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Category:Legal-Exhibit
MONTHYEARML15337A3522015-11-17017 November 2015 Official Exhibit - NYS000582-00-BD01 - Diagram of Strength Vs Amplitude by Dr. Richard T. Lahey ML15337A3372015-11-11011 November 2015 Official Exhibit - ENTR00726-00-BD01 - Track 2 Hearing Exhibit List ML15337A3322015-11-0505 November 2015 Official Exhibit - ENT000726-00-BD01 - Entergy Track 2 Hearing Exhibit List ML15337A3352015-11-0505 November 2015 Official Exhibit - RIVR14001-00-BD01 - Riverkeeper Tailored Track 2 Exhibit List ML15337A3362015-11-0505 November 2015 Official Exhibit - NRCR10001-00-BD01 - NRC Staff Track 2 Exhibit List ML15337A3332015-11-0404 November 2015 Official Exhibit - NYSR25001-00-BD01 - NYS Revised Tailored Exhibits List Relevant to Track 2 Contentions ML15337A3312015-11-0303 November 2015 Official Exhibit - NRC000230-00-BD01 - Corrections to Prefiled Testimony NRC000168 and NRC000197 ML15337A3262015-10-29029 October 2015 Official Exhibit - ENT000722-00-BD01 - Supplemental Testimony of Entergy Witnesses Nelson Azevedo, Timothy Griesbach & Randy Lott ML15337A3292015-10-29029 October 2015 Official Exhibit - ENTR16001-00-BD01 - Entergy Revised Exhibit List ML15337A3242015-09-23023 September 2015 Official Exhibit - NYS000576-00-BD01 - Pre-Filed Supplemental Testimony of Richard T. Lahey Re Contentions NYS-25, NYS-26B/RK-TC-1B & NYS-38/RK-TC-5 ML15337A3072015-09-0909 September 2015 Official Exhibit - NYS000573-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2962015-09-0909 September 2015 Official Exhibit - NYS000570-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2832015-09-0909 September 2015 Official Exhibit - NYS000563-00-BD01 - Pressurized Water Reactor (PWR) Systems, USNRC Technical Training Center, Reactor Concepts Manual, Pages 4-1 to 4-28 ML15337A2952015-09-0909 September 2015 Official Exhibit - NYS000569-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2942015-09-0909 September 2015 Official Exhibit - NYS000568-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A2932015-09-0909 September 2015 Official Exhibit - NYS000567-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A3042015-09-0909 September 2015 Official Exhibit - NYS000571-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of David J. Duquette in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2972015-09-0909 September 2015 Official Exhibit - RIV000164-00-BD01 - NUREG-1740, ACRS, Voltage-Based Alternative Repair Criteria: a Report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion (2001) ML15337A3062015-09-0909 September 2015 Official Exhibit - NYS000572-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2822015-09-0909 September 2015 Official Exhibit - NYS000566-00-BD01 - Figure 1 for Supplemental Reply Testimony of Dr. Richard T. Lahey ML15337A3142015-09-0404 September 2015 Official Exhibit - ENTR00615-PUB-00-BD01 - Entergy'S Statement of Position Re Contention NYS-25 (Embrittlement) - Redacted ML15334A2842015-08-10010 August 2015 Official Exhibit - ENT000687-00-BD01 - NRC, Safety Evaluation Report, Topical Report on ASME Section III Piping and Component Fatigue Analysis Utilizing the Westems Computer Code (WCAP-17577, Revision 2) (Undated) ML15335A2932015-08-10010 August 2015 Official Exhibit - NRCR00104-00-BD01 - on Yee Statement of Professional Qualifications (Revised) ML15337A2642015-08-10010 August 2015 Official Exhibit - NRC000196-PUB-00-BD01 - NRC Staff'S Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) ML15337A3192015-08-10010 August 2015 Official Exhibit - ENT000698-PUB-00-BD01 - Entergy'S Revised Statement of Position Regarding Contention NYS-38/RK-TC-5(Safety Commitments) (Aug. 10, 2015)Redacted ML15337A3202015-08-10010 August 2015 Official Exhibit - ENT000699-PUB-00-BD01 - Redacted Revised Testimony of Entergy Witnesses Nelson Azevedo, Robert Dolansky, Alan Cox, Jack Strosnider, Timothy Griesbach, Barry Gordon, Randy Lott, and Mark Gray Regarding Contention NYS-38/RK ML15337A3172015-08-10010 August 2015 Official Exhibit - ENT000678-PUB-00-BD01 - NL-07-140, Letter from F. Dacimo, Entergy, to NRC Document Control Desk, ?Reply to Request for Additional Information Regarding License Renewal Application? (Nov. 28, 2007)Redacted ML15337A2652015-08-10010 August 2015 Official Exhibit - NRC000197-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 ML15337A2412015-08-10010 August 2015 Official Exhibit - NRCR00147-00-BD01 - NRC Staff'S Revised Statement of Position on State of New York and Riverkeeper'S Joint Contention NYS-38/RK-TC5 (Revised) ML15335A2902015-08-10010 August 2015 Official Exhibit - NRC000222-00-BD01 - IP3 FSAR Rev. 04 Chapter 3 (2011) (Excerpt) ML15334A2632015-08-10010 August 2015 Official Exhibit - ENT000648-00-BD01 - M. Mitchell, Chief, Vessels and Internals Integrity Branch, Response to Non-Concurrence Regarding Safety Evaluation for Topical Report MRP-227 Pressurized Water Reactor Internals Inspection and Evaluat ML15337A2622015-08-10010 August 2015 Official Exhibit - NRC000228-00-BD01 - Indian Point Unit 2 Technical Specifications 3.1.4 ML15337A2452015-08-10010 August 2015 Official Exhibit - NRC000227-00-BD01 - Gary Stevens Statement of Professional Qualifications ML15337A2632015-08-10010 August 2015 Official Exhibit - NRC000229-00-BD01 - Indian Point, Unit 3 Technical Specifications 3.1.4 ML15335A2192015-08-10010 August 2015 Official Exhibit - ENTR00031-00-BD01 - Curriculum Vitae of Alan B. Cox ML15335A2112015-08-10010 August 2015 Official Exhibit - ENTR20186-00-BD01 - Curriculum Vitae of Mark A. Gray ML15337A3162015-08-10010 August 2015 Official Exhibit - ENT000616-PUB-00-BD01 - Testimony of Entergy Witnesses Nelson F. Azevedo, Robert J. Dolansky, Alan B. Cox, Jack R. Strosnider, Timothy J. Griesbach, Randy G. Lott, and Mark A. Gray Regarding Contention NYS-25 (Embrittleme ML15337A2782015-08-10010 August 2015 Official Exhibit - NRC000168-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Dr. Ching Ng, Mr. Gary Stevens, P.E., and Mr. on Yee, Concerning Contentions NYS-26B/RK-TC-1B and NYS-38/RK-TC-5 ML15337A2712015-08-10010 August 2015 Official Exhibit - NRC000223-00-BD01 - IP3 FSAR Rev. 04 Chapter 14 (2011) ML15337A2592015-08-10010 August 2015 Official Exhibit - NRC000224-00-BD01 - IP3 FSAR Rev. 04 Chapter 16 ML15337A2442015-08-10010 August 2015 Official Exhibit - NRCR00161-00-BD01 - NRC Staff Testimony of Dr. Allen L. Hiser and Mr. Kenneth J. Karwoski Concerning Portions of State of New York and Riverkeeper, Inc. Joint Contention NYS-38/RK-TC5 (Revised) ML15334A2822015-08-10010 August 2015 Official Exhibit - ENT000680-00-BD01 - Curriculum Vitae of Barry M. Gordon ML15335A2912015-08-10010 August 2015 Official Exhibit - NRCR00118-00-BD01 - Indian Point Unit 3 Technical Specifications (Excerpt) (Revised) ML15334A2282015-08-10010 August 2015 Official Exhibit - ENT000634-00-BD01 - Entergy, IP2, FSAR Update, Revision 25 (2014) (Excerpts) ML15335A2822015-08-10010 August 2015 Official Exhibit - NRC000220-00-BD01 - Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update, (June 2014) ML15337A2692015-08-10010 August 2015 Official Exhibit - NRC000169-00-BD01 - NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt) ML15337A2602015-08-10010 August 2015 Official Exhibit - NRC000226-00-BD01 - Jeffrey C. Poehler Statement of Professional Qualifications ML15335A2732015-08-10010 August 2015 Official Exhibit - NRC000183-00-BD01 - NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) ML15335A2202015-08-10010 August 2015 Official Exhibit - ENTR00184-00-BD01 - Curriculum Vitae of Jack R. Strosnider ML15335A3012015-08-10010 August 2015 Official Exhibit - NRC000206-00-BD01 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 14 - Safety Analysis (2014) 2015-09-09
[Table view] |
United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of
- Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)
ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #:
Identified:
Admitted: Withdrawn:
Rejected: Stricken: Other: NYS000329-00-BD01
10/15/2012
10/15/2012 NYS000329 Submitted: December 22, 2011 c.,-VR REGU<..tr < 0 .. i ....
- " UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
OFFICE OF NEW REACTORS WASHINGTON, DC 20555-0001 June 29, 2011 NRC INFORMATION
NOTICE 2011-13: CONTROL ROD BLADE CRACKING RESULTING
IN REDUCED DESIGN LIFETIME
ADDRESSEES
All holders of an operating
license or construction
permit for a nuclear power pressurized-water
reactor or boiling-water
reactor (BWR) issued under Title 10 of the Code of Federal Regulations
(10 CFR) Part 50, "Domestic
Licensing
of Production
and Utilization
Facilities," except those who have permanently
ceased operations
and have certified
that fuel has been permanently
removed from the reactor vessel. All holders of and applicants
for a power reactor combined license, standard design certification, standard design approval under 10 CFR Part 52, "Licenses, Certifications, and Approvals
for Nuclear Power Plants."
PURPOSE
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice (IN) to inform addressees
that GE Hitachi Nuclear Energy (GEH) has discovered
severe cracking in Marathon control rod blades (CRBs) near the end of their nuclear lifetime limits in an international
BWR/6. As a result of investigations
into the cracking, GEH has determined
that the design life of certain Marathon CRBs may be less than previously
stated and is revising the end-of-life
depletion
limits of these CRBs. The NRC expects that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
Suggestions
contained
in this IN are not NRC requirements;
therefore, no specific action or written response is required.
DESCRIPTION
OF CIRCUMSTANCES
In August 2010, GEH, as part of its surveillance
program to monitor Marathon CRB performance, visually inspected
four discharged
CRBs at an international
BWR/6 and found cracks on all four CRBs. The cracks were much more numerous and had more material distortion
than those observed in previous inspections
of Marathon CRBs. The cracks were also more severe in that they resulted in missing boron-carbide
capsule tube fragments
from two of the inspected
CRBs. (A lost parts analysis determined
that the missing fragments
caused no negative effect on plant performance.)
Additionally, these cracks occurred at locations
of lower reported local boron-10 depletion
than previously
documented.
GEH attributed
the cracking to irradiation-assisted
stress-corrosion
cracking that results when a material that is susceptible
to irradiation
is in an aggressive
environment
from oxidizing
BWR ML 111380019 OAGI0001190_00001 water and experiences
excessive
stress because of boron-carbide
swelling.
GEH determined
that a significant
contributor
to the extensive
cracking was a rapid thermal transient
that occurred when the automatic
depressurization
system actuated and injected cold water. GEH does not anticipate
the same severe extent of Marathon CRB cracking in other plants unless a similar or more extreme thermal transient
should occur. GEH further concluded
that the cracking phenomenon
is confined to D-Iattice
and S-Iattice
BWR plants; no inspections
to date have identified
cracks on C-Iattice
Marathon CRBs. GEH attributed
this to a difference
in the C-Iattice
design that better accommodates
boron-carbide
swelling.
Based on the results of the investigation, GEH determined
that the lifetimes
of Marathon CRBs in D-Iattice
and S-Iattice
plants may be less than previously
stated. Therefore, GEH recommended
a lifetime reduction.
The recommended
Marathon CRB lifetime reduction
imposes a 60-percent
local boron-10 depletion
lifetime limit, or 54-percent
for D-Iattice "V4 segment and 55-percent
for S-Iattice "V4 segment lifetime limit. GEH recommends
that all plants containing
D-Iattice
and S-Iattice
Marathon CRBs remove the blades from service before they exceed the revised lifetime limits. For any Marathon CRB that exceeds the revised lifetime limit while in use, GEH advises that reactor operation
can continue, but the licensee should monitor reactor coolant boron and tritium concentrations
in accordance
with normal plant procedures.
If no significant
increase is observed in these concentrations, GEH recommends
that reactor operation
can continue until the end of the cycle before removing the CRBs from service. GEH recommends
that licensees
contact GEH if they detect a significant
increase in boron or tritium concentration
or both. The U.S. plants that may contain D-Iattice
and S-Iattice
Marathon CRBs and that; therefore, are potentially
affected are Browns Ferry-1, -2 and -3, Cooper, Clinton, Dresden-2 and -3, Duane Arnold, Grand Gulf, Fitzpatrick, Hatch-1 and -2, Monticello, Nine Mile Point-1, Oyster Creek, Peach Bottom-2 and -3, Perry, Pilgrim, River Bend, Quad Cities-1 and -2, and Vermont Yankee.
DISCUSSION
GEH's Marathon CRBs consist of a series of absorber tubes, each containing
capsules filled with boron carbide (a neutron absorber), welded together to form the control rod blades. Absorber tube cracks allow water to enter both the outer absorber tube and the boron-carbide
capsules, whereupon
boron carbide may leach into the reactor coolant, which could result in reduced control rod worth. Licensees
must maintain control rods in an operable condition
as required by plant technical
specifications.
Technical
specification
requirements
for reactivity
anomalies
give a limit for the difference
between predicted
versus measured core reactivity
during power operation
to ensure that a reactivity
anomaly, such as change in control rod worth, does not result in a loss of shutdown margin or exceeding
specified
acceptable
fuel design limits. In addition, GEH advised plant operators
to continue monitoring
for reactor coolant boron and tritium concentrations
in accordance
with normal plant procedures
to detect CRB cracking and to follow the GEH Marathon CRB surveillance
program, particularly
for D-Iattice
and S-Iattice
plants. OAGI0001190
00002
CONTACT
This I N requires no specific action or written response.
Please direct any questions
about this matter to the technical
contacts listed below or to the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager. IRA by CRegan fori Timothy J. McGinty, Director Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical
Contacts:
Shih-Liang
Wu, NRR 301-415-3284 IRA by JTappert fori Laura A. Dudes, Director Division of Construction
Inspection
and Operational
Programs Office of New Reactors Arthur Kevin Heller, NRR 301-415-8379 E-mail: Shih-Liang.Wu@nrc.gov
E-mail: Kevin.Heller@nrc.gov
Note: NRC generic communications
may be found on the NRC public Web site, htt(2:1lwww.nrc.gov, under NRC Library. OAGI0001190
00003
CONTACT
This I N requires no specific action or written response.
Please direct any questions
about this matter to the technical
contacts listed below or to the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager. IRA by CRegan fori Timothy J. McGinty, Director Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical
Contacts:
Shih-Liang
Wu, NRR 301-415-3284 IRA by JTappert fori Laura A. Dudes, Director Division of Construction
Inspection
and Operational
Programs Office of New Reactors Arthur Kevin Heller, NRR 301-415-8379 E-mail: Shih-Liang.Wu@nrc.gov
E-mail: Kevin.Heller@nrc.gov
Note: NRC generic communications
may be found on the NRC public Web site, htt(2:1lwww.nrc.gov, under NRC Library. ADAMS Accession
No.: ML111380019 TAC ME5743 OFFICE SNPB:NRR Tech Editor BC:SNPB:NRR
D:DSS BC:SRSB:NRO
NAME AHelier JDougherty
AMendiola
SBahadur JDonoghue
DATE 6/15/2011
5/25/11 e-mail 6/16/2011 6/17/2011
6/14/2011 OFFICE LAPGCB:NRR
PM:PGCB:NRR
BC:PGCB:NRR
D:DCIP:NRO
D:DPR:NRR
NAME CHawes DBeaulieu
SRosenberg
LDudes (JTappert
for) TMcGinty (CRegan for) OFFICE 6/22/11 6/22/2011
06/22/11 06/27/11 06/29/11 OFFICIAL RECORD COpy OAGI0001190
00004
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list | - Information Notice 2011-01, Commercial Grade Dedication Issues Identified During NRC Inspections (15 February 2011, Topic: Commercial Grade Dedication)
- Information Notice 2011-02, Operator Performance Issues Involving Reactivity Management at Nuclear Power Plants (31 January 2011, Topic: Downpower)
- Information Notice 2011-03, Nonconsecutive Criticality Safety Analyses for Fuel Storage (16 February 2011, Topic: Nonconservative Technical Specifications)
- Information Notice 2011-03, Nonconsecutive Criticality Safety analyses for Fuel Storage (16 February 2011, Topic: Nonconservative Technical Specifications)
- Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors (23 February 2011, Topic: Boric Acid)
- Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors (23 February 2011, Topic: Boric Acid)
- Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors (23 February 2011, Topic: Boric Acid)
- Information Notice 2011-05, Tohoku-Taiheiyou-Oki Earthquake Effects on Japanese Nuclear Power Plants (18 March 2011, Topic: Boric Acid, B.5.b Mitigating Strategies, Earthquake)
- Information Notice 2011-07, Specific License Required When Exporting To Embargoed Destinations Listed In 10 CFR 110.28 (14 April 2011, Topic: Moisture Density Gauge)
- Information Notice 2011-08, Tohoku-Taiheiyou-Oki Earthquake Effects on Japanese Nuclear Power Plants - for Fuel Cycle Facilities (31 March 2011, Topic: Boric Acid, Earthquake)
- Information Notice 2011-10, Thermal Issues Identified During Loading of Spent Fuel Storage Casks (2 May 2011, Topic: Fuel cladding)
- Information Notice 2011-11, Heat and Smoke Detector Requirements for 10 CFR Part 36 Irradiators (27 April 2011, Topic: Pandemic)
- Information Notice 2011-12, Reactor Trips Resulting from Water Intrusion Into Electrical Equipment (16 June 2011, Topic: Preliminary White Finding)
- Information Notice 2011-12, Reactor Trips Resulting from Water Intrusion into Electrical Equipment (16 June 2011, Topic: Preliminary White Finding)
- Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) (29 June 2011, Topic: Shutdown Margin)
- Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) (29 June 2011, Topic: Shutdown Margin)
- Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) (29 June 2011, Topic: Shutdown Margin)
- Information Notice 2011-14, Component Cooling Water System Gas Accumulation and Other Performance Issues (18 July 2011, Topic: Unanalyzed Condition, Preliminary White Finding)
- Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues (1 August 2011, Topic: Coatings, Incorporated by reference, Aging Management, Moisture barrier)
- Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping (26 July 2011, Topic: Functionality Assessment)
- Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components (26 September 2011)
- Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) (24 July 2019, Topic: Aging Management)
- Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting From Nuclear Fuel Thermal Conductivity Degradation (13 December 2011, Topic: Fuel cladding)
- Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting from Nuclear Fuel Thermal Conductivity Degradation (13 December 2011, Topic: Fuel cladding)
- Information Notice 2011-22, Instrumentation & Control Module Failures, Incorrect Configurations and Settings (21 December 2011)
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