Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
Results
Other: ML083030246, ML083330066, ML083640401, ML090220584, ML090650061, ML090720066, ML090720068, ML090830248, ML090860762, ML090930256, ML091070269, ML091170031, ML091830055, ML091880258, ML101040676, ML101050376, ML101270268, ML102010302, ML102020397, NLS2009099, SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application
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MONTHYEARML0830302462008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix E, Environmental Report Project stage: Other ML0833300662008-12-19019 December 2008 Determination of Acceptability and Sufficiency for Docketing and Opportunity for a Hearing Regarding the Application from Nebraska Public Power District, for Renewal of the Operating License for the Cooper Nuclear Station Project stage: Other ML0901203602009-01-0909 January 2009 Safety Evaluation Report Project stage: Request ML0836404012009-01-21021 January 2009 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for License Renewal for the Cooper Nuclear Station Unit 1 (TAC No. MD9763 and MD 9737) LTR Project stage: Other ML0906500612009-02-0202 February 2009 Letter from Nebraska State Historical Society Regarding Cooper Nuclear Station License Renewal Project stage: Other ML0907506862009-02-25025 February 2009 Scoping and Process Public Meeting Sides of February 25, 2009 Project stage: Request ML0908400622009-02-25025 February 2009 Transcript of Cooper Nuclear Station License Renewal Pubic Meeting - Evening Session, February 25, 2009, Pages 1-41 Project stage: Meeting ML0908400632009-02-25025 February 2009 Transcript of Cooper Nuclear Station License Renewal Public Meeting - Afternoon Session, Wednesday, February 25, 2009, Pages 1-33 Project stage: Meeting ML0907200662009-02-25025 February 2009 Comment (1) of James Gerweck, on Behalf of the Richardson County, Nebraska, Emergency Management Agency, Supporting CNS License Renewal Project stage: Other ML0907200682009-02-27027 February 2009 Comment (3) of Ashtin Paris, on Behalf of the City of Rock Port, Supporting Nebraska Public Power District'S Cooper Nuclear Station License Renewal Project stage: Other ML0908607622009-03-0909 March 2009 Letter from the Nebraska Department of Natural Resources the Cooper Nuclear Station License Renewal Project stage: Other ML0907200672009-03-10010 March 2009 Comment (2) of Alan Richard, on Behalf of Pawnee City Development Corporation, Supporting Renewal of License for Cooper Nuclear Station Project stage: Request ML0908302482009-04-0303 April 2009 Environmental Site Audit Regarding Cooper Nuclear Station Unit 1 License Renewal Application (TAC MD9763 and MD9737) Project stage: Other ML0902205842009-04-0303 April 2009 Proposed Review Schedule Regarding the Application from Nebraska Public Power District for Renewal of the Operating License for the Cooper Nuclear Station Project stage: Other ML0909302562009-04-0909 April 2009 Audit Plan for Aging Management Program Site Audit Regarding Cooper Nuclear Station Unit 1, License Renewal Application (Tac No. MD9737) Project stage: Other ML0909103082009-04-14014 April 2009 Summary of Public Environmental Scoping Meeting Related to the Review of the Cooper Nuclear Station, Licensed Renewal Application Project stage: Meeting ML0910702692009-04-16016 April 2009 EPA Comment on the Cooper Nuclear Station License Renewal Application Project stage: Other ML0911700312009-04-28028 April 2009 Environmental Site Audit Regarding Cooper Nuclear Station Unit 1 License Renewal Application Project stage: Other ML0909704142009-04-30030 April 2009 Summary of Site Audit Related to the Review of the License Review Application for Cooper Nuclear Station, Unit 1 Project stage: Approval ML0911905972009-05-0101 May 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application (TAC No. MD9763 and MD9737) Project stage: RAI NLS2009039, Response to Request for Additional Information for License Renewal Application - Balance-of-Plant Scoping and Screening2009-05-28028 May 2009 Response to Request for Additional Information for License Renewal Application - Balance-of-Plant Scoping and Screening Project stage: Response to RAI ML0912000172009-05-29029 May 2009 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by the Nebraska Public Power District, for Renewal of the Operating License for Cooper Nuclear Station Unit 1 Project stage: Approval ML0917500882009-06-0101 June 2009 CNS Lr - NDEQ 2009 Ambient Network Plan Project stage: Request ML0918300552009-06-0808 June 2009 Reply from Fish and Wildlife Service on Transmission Line for Cooper Nuclear Station License Renewal Project stage: Other ML0915303162009-06-0808 June 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0917501182009-06-11011 June 2009 CNS Lr - Tornado Occurrences in Nemaha County, Ne 1950-2009 Project stage: Request ML0913803652009-06-15015 June 2009 Audit Report Regarding the Cooper Nuclear Station, Unit 1, License Renewal Application Project stage: Acceptance Review NLS2009040, Response to Request for Additional Information for License Renewal Application - Aging Management Programs2009-06-15015 June 2009 Response to Request for Additional Information for License Renewal Application - Aging Management Programs Project stage: Response to RAI NLS2009049, Response to Request for Additional Information for License Renewal Application - Section B and C2009-06-22022 June 2009 Response to Request for Additional Information for License Renewal Application - Section B and C Project stage: Response to RAI ML0916002892009-06-29029 June 2009 Request for Additional Information for Cooper Nuclear Station License Renewal Project stage: RAI ML0916002782009-06-29029 June 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI NLS2009048, Response to Request for Additional Information for License Renewal Application Severe Accident Mitigation Alternatives2009-07-0101 July 2009 Response to Request for Additional Information for License Renewal Application Severe Accident Mitigation Alternatives Project stage: Response to RAI ML0917503682009-07-0101 July 2009 Summary of Regulatory Audit Related to the Review of the License Renewal Application for Cooper Nuclear Station Project stage: Approval ML0918802582009-07-0808 July 2009 Environment Project Manager Change for the License Renewal of Cooper Nuclear Station Project stage: Other ML0918804782009-07-14014 July 2009 Request for Additional Information Project stage: RAI ML0919005022009-07-14014 July 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0918804822009-07-14014 July 2009 Request for Additional Information for the Review of Cooper Nuclear Station License Renewal Application Project stage: RAI ML0918702982009-07-16016 July 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0918703042009-07-16016 July 2009 License Renewal Request for Additional Information Project stage: RAI ML0921600842009-07-20020 July 2009 Notice of Diane Curran'S Withdrawal of Appearance Project stage: Request ML0920902762009-07-29029 July 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application (TACs MD9763 and MD9737) Project stage: RAI NLS2009055, Response to Request for Additional Information for License Renewal Application2009-07-29029 July 2009 Response to Request for Additional Information for License Renewal Application Project stage: Response to RAI NLS2009063, Response to Request for Additional Information for License Renewal Application2009-08-17017 August 2009 Response to Request for Additional Information for License Renewal Application Project stage: Response to RAI ML0919600402009-08-19019 August 2009 Summary of Regulatory Audit Related to the Review of the License Renewal Application for Cooper Nuclear Station Project stage: Approval ML0923106542009-08-28028 August 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0926500572009-09-28028 September 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0926809352009-10-0707 October 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI ML0927300142009-10-15015 October 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI NLS2009085, Response to Request for Additional Information on License Renewal Application2009-10-22022 October 2009 Response to Request for Additional Information on License Renewal Application Project stage: Response to RAI ML0929200192009-10-29029 October 2009 Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application Project stage: RAI 2009-04-09
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Category:Letter
MONTHYEARML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23311A1122023-11-0909 November 2023 Project Manager Assignment ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20243012023-09-0101 September 2023 Notification of NRC Initial Operator Licensing Examination 05000298/2024301 IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23102A0282023-04-19019 April 2023 U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting IR 05000298/20230012023-04-17017 April 2023 Integrated Inspection Report 05000298/2023001 ML23060A1582023-03-0808 March 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001 IR 05000298/20220062023-03-0101 March 2023 Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006 ML23041A1622023-02-10010 February 2023 Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information IR 05000298/20220042023-01-30030 January 2023 Integrated Inspection Report 05000298/2022004 IR 05000298/20220112022-12-23023 December 2022 License Renewal Phase 4 Inspection Report 05000298/2022011 ML22286A2072022-11-30030 November 2022 Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements IR 05000298/20220032022-10-27027 October 2022 Integrated Inspection Report 05000298/2022003 ML22304A0052022-10-26026 October 2022 Surveillance Capsule Location (Re-insertion Into the Reactor Vessel) IR 05000298/20223022022-10-20020 October 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022302 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information IR 05000298/20224022022-09-29029 September 2022 NRC Security Inspection Report 05000298/2022402 (Full Report) IR 05000298/20220052022-08-18018 August 2022 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298 2022005) IR 05000298/20223012022-08-10010 August 2022 NRC Examination Report 05000298/2022301 IR 05000298/20220022022-07-28028 July 2022 Integrated Inspection Report 05000298/2022002 ML22200A2772022-07-21021 July 2022 Correction to Proposed Inservice Testing Alternative RS-01, Revision of Error in Safety Evaluation ML22152A1232022-07-18018 July 2022 Issuance of Amendment No. 271 Request for Exception from Certain Primary Containment Leak Rate Testing Requirements IR 05000298/20224012022-06-29029 June 2022 Security Baseline Inspection Report 05000298/2022401 IR 05000298/20224032022-06-28028 June 2022 Security Baseline Inspection Report 05000298/2022403 IR 05000298/20220102022-06-16016 June 2022 Triennial Fire Protection Inspection Report 05000298/2022010 ML22140A1612022-06-0808 June 2022 Proposed Inservice Inspection Alternative RR5-01 Revision 1 ML22147A1122022-06-0101 June 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022301 ML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 IR 05000298/20220012022-04-28028 April 2022 Integrated Inspection Report 05000298/2022001 IR 05000298/20224042022-04-13013 April 2022 Material Control and Accounting Program Inspection Report 05000298/2022404 - (Public) ML22084A6032022-04-0404 April 2022 Notification of NRC Evaluations of Changes, Tests and Experiments Inspection 05000298/2022002 and Request for Information ML22090A2892022-04-0101 April 2022 John Larson'S Invitation to Participate in the 8th Nuclear Regulatory Commission'S Workshop on Vendor Oversight ML22045A0012022-03-31031 March 2022 Proposed Inservice Inspection Alternative RI5- 02 Revision 3 IR 05000298/20210062022-03-0202 March 2022 Annual Assessment Letter for Cooper Nuclear Station (Report 05000298/2021006) IR 05000298/20210042022-01-24024 January 2022 Integrated Inspection Report 05000298/2021004 ML21350A0582021-12-21021 December 2021 Withdrawal of an Amendment Request ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements 2024-01-03
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Text
H Nebraska Public Power District"Always there when you need us" 54.17 NLS2009092 November 16, 2009 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555-0001
Subject:
Response to Request for Additional Information for the Review of Cooper Nuclear Station License Renewal Application Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
1.Letter from Tam Tran, U.S. Nuclear Regulatory Commission, to Stewart B. Minahan, Nebraska Public Power District, dated October 15, 2009, "Request for Additional Information for the Review of the Cooper Nuclear Station License Renewal Application (TAC No. MD9763 and MD9737)." 2. Letter from Stewart B. Minahan, Nebraska Public Power District, to U.S.Nuclear Regulatory Commission, dated September 24, 2008, "License Renewal Application" (NLS2008071).
Dear Sir or Madam:
The purpose of this letter is for the Nebraska Public Power District to respond to the Nuclear Regulatory Commission Request for Additional Information (Reference
- 1) regarding the Cooper Nuclear Station License Renewal Application (Reference 2). This response is provided in the Attachment to this letter.Should you have any questions regarding this submittal, please contact David Bremer, License Renewal Project Manager, at (402) 825-5673.COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone:
(402) 825-3811 / Fax: (402) 825-5211 www nppd.com NLS2009092 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.Executed on (Date)Sincerely, Stewart B. Minahan Vice President
-Nuclear and Chief Nuclear Officer/Wv Attachment cc: Regional Administrator w/ attachment USNRC -Region IV Cooper Project Manager w/ attachment USNRC -NRR Project Directorate IV-l Senior Resident Inspector w/ attachment USNRC -CNS Nebraska Health and Human Services w/ attachment Department of Regulation and Licensure NPG Distribution w/ attachment CNS Records w/ attachment NLS2009092 Attachment Page 1 of 4 Attachment Response to Request for Additional Information for License Renewal Application Cooper Nuclear Station, Docket No. 50-298, DPR-46 The Nuclear Regulatory Commission (NRC) Request for Additional Information (RAI)regarding the License Renewal Application is shown in italics. The Nebraska Public Power District's (NPPD) response to this RAI is shown in block font.NRC Request: RAI B. 1.30-2 One Time Inspection -Small Bore Piping Background In a letter dated May 1, 2009, the staff requested additional information on how the applicant plans to address volumetric inspections of socket welds in its aging management program (AMP)for American Society of Mechanical Engineers (ASME) Class ] small-bore piping. In a letter dated June 15, 2009, the applicant responded stating that, "NUREG Section XM.M35 does not explicitly address socket welds. Because there is no accepted industry standard method for volumetric examination of socket welds, no such examinations are included in the CNS [Cooper Nuclear Station] program." The applicant goes on to discuss the fact that a surface inspection and visual inspection (VT-2) ofASME Class 1 small-bore piping socket welds will be performed in lieu of a volumetric inspection.
Finally, the applicant stated that a review of site-specific operating experience had been performed and that no history of cracking in Class 1 small-bore piping, including socket welds, had been identified Issue The staff does not consider the performance of surface and VT-2 inspections to be a suitable alternative to volumetric inspections as a means of detecting cracking of socket welds in ASME Class ] small-bore piping. Specifically, these types of inspections are not effective for detecting sub-surface cracks that may exist in these welds.It is also not clear that relevant industry operating experience was considered when the decision was made to not perform volumetric inspections of these socket welds. The staffperformed a cursory review of available operating experience and identified several examples of socket weld failures resulting from cracking.
Since 1997, as many as 47 socket weld failures have occurred at 35 nuclear power plants. Aging effects identified during the cause analysis was largely cracking on the inside diameter (below the visible surface of the weld) stemming from intergranular stress corrosion and fatigue. At least 12 of the 47 occurrences resulted in plant scrams or other significant operational challenges.
NLS2009092 Attachment Page 2 of 4 Request The staff requests the applicant provide an AMP for detecting cracking in ASME Class 1 small-bore piping, including sub-surface cracking in socket welds. As discussed in NEI 95-10,"Industry Guidelines for Implementing the Requirements of 10 CFR Part 54 -The License Renewal Rule," the staff also requests that a review of relevant industry operating experience be conducted to determine whether it changes the conclusions drawn from the previously performed plant-specific determinations.
NPPD Response: To manage the effects of aging on ASME Class 1 small-bore piping, NUREG- 1801 recommends the program described in Section XI.M35, "One-Time Inspection of ASME Code Class 1 Small-Bore Piping." NPPD credits the AMP described in NUREG-1801,Section XI.M35 to manage the effects of aging on ASME Class 1 small-bore piping at Cooper Nuclear Station (CNS). The operating experience attribute of AMP XI.M35 states: This inspection uses volumetric inspection techniques with demonstrated capability and a proven industry record to detect cracking in piping weld and base material.
However, the application of the specific technique to ASME Code Class 1 small-bore piping needs to be qualified before the examination.
In summary, NUREG-1801 AMP XI.M35 recommends volumetric testing using qualified techniques with demonstrated capability to detect cracking in small-bore piping.For socket welds, there are no volumetric inspection techniques with demonstrated capability and a proven industry record to detect cracking in piping weld and base material.
This position was reaffirmed by the staff in the following passage from the Beaver Valley license renewal Safety Evaluation Report issued on June 8, 2009 (ADAMS Accession Number ML091600216):
The staff confirms that because there is no accepted method to volumetrically inspect these welds, it has accepted visual inspection of socket welds and notes that any cracks that form in these welds would initiate from the inside diameter, which would be very difficult to detect using a volumetric technique due to the configuration of the socket welds. The staff concludes that a visual inspection at operating temperature and pressure is the only practical method for inspecting these welds.NPPD employs visual inspection at operating temperature and pressure for inspecting ASME Class 1 small-bore piping at CNS.In response to the staff request, a review of recent industry operating experience was performed using the NRC ADAMS database.
NPPD reviewed licensee event reports (LER) from ADAMS NLS2009092 Attachment Page 3 of 4 that contained the word "socket." The review identified 70 items of which only 22 were related to cracking of Class 1 piping socket welds. These events were the result of high-cycle fatigue cracking due to vibration or weld defects during installation.
Cracking due to high-cycle fatigue is the result of improper design or installation that creates an unanalyzed condition that will lead to failure of the component early in life if not corrected.
It is not related to the effects of aging.Typical industry response to cracking caused by high-cycle fatigue is to modify the design to6 prevent recurrence including using improved socket welds and changing the installation to eliminate the vibration.
The plant shutdowns required by some of these events were the result of Technical Specification requirements regarding reactor coolant system leakage even though the size of the leaks did not impact the ability of the systems to perform their design functions.
None of the LERs identified stress corrosion cracking or corrosion as the cause of the cracking.The conclusions of this review are also supported by information published by the NRC in NUREG/CR-6936, Probabilities of Failure and Uncertainty Estimate Information for Passive Components
-A Literature Review, May 2007. It states: Vibration fatigue failures are normally a result of poor piping design or installation and welding practices.
A relatively large share of vibration fatigue failures initiates at the fillets of socket and support attachment welds due to a high stress concentration at the juncture of the weld and base metal. Small-bore pipe socket welded vent and drain connections less than 25.4 mm (<1.0 in.) in the immediate proximity of vibration sources tend to be most susceptible to this failure mechanism (Olson 1985; EPRI 1994 Riccardella et al, 1997; Shah et al 1998).Unlike the previously discussed mechanisms, vibration fatigue may not always lend itself to periodic inservice examinations (i.e., volumetric, surface) as a means of managing this degradation mechanism.
This is especially true if the inspections occur at the normal inservice inspection frequency of once every 10 years. The nature of this mechanism is such that, generally, almost the entire fatigue life of the component is expended during the initiation phase. Once a crack initiates, failure quickly follows. Therefore, the absence of any detectable crack may not ensure reliable component performance.
This industry operating experience supports the adequacy of the inspections of small-bore piping socket welds at CNS described in response to RAI B.1.30-1.
As additional clarification to the cited response to RAI B. 1.30-1, prior to 2004 NPPD experienced socket weld cracking due to high-cycle fatigue from excessive vibration that was not related to the effects of aging. That response stated that small-bore piping and socket welds are inspected in accordance with ASME Code requirements.
These Code requirements take into consideration the low safety significance of small-bore piping leakage and the predominant mechanism of high-cycle fatigue (vibration).
The inspection consists of a VT-2 visual inspection during system leakage tests each refueling NLS2009092 Attachment Page 4 of 4 outage per the requirements of IWB-2500-1, Examination Category B-P. This type of inspection has been determined sufficient for the current period of operation and approved by the NRC under 10 CFR 50.55a. Any change in the requirements for inspections of socket welds would be addressed by a change to the ASME Code which would be adopted by CNS. Current industry and site operating experience described above have identified only cracking in small-bore socket welds due to high-cycle fatigue and provides no evidence for the need to change existing requirements for inspections of socket welds.Through the period of extended operation, NPPD will continue to implement at CNS the requirements of ASME Code Section XI as endorsed and modified by the NRC staff in 10 CFR 50.55a. This will include any future provisions for volumetric examination of small-bore socket welds when methods for such examination are developed and endorsed by the ASME Section XI Code and the NRC staff.
ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© 4 ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS0 4 Correspondence Number: NLS2009092 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document.
Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments.
Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE None I I I I PROCEDURE 0.42 REVISION 24 PAGE 19 OF 26