08/13-NRC Staff Exhibit 4A - NUREG-1800 Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) (September 2005), (Excerpt)
ML1022504772010-08-13013 August 2010
NRC Staff Exhibit List
ML1022504962010-08-13013 August 2010
Northard Exhibit 43, Section 3.0.4. of NRC SER
ML1022504982010-08-13013 August 2010
Northard Exhibit 48, WM-0491 - Prairie Island Corrective Backlog
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Skoyen Exhibit 17, NUREG-1765 Excerpt
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Northard Exhibit 52, Pride Initiative Focus/2010
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Skoyen Exhibit 18, CE01140617-03 Potential IWE Non-Compliance
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Northard Exhibit 42, Event Cross References in 2009
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Skoyen Rebuttal Exhibits List
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List of Northard Rebuttal Exhibits
ML1024607592010-08-0606 August 2010
NSP000066-PINGP Corrective Backlog 2010
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NRC Staff Exhibit 62 - Summary of July 28, 2010 Public Meeting to Discuss Observations and Lessons Learned During the Pilot Application of the Nuclear Energy Institutes Nuclear Safety Culture Assessment Process (August 4, 2010)
ML1021607812010-08-0404 August 2010
Intervenor-Exhibit 21-Xcel Management Review Committee Meeting Summary No. 2010-01, Msrc Meeting Date March 17 and 18, 2010 (NSPM Prod 00000267)
ML1021607642010-08-0404 August 2010
Intervenor-Exhibit 1-Resume for Christopher I. Grimes
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NRC000058-Summary of July 28, 2010 Public Meeting to Discuss Observations and Lessons Learned During the Pilot Application of the Nuclear Energy Institute'S Nuclear Safety Culture Assessment Process (August 4, 2010)
ML1021503902010-07-30030 July 2010
Applicant-Northard Exhibit 4-INPO V NRC Nuclear Safety Culture Components
ML1021503922010-07-30030 July 2010
Applicant-Northard Exhibit 5 - Nuclear 2010 Business Plan Overview
ML1021503932010-07-30030 July 2010
Applicant-Northard Exhibit 10-FP-PA-HU-03, Rev. 6, Human Performance Observation Program.
2010-09-08
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 Docket Nos. 50-282-LR and 50-306-LR NRC STAFF EXHIBIT 63 Boric Acid Corrosion Guidebook, Revision 1: Managing Boric Acid Corrosion Issues at PWR Power Stations, EPRI, Palo Alto, CA (2001) 1000975 Pages 4-25 & 4-26
Boric Acid Corrosion Guidebook, Revision 1 Managing Boric Acid Corrosion Issues at PWR Power Stations Effective December 6. 2006. this report has been made publicly available in accordance with Section 734.3(b)(3) and published in accordance with Section 734.7 the U.S. Export Administration Regulations. As a result of this publication, this is subject to only copyright protection and does not require any license WARNING: from EPRI. This notice supersedes the export control restrictions and any Please read the License Agreement proprietary licensed material notices embedded in the document prior to publication.
on the back cover before removing the Wrapping Material.
Technical Report
EPRI Licensed Material Boric Acid Corrosion Tests Test Ref.: A Test Type: Immersion Aerated and Deaerated Boric Acid Org/Date: Westinghouse (1967)
References:
"Materials Behavior Related Issues for Bolting Applications in the Nuclear Industry." Conference: Improved Technology for Critical Bolting Applications, Chicago, Ill., July 20-24, 1986. MPC-Vol. 26 [22].
Absorption o/Corrosion Hydrogen by 302B Steel at 70F to 500F.
Westinghouse Electric Corporation, 1967, WCAP-7099 [23].
Test Configuration, Procedure, and Results Westinghouse conducted a series of tests on electrically isolated coupons of A-302 Grade B low-alloy steel in both aerated and deaerated environments. Some experiments involved cases where the low-alloy steel test coupons were coupled to 304 stainless steel. Tests were conducted at 2500 ppm boron at several different temperatures.
Table 4-3 gives the average corrosion rate for long periods of time (40-160 days) for each of the test conditions. The test results plotted in Figure 4-8 show the effect of test duration.
Table 4-3 Average Corrosion Rates in Aerated and Oeaerated Water - Westinghouse Tests Temperature in Corrosion Rate Oeaerated in Corrosion Rate Aerated in OF eC) IncheslYear (mm/yr) IncheslYear (mm/yr)
Isolated Coupled to 304 Isolated Coupled to 304 70 (21) 0.0002 (0.005) --- 0.002 (0.05) 0.002 (0.05) 100 (38) 0.00005 (0.0013) 0.00005 (0.0013) 0.007 (0.18) 0.007 (0.18) 140 (60) 0.00007 (0.0018) 0.00011 (0.0028) 0.015 (0.38) 0.015 (0.38) 500* (260) --- --- 0.24 (6.1) --
- Provided at meeting with Westinghouse.
Key observations from these tests are:
- In deaerated water at temperatures less than 140°F (60°C), the corrosion rates are very low.
- In aerated water, the corrosion rates increase with temperature from 70°F to 140°F (21°C to 60°C) with the long-term corrosion rate at 140°F (60°C) being about 0.0 IS in/yr (0.38 mrnlyr).
- The galvanic couple between low-alloy steel and stainless steel has little effect on the corrosion rates of low-alloy steel in borated water.
4-25
EPRI Licensed Material Boric Acid Corrosion Tests
- Initial corrosion rates can be much higher than long-term corrosion rates.
- The corrosion rate in aerated borated water at 500 0 P (260°C) is 0.24 inlyr (6.1 mrnlyr).
Conclusions Corrosion rates in low-temperature de aerated water are very low. Corrosion rates in aerated water at temperatures less than 140 0 P (60°C) are acceptably low to not pose a serious problem with leakage of borated water.
18000 200 o A302B Isolated Coupons ACO A3028 Isolated Coupons 16000
- A302B Coupled to 30488 180 .... A3028 Coupled to 30488 14000 160 12000 140 N
E E
~ ~
E 10000 E 120 c:- c'
.g
.2 i\\
g'"
CI) g 8000 100
!.~
,r;)
U° U° 1-6000 80 4000 60 21 'C ~ 4.77 X 10" mm/yr (70'F ~ 0.002 In/yr)
~~~::~::~~::==(=70='~F~~~0.:00~2~ln=/y~r)~~
2000 40 A o~~~=
o~
o 20 40 60 80 100 120 140 160 O~--~~~--~--~--~--~
o 20 40 60 80 100 120
__ ~~
140 160 Test Time, Days Test Time. Days Corrosion as measured in wei~ht loss Corrosion as A3028 in deaerated of A302B in air-saturated bOriC acid boric acid solution containing solution containing 2500 ppm boron 2500 ppm boron Figure 4-8 Corrosion Rate in Aerated and Deaerated Water - Westinghouse Tests [22) 4-26
