Letter Sequence Other |
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TAC:ME8551, Control Room Habitability (Approved, Closed) |
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MONTHYEARNLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012
Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)
Project stage: Request
ML1211800892012-05-22022 May 2012
National Fire Protection Association (NFPA) Standard NFPA 805, License Amendment Request - Online Reference Portal
Project stage: Other
ML1217400472012-06-21021 June 2012
Email, Request for Supplement to Complete Acceptance Review, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: Acceptance Review
ML1217400512012-06-21021 June 2012
List of Questions for Supplement to Complete Acceptance Review, License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: Acceptance Review
NLS2012068, Response to Acceptance Review of Cooper Nuclear Station License Amendment Request to Adopt NFPA-8052012-07-12012 July 2012
Response to Acceptance Review of Cooper Nuclear Station License Amendment Request to Adopt NFPA-805
Project stage: Request
ML12207A4842012-07-25025 July 2012
Acceptance Review Email Following Supplement, License Amendment Request to Adopt National Fire Protection Agency (NFPA)-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: Acceptance Review
ML12283A4002012-10-0909 October 2012
Email, Draft Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA)-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: Draft RAI
ML12312A2812012-11-14014 November 2012
Request for Additional Information, License Amendment Request to Adopt National Fire Protection Agency (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: RAI
ML13039A0812013-02-0707 February 2013
Email Conference Call Attendees for 2/7/2013 Phone Conference Regarding Rais, Request to Adopt National Fire Protection Agency (NFPA)-805 Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: RAI
NLS2013032, 120-Day Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052013-03-13013 March 2013
120-Day Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
Project stage: Response to RAI
ML13319B2202013-11-14014 November 2013
NRR E-mail Capture - Cooper Nuclear Station: Round 2 RAIs NFPA-805 LAR (ME8551)
Project stage: RAI
NLS2013104, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Cooper Nuclear Station2013-12-12012 December 2013
Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Cooper Nuclear Station
Project stage: Response to RAI
NLS2014001, Day Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052014-01-17017 January 2014
Day Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
Project stage: Response to RAI
ML14034A0502014-02-0606 February 2014
Summary of Audit Conducted 1/28-29/2014, License Amendment Request to Adopt National Fire Protection Agency (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: Other
NLS2014015, Supplement to 60-Day Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052014-02-18018 February 2014
Supplement to 60-Day Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
Project stage: Supplement
ML14077A0202014-03-17017 March 2014
Final Cooper Section 3 4 Fpra Record-of-Review 03-17-2014
Project stage: Request
ML14104A8722014-03-27027 March 2014
NRR E-mail Capture - Request for NFPA 805 License Amendment Facutrual Accuracy Review
Project stage: Acceptance Review
ML14077A0192014-03-28028 March 2014
Final Cooper Section 3 4 IE PRA Record-of-Review 03-13-2014
Project stage: Request
NLS2014031, Revisions to NFPA 805 License Amendment Request and Response to a Request for Additional Information2014-04-11011 April 2014
Revisions to NFPA 805 License Amendment Request and Response to a Request for Additional Information
Project stage: Response to RAI
ML14055A0232014-04-29029 April 2014
Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
Project stage: Approval
2013-02-07
[Table View] |
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Category:Meeting Summary
MONTHYEARML24204A0912024-07-30030 July 2024
Summary of May 9, 2024, Preapplication Teleconference with Nebraska Public Power District to Discuss Proposed Changes to the Cooper Nuclear Station Emergency Plan
ML24122C6862024-05-0202 May 2024
Summary of the April 24, 2024 Information Meeting with Question and Answer Session to Discuss the 2023 Annual Assessment of Safety Performance at Cooper Nuclear Station
ML24016A0772024-02-0202 February 2024
December 13, 2023, Summary of Pre-application Teleconference with Nebraska Public Power District to Discuss License Amendment to Adjust High Pressure Coolant Injection Flow Setpoints for Cooper Nuclear Station
ML23165A0352023-06-26026 June 2023
Summary of June 1, 2023, Pre-Application Teleconference with Nebraska Public Power District to Discuss Planned License Amendment Request to Add Temporary Note to TS LCO 3.8.3 for Diesel Fuel Oil Tank Cleaning and Inspection
ML23164A1152023-06-23023 June 2023
Summary of Pre-Application Teleconference with Nebraska Public Power District to Discuss Relief Request for Drywell Inspections Performed During Refueling Outage 32
ML22147A0932022-06-0606 June 2022
2021 Annual Assessment Public Meeting Summary
ML21140A3892021-05-24024 May 2021
Riv Column 1 EOC 2020 Public Meeting Summary
ML20189A2832020-07-0707 July 2020
Summary of Region IV Annual Assessment Public Meeting
ML19350C3122019-12-19019 December 2019
Summary of December 3, 2019, Public Meeting with Nebraska Public Power District, on Proposed Changes to the Emergency Plan to Revise the Emergency Action Level Scheme at Cooper Nuclear Station
ML19204A2452019-07-25025 July 2019
Summary of Presubmittal Teleconference with Nebraska Public Power District Regarding Proposed Exemption from Appendix J of 10 CFR Part 50 for Cooper Nuclear Station
ML17324A2802017-11-16016 November 2017
Summary of Regulatory Conference to Discuss Safety Significance of Cooper Nuclear Station Emergency Station Service Transformer Bus Duct Deficiency
ML16334A4732016-12-0606 December 2016
Summary of Closed Meeting to Discuss Dam Failure Analysis Developed for the Integrated Assessment for Cooper Nuclear Station
ML14156A2832014-06-16016 June 2014
Summary of 5/22/2014 Meeting with Omaha Public Power District and Nebraska Public Power District to Discuss Flooding Hazard Evaluation Extension Requests for Fort Calhoun, Unit 1, and Cooper Nuclear Station
ML14147A3592014-06-0909 June 2014
Summary of Meeting Between Army Corps of Engineers, NRC, Omaha Public Power District, and Nebraska Public Power District - Discuss Flooding Analysis Associated with Fort Calhoun, Unit 1 and Cooper Nuclear Station
ML14139A3582014-06-0505 June 2014
5/9/2014 Summary of Meeting with Omaha Public Power District and Nebraska Public Power District to Discuss Flooding Hazard Evaluation Extension Requests for Fort Calhoun, Unit 1, and Cooper Nuclear Station
ML14139A3442014-05-29029 May 2014
Summary of Closed Meeting Between Representatives of the Nuclear Regulatory Commission, Omaha Public Power District and Nebraska Public Power District to Discuss Flooding Analysis
ML14031A1622014-02-10010 February 2014
Summary of Meeting Between Army Corps of Engineers, NRC, Omaha Public Power District, and Nebraska Public Power District - Discuss Flooding Analysis Associated with Fort Calhoun, Unit 1 and Cooper Nuclear Station
ML14034A0502014-02-0606 February 2014
Summary of Audit Conducted 1/28-29/2014, License Amendment Request to Adopt National Fire Protection Agency (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
ML13178A1592013-06-26026 June 2013
Summary of Meeting for Public Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station
ML1132200762011-12-0505 December 2011
Summary of Meeting with Nebraska Public Power District to Discuss Amendment Request to Implement a 24-Month Fuel Cycle and Adopt Technical Specification Task Force (TSTF)-493, Revision 4 for Cooper Nuclear Station
ML1131903962011-11-0303 November 2011
Summary of Meeting with Nebraska Public Power District to Discuss Safety Performance at Cooper Nuclear Station
ML11292A1612011-10-20020 October 2011
Summary of Meeting with Beyond Nuclear Regarding Their 10 CFR 2.206 Petition to Suspend Operating Licenses of General Electric Mark I Boiling Water Reactors
ML1121700812011-08-18018 August 2011
7/12/11 - Summary of Teleconference with Nebraska Public Power District to Discuss Cooper'S Request to Revise TS 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs) at Cooper Nuclear Station
ML11166A1342011-06-22022 June 2011
Meeting Summary with the Beyond Nuclear Petitioners Regarding Their 2.206 Petition to Suspend Operating Licenses (Ols) of General Electric (GE) Boiling Water Reactors (Bwrs) Mark I (Bwrs)
ML1112606772011-05-0606 May 2011
Summary of Meeting with Nebraska Public District, Cooper Discussed the Significance, Cause and Corrective Action Associated with an Apparent Violation with Low-to-Moderate Safety Significance
ML1029204632010-10-29029 October 2010
Summary of Pre-Licensing Meeting with Nebraska Public Power District to Discuss Future License Amendment Request for Cooper Nuclear Station TSTF-493, Revision 4, Clarify Application of Setpoint Methodology for LSSS Functions
ML1015303172010-07-13013 July 2010
Summary of Telephone Conference Call Held on May 26, 2010 Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information, for Cooper Nuclear Station Lic
ML1015204892010-06-16016 June 2010
Summary of Telephone Conference Call Held on May 18, 2010, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station Lic
ML1016001102010-06-0909 June 2010
Summary of Annual Performance Assessment Meeting for Cooper Nuclear Station
ML1010406562010-05-11011 May 2010
04/07/10 Summary of Public Meeting to Discuss the Draft Supplemental Environmental Impact Statement Related to the Review of Cooper Nuclear Station License Renewal Application
ML1011904802010-04-29029 April 2010
Summary of Meeting with Nebraska Public Power District to Discuss Issues Associated with the Independent Spent Fuel Storage Installation (ISFSI)
ML1007106452010-04-20020 April 2010
Summary of Telephone Conference Call Held Between NRC & NPPD, Related to a Clarification for Certain Responses to RAI for Cooper Nuclear Station Lr
ML1002901692010-02-26026 February 2010
Summary of Telephone Conference Call Held on January 14, 2010, Between the U.S. NRC and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station Licen
ML1001900422010-02-0303 February 2010
Summary of Telephone Conference Call Held on 1/8/2010, Between the U.S. NRC and Nebraska Public Power District Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station
ML1000900472010-01-21021 January 2010
November 9, 2009, Summary of Telephone Conference Call Held on Between NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper License Renewal
ML0929200262009-10-28028 October 2009
Summary of Telephone Conference Call Held on 09/14/09, Between the U.S. NRC Staff and NPPD, Related to a Request for Additional Information (RAI) and Clarification for Certain Responses to Rais, for Cooper Nuclear Station License Renewal
ML0923007182009-10-15015 October 2009
Summary of Teleconference Call Held Between the NRC and Nebraska Public Power District Related to Clarifications on Request for Additional Information for Cooper
ML0926805692009-10-0808 October 2009
09/02/09 Summary of Telephone Conference Call Between NRC Staff and NPPD, Related to a Clarification for Certain Responses to Requests for Additional Information, for Cooper Nuclear Station License Renewal
ML0923804342009-09-17017 September 2009
07/07/2009 Meeting Summary, Telephone Conference Call Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal
ML0923101202009-09-17017 September 2009
Summary of Tele Conf Call with Nebraska Public Power Districts to Discuss Clarifications for the Severe Accident Mitigation Alternative Documented in the NRC Request for Additional Information Letter Dated May 1, 2009
ML0920103992009-08-25025 August 2009
Summary of Telephone Conference Call Held on June 16, 2009, Between the NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal
ML0920303052009-07-29029 July 2009
Summary of Telephone Conference Call Held on 7/9/2009, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal
ML0917503682009-07-0101 July 2009
Summary of Regulatory Audit Related to the Review of the License Renewal Application for Cooper Nuclear Station
ML0915604962009-06-10010 June 2009
Summary of Telephone Conference Call Held on May 20, 2009, Between the USNRC Staff and NPPD, Related to a Clarification on Certain RAI (RAI B.1.15-3 and RAI B.1.15-4), for CNS Renewal
ML0909704142009-04-30030 April 2009
Summary of Site Audit Related to the Review of the License Review Application for Cooper Nuclear Station, Unit 1
ML0909103082009-04-14014 April 2009
Summary of Public Environmental Scoping Meeting Related to the Review of the Cooper Nuclear Station, Licensed Renewal Application
ML0909700972009-04-0707 April 2009
Summary of Annual Performance Assessment Meeting with Nebraska Public Power District to Discuss Safety Performance at Cooper Nuclear Station Between January 1 & December 31, 2008
ML0831101972008-11-0505 November 2008
Summary of Meeting with Nebraska Public Power District to Discuss Inspection Procedure 95002 Supplemental Inspection Preparations and Diesel Generator Performance Improvement Plan
ML0810900022008-04-22022 April 2008
Summary of Telephone Conference Verbal Authorization for Cooper Relief Request RI-35
ML0720002802007-07-18018 July 2007
Meeting Summary for Regulatory and Predecisional Enforcement Conference; Cooper Nuclear Station
2024-07-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 6, 2014 LICENSEE: Nebraska Public Power District FACILITY: Cooper Nuclear Station
SUBJECT:
SUMMARY
OF COOPER NUCLEAR STATION JANUARY 28 AND 29, 2014, AUDIT ASSOCIATED WITH LICENSE AMENDMENT REQUEST TO TRANSITION TO NATIONAL FIRE PROTECTION ASSOCIATION 805 STANDARDS (TAC NO. ME8551)
The purpose of this summary is to document the results of an audit performed at Cooper Nuclear Station (CNS) associated with a National Fire Protection Association 805 (NFPA-805) license amendment request (LAR) dated April 24, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121220216). The audit was in the area of the probabilistic risk assessment (PRA) portion of the LAR.
The audit plan is documented in a U.S. Nuclear Regulatory Commission (NRC) staff e-mail dated January 13, 2014 (ADAMS Accession No. ML14015A336). Below is a summary of the audit.
Audit Location and Dates The audit was held at the CNS site in Brownville, Nebraska on January 28, and 29, 2014.
Attendees The following NRC staff from the Office of Nuclear Reactor Regulation (NRR), Division of Risk Assessment (ORA), PRA Licensing Branch (APLA) participated in the audit: Hossein Hamzehee, Steve Dinsmore, and Dan O'Neal Nebraska Public Power District (NPPD, the licensee) personnel that participated in substantive discussions included the following:
Ole Olson NPPD Steve Nelson NPPD Steve Meyer Scientech Manuel Saadallah EPM Todd Stevens NPPD James Blum EPM Thomas Shudak NPPD Jim Chapman Scientech Bill Victor NPPD
Information Reviewed During the Audit As discussed in the January 13, 2014, audit plan, the NRC staff discussed PRA-related information associated with NPPD's April 24, 2012, NFPA-805 LAR. During the audit, the NRC staff discussed request for additional information {RAI) responses provided by NPPD by letters dated December 12, 2013, and January 17, 2014 (ADAMS Accession Nos. ML13353A073 and ML14027A425, respectively). As needed, the LAR and previous RAis were discussed.
Supplemental information that would support completion of the NRC staff's review was discussed and provided in Enclosure 1. In addition, the licensee drafted a summary of the PRA discussions and provided it to the NRC staff for reference in the audit trip report. The licensee's summary is provided as Enclosure 2.
Docket No. 50-298
Enclosures:
- 1. NRC staff Notes on January 28 and 29, 2014, NRC Audit Requests
- 2. NPPD's Notes on January 28 and and 29, 2014, NRC Audit Requests cc w/encls: Distribution via Listserv
NRC Staff Notes on January 28 and 29, 2014, NRC Audit Requests Aside from the changes or additions discussed below, the NRC staff stated that further probabilistic risk assessment (PRA)-related information to complete the review was not needed at this time although additional information may be identified as the safety evaluation is finalized. The following supplementary information or modifications to the request for additional information (RAI) responses were discussed with the licensee during the audit.
PRA RAI-02b The response to the RAI 02b discussed reduced damage temperatures and additional ignition sources. The staff expressed concern regarding the lack of a clear summary of the integrated final methodology for modelling Kerite cables. The licensee agreed to provide a summary of how Kerite cables were evaluated either as a table entry (in the table to be referenced in the implementation items) or a RAI response that can be referenced in the table.
PRA RAI35 The response to the RAI stated that an updated Table G-1 (of the license amendment request (LAR)) will be provided in a future submittal. After some discussion, the NRC staff stated that an updated Table G-1 is not needed to complete the review and the statement could be retracted.
PRA RAI 14.01 The response to this RAI provided a description and results of the main control room (MCR) re-analysis. The response describes a methodology that uses a single conditional core damage probability (CCDP) of about 0.1 for all MCR abandonment scenarios. The NRC staff questioned the use of a single, relatively low, CCDP for all MCR abandonment scenarios and noted that plant-specific and shutdown capability characteristics were not described sufficiently in the current RAI response before the review could be completed. The licensee agreed to provide additional information to support its proposed use of a single CCDP.
The licensee also agreed to provide additional information including 1) a brief explanation on how the incipient detection scenarios are included in the MCR abandonment risk calculations, and 2) some discussion of the impact of using the single CCDP on the transition change in risk estimate.
PRA RAI40 The response to RAI 40 was discussed extensively. The response includes a Table 1 that indicates how the PRA has been changed or will be changed with a reference to the RAI responses that describe the change. The discussion centered on identifying 1) changes that had been made to the PRA in support of the transition risk estimate, and 2) other changes that have not yet been made but should be made before the licensee uses the PRAto calculate affected changes in risk for post-transition changes as part of the self-approval process. The NRC staff requested that the licensee clarify the status of all the changes. In particular, the Enclosure 1
NRC staff requested the licensee provide a record of the changes and to indicate any planned changes and when these changes will be made. For example, if a link to the RAI response describing each issue/method that was or will be changed was included, the use of fire PRA methods acceptable to the NRC staff should be documented. Subsequent changes to fire PRA methods to alternative acceptable methods may be made using the post-transition change process.
Two fire PRA changes that were in previous RAI response but were not in the current table were identified: PRA RAI 06 (regarding non-suppression probabilities) and PRA RAI 02.h.01 (regarding including the impact of state of knowledge correlations on the risk estimates). The licensee agreed to partially reformat and clarify the entries in the current table, to add the two missing entries, and to identify when the entry has or will be completed. The revised table could then be referenced by an entry in one of the Attachment S tables and incorporated by reference into the license condition. The licensee agreed to consider developing a new Attachment S implementation item that would reference the revised table.
PRA RAI 16.02 The NRC staff indicated that the response to 16.02 did not clearly state that all failures associated with fire induced cable failure were included in the risk evaluations. The licensee agreed to provide a more concise description of how the risk of variance from deterministic requirements (VFDRs) are calculated that would include this information.
Nebraska Public Power District's Notes on January 28 and 29, 2014, NRC Audit Requests PRA RAI 02.h.01 Concern: Wording of S-3.30 does not address what to do if Regulatory Guide (RG) 1.205 couldn't be met (i.e. if NRC approval is necessary).
Resolution: No change required, consistent with Callaway Implementation Item.
Concern: S-3.30 should include updating the model with correlations to state-of-knowledge/
uncertainty.
Resolution: Licensee will include in Supplement to RAI 40. New Implementation item S-3.19 will update the fire probabilistic risk assessment (FPRA) model as described in RAI 40 Supplement (self-approval).
PRA RAI 19.01 Concern: Check on including S-3 Table in scope of Licensing Condition.
Resolution: License Condition 2.C(4) will be reviewed to include both the S-2 and S-3 tables.
However, wording will be included that following implementation of these activities, future changes to these Implementation Items will be made under the change management provisions of this License Condition. (Reference DC Cook, Duane Arnold Energy Center, Callaway)
Concern: Provide a consolidated S-2 and S-3 Table.
Resolution: Licensee will provide updated tables in Supplement.
PRA RAI35 Concern: Clarify Part c that no G-1 Table update is needed.
Resolution: Licensee will provide RAI 35 supplement that no update to G-1 Table is needed for the current plant configuration.
PRA RAI 03.01 Concern: May need clarification to main control room (MCR) abandonment. Refer to RAI 14.01 for methodology revision for incipient detection.
Resolution: Incorporate language in RAI 40 Supplement that details that RAI 14.01 methodology is also used for incipient detection.
Concern: Ensure use of .1 08 in fire PRA update. Include in S-3.30.
Enclosure 2
Resolution: The licensee plans to create S-3.31 to reference RAI 40 table that discusses model update with 108.
PRA RAI 14.01 Concern: Clarify .1 08 is appropriate for MCR abandonment.
Resolution: The licensee will supplement RAI response with additional justification. The licensee will include application with habitability, and loss of control. The licensee will address delta risk changes with increases in 0.1 08.
PRA RAI40 Concern: Need Implementation Item to update fire model and methodologies going forward.
Resolution: The licensee will provide Implementation Item S-3.31 providing this with reference to RAI 40. The licensee will also ensure 02.h.01 recognizes S 3.30 vs. S 3.31.
Concern: Clarify RAI 40 for 02.f(i). 01.
Resolution: This is subconcern from above.
Concern: Convert appropriate "No's" to "Yes's", with appropriate justification.
Resolution: The licensee will include in RAI 40 Supplement.
PRA RAI16.02 Concern: Look at response to see if clarification is needed on how cable damage is considered in variance from deterministic requirements (VFDRs).
Resolution: The licensee will supplement RAI with additional information.
PRA RAI 06 Concern: Add NSP s 1E-3 to response.
Resolution: The licensee will add row to PRA RAI 40 table.
ML13353A073 and ML14027A425, respectively). As needed, the LAR and previous RAis were discussed.
Supplemental information that would support completion of the NRC staff's review was discussed and provided in Enclosure 1. In addition, the licensee drafted a summary of the PRA discussions and provided it to the NRC staff for reference in the audit trip report. The licensee's summary is provided as Enclosure 2.
Please direct any inquiries to me at 301-415-1132 or at Joseph.Sebrosky@nrc.gov.
IRA/
Joseph M. Sebrosky, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosures:
- 1. NRC staff Notes on January 28 and 29, 2014, NRC Audit Requests
- 2. NPPD's Notes on January 28 and and 29, 2014, NRC Audit Requests cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC DONeal, NRR LPL4-1 Reading SDinsmore, NRR RidsNrrDorllpl4-1 Resource HHamzehee, NRR RidsNrrLAJBurkhardt Resource LFields, NRR RidsNrrPMCooper Resource JRobinson, NRR ADAMS Accession No. ML14034A050 OFFICE NRR/DORLILPL4-1 /PM NRR/DORLILPL4-1/LA NRR/DRA/APLA/BC NAME JSebrosky JBurkhardt HHamzehee DATE 2/6/14 2/5/14 2/6/14 OFFICE NRR/DORL/LPL4-1 /BC NRR/DORLILPL4-1/PM NAME MMarkley JSebrosky DATE 2/6/14 2/6/14
