ULNRC-06182, Response to NRC Regulatory Issue Summary (RIS) 2014-13, Planned Licensing Action Submittal for All Power Reactor Licensees.

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Response to NRC Regulatory Issue Summary (RIS) 2014-13, Planned Licensing Action Submittal for All Power Reactor Licensees.
ML15034A631
Person / Time
Site: Callaway Ameren icon.png
Issue date: 02/03/2015
From: Maglio S
Ameren Missouri, Union Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
(RIS) 2014-13, ULNRC-06182
Download: ML15034A631 (8)


Text

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"HAmeren Callaway Plant MISSOURI February 3, 2015 ULNRC-06182 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 RESPONSE TO NRC REGULATORY ISSUE

SUMMARY

(RIS) 2014-13, "PLANNED LICENSING ACTION SUBMITTALS FOR ALL POWER REACTOR LICENSEES" NRC Regulatory Issue Summary (RIS) 2014-13, "Planned Licensing Action Submittals for All Power Reactor Licensees," was issued on December 17, 2014 to request all power reactor licensees to provide information regarding the licensing actions they plan to request and submit to the NRC for review over the next three calendar years, as well as power uprate applications they plan to submit to the NRC for review over the next five calendar years. The primary purpose is to assist the NRC in determining resource and budget needs with respect to future licensing activities and in planning the technical resources needed for reviews of licensing submittals/activities.

Although, as stated in the RIS, no specific action or written response is required, it is noted that submission of the requested information will enable the agency to more efficiently and effectively plan its licensing work. As the licensee for Callaway Plant, Ameren Missouri (Union Electric) agrees to provide the requested information. The requested information is provided in the attachment to this letter. Most of the planned licensing actions listed in the attachment are either license amendment requests or ASME Code relief requests. There is no plan for a power uprate for Callaway in the next five years.

The contents and format of the attached are in accordance with the recommendations stated in the RIS .

In addition, a copy of this letter (with attachment) has been provided to the contact specified in the RIS.

                                                                                                                                                                                                                                                    • PO Box 620 Fulton, MO 65251 AmerenMissouri.com ..............

STARS

  • Alliance

ULNRC-06182 February 3, 2015 Page2 For any questions you may have regarding this letter and the attached, please contact Scott Maglio at (573) 676-8719.

Sincerely,

<j~tf A* ¥\\ )

Scott A. Magli~

Manager, Regulatory Affairs TBE/nls

Attachment:

Table of Estimated Licensing Actions

ULNRC-06182 February 3, 2015 Page 3 cc: Mr. Marc L. Dapas Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Fred Lyon Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8B 1 Washington, DC 20555-2738 Mr. Tracy Orf Division of Operating Reactor Licensing Technical Assistant U.S. Nuclear Regulatory Commission Mail Stop 0-8C2 Rockville, MD 20852-2738

ULNRC-06182 February 3, 2015 Page4 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4150 International Plaza Suite 820 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)

Electronic distribution for the following can be made via Responses and Reports ULNRC Distribution:

F. M. Diya D. W. Neterer L. H. Graessle T. E. Herrmann B.L.Cox M. A. McLachlan G. S. Kremer S. A. Maglio T. B. Elwood M.G. Hoehn Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)

Attachment to ULNRC-06182 TABLE OF ESTIMATED LICENSING ACTIONS CALLAWAY ENERGY CENTER UNIT 1 DOCKET NO. 05000483 LICENSING PROJECTED OUTAGE LICENSING RELATED?

ACTION LICENSING ACTION DESCRIPTION SUBMITTAL COMMENTS ACTION IF SO, DATE NUMBER DATE NEEDED 1 License License Renewal Application (LRA) to extend LRA and all No All correspondence for the LRA Renewal licensed operating life for Callaway an related has been submitted. NRC and Application for additional 20 years. correspondence ACRS review complete. Awaiting Callaway submitted. final Commission approval and (10 CFR 54) issuance of renewed License.

2 ASME Code ASME Code Relief Request 14R-02 to allow Submitted. Yes Ameren Missouri letter ULNRC-Relief Request less than 100% visual examination of Class 1 06176 submitted 1/26/2015.

(10 CFR supports. Needed for Refuel21 (Spring 50.55a(z)) 2016).

3 LAR License Amendment Request (LAR) for 3/2015 No (1 0 CFR 50.90) extension of the schedule for completing implementation of the Cyber Security Plan.

4 LAR License Amendment Request (LAR) for Steam 3/2015 Yes Needed for Refuel 21 (Spring (1 0 CFR 50.90) Generator Tube Inspection Program 2016).

relaxations per NRC-approved TSTF-51 0.

5 Relief Request Relief Request for limited coverage 3/2015 No Addresses inspections that were (1 0 CFR 50.55a) examinations performed during the third partially completed during the inservice inspection interval. third inservice inspection interval, (which ended on 12/19/2014).

6 LAR License Amendment Request (LAR) for 3/31/2015 Yes Needed for Refuel21 (Spring (1 0 CFR 50.90) revision of TS 5.6.5, "Core Operating Limits 2016).

Report (COLR)," to reflect updated Westinghouse DNB correlation.

Attachment to ULNRC-06182 LICENSING PROJECTED OUTAGE LICENSING RELATED?

ACTION LICENSING ACTION DESCRIPTION SUBMITTAL COMMENTS ACTION IF SO, DATE NUMBER DATE NEEDED 7 LAR License Amendment Request (LAR) to adopt 5/2015 No (10 CFR 50.59) TSTF-523 for incorporating Technical Specification provisions/requirements for gas (1 0 CFR 50.90) voiding in EGGS/Containment Spray piping (pursuant to GL 2008-01).

8 LAR License Amendment Request (LAR) for 8/2015 No (1 0 CFR 50.90) incorporating exception to Reg. Guide 1.106 (Rev. 1) into FSAR (regarding bypassing of thermal overload protection devices).

9 Relief Request Relief Request to use Code Case N-789, 2015 No This relief is being sought as a (1 0 CFR 50.55a) "Alternative Requirements for Sleeve contingency to provide additional Reinforcements of Class 2 and 3 Moderate alternatives for repair of Class 2 Energy Carbon Steel piping Section XI, or 3 moderate-energy carbon Division 1," for Class 2 and 3 moderate-energy steel raw water piping, should the raw water piping repairs due to degradation need arise.

mechanisms such as erosion, corrosion, cavitation or pitting.

10 Relief Request Relief Request to use the alternate root-mean- 2016 Yes Needed for Refuel 22 (Fall2017).

(1 0 CFR 50.55a) square depth sizing requirements for examination of the "C" cold leg elbow to safe-end weld. This request is similar to Relief Request ISI-33 used in the second and third inservice inspection intervals and is now essentially a request to use Code Case N-696-1, "Qualification Requirements for Appendix VIII Piping Examinations Conducted from the Inside Surface,Section XI, Division 1."

11 LAR New LAR to incorporate a new Technical 2016 No (1 0 CFR 50.90) Specification for Class 1E electrical equipment air conditioning (A/C) trains at Callaway. (Ref.

TAC Nos. ME7534 and ME9233) 12 LAR License Amendment Request (LAR) for 2016 Yes Needed for Refuel 22 (Fall 2017).

(10 CFR 50.90) revision of TS 5.6.5, "Core Operating Limits Report (COLR)," to reflect change in core reload methodology.

Attachment to ULNRC-06182 LICENSING PROJECTED OUTAGE LICENSING RELATED?

ACTION LICENSING ACTION DESCRIPTION SUBMITTAL COMMENTS ACTION IF SO, DATE NUMBER DATE NEEDED 13 Relief Request Relief Request for relief from N-770-1, 2016 Yes Needed for Refuel 22 (Fall 2017).

(10 CFR 50.55a) "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials,Section XI, Division 1," reactor vessel nozzle inspection intervals due to implementation of surface stress mitigation technique.

14 LAR License Amendment Request (LAR) to 2017 No (10 CFR 50.90) permanently establish a 15-year Type A (ILRT) test interval per NEI 94-01, Revision 3-A.

Includes revision of TS 5.5.16, "Containment Leakage Rate Testing Program."

15 LAR License Amendment Request (LAR) to resolve 2017 No (1 0 CFR 50.90) emergency diesel generator (EDG) frequency/voltage issue (based on WCAP-17308-NP).

16 LAR License Amendment Request (LAR) to adopt 2017 No (1 0 CFR 50.90) Risk-informed Technical Specification Task Force Initiative 4b for flexible Completion Times.

17 LAR License Amendment Request for revising F0 (Z) 2017 No (1 0 CFR 50.90) (TS 3.2.1) per WCAP-17661-P/NP (PA-LSC-0795).

18 Relief Request Relief Request to use ASME Section XI, 2017 No Will be needed prior to the end of (10 CFR 50.55a) Appendix VIII for examination of the reactor the fourth inservice inspection vessel-to-flange weld, as opposed to ASME interval.

Section V, Article 4. This is similar to Relief Request 13R-06 used during the third inservice inspection interval.

Attachment to ULNRC-06182 OUTAGE I

LICENSING PROJECTED LICENSING RELATED?

ACTION LICENSING ACTION DESCRIPTION SUBMITTAL COMMENTS ACTION IF SO, DATE NUMBER DATE NEEDED 19 Relief Request Relief Request to extend the inspection interval 2017 No Will be needed prior to the end of (1 0 CFR 50.55a) for Alloy 690 head penetrations currently the fourth inservice inspection defined in N-729-1 "Alternative Examination interval.

Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1." (EPRI Report MRP-375, "Technical Basis for Reexamination Interval Extension for Alloy 690 PWR Reactor Vessel Top Head Penetration Nozzles," to be used as technical basis).