ULNRC-06033, Proposed Revision to Final Safety Analysis Report FSAR-SP Section 3.7(B) & 3.7(N), Seismic Design, (License Amendment Request LDCN 12-0041)
| ML13242A241 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/29/2013 |
| From: | Abel S Ameren Missouri, Union Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MF0407, ULNRC-06033 | |
| Download: ML13242A241 (9) | |
Text
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WAmeren MISSOURI Callaway Plant August 29,2013 ULNRC-06033 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen:
10 CFR 50.90 10 CFR 50.59( c )(2)(viii)
DOCKET NUMBER 50-483 CALLA WAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF -30 PROPOSED REVISION TO FINAL SAFETY ANALYSIS REPORT FSAR-SP SECTIONS 3.7(B) & 3.7(N), "SEISMIC DESIGN" (LICENSE AMENDMENT REQUEST LDCN 12-0041) (TAC NO. MF0407)
References:
- 1) ULNRC-05941 dated December 20, 2012
- 2) NRC Letter, "Callaway Plant, Unit 1 -Request for Additional Information Re: Proposed Revision to FSAR-SP Sections 3.7(B) and 3.7(N), "Seismic Design" {TAC No. MF0407) dated August 9, 2013
- 3) ULNRC-05998 dated June 6, 2013 By the Reference 1letter, Union Electric Company (Ameren Missouri) submitted a proposed amendment that would revise a methodology in the licensing basis, as described in the Final Safety Analysis Report - Standard Plant (FSAR-SP), to include damping values for the seismic design and analysis of the integrated head assembly (IHA) that are consistent with the recommendations of Regulatory Guide (RG) 1.61, Revision 1 "Damping Values for Seismic Design of Nuclear Power Plants." Reference 2 dated August 9, 2013 transmitted a Request for Additional Information (RAI) related to our application. contains Ameren Missouri's response to the request contained in the August 9, 2013 RAI.
A clarification is hereby provided for the response that was provided by Reference 3. Specifically, Callaway's response to RAI EMCB-Callaway-IHA-RAI-7 stated the design basis code of record for the existing Seismic Category I CRDM seismic support assembly for the existing equipment is the 1977 Edition with Addenda through Summer 1977 of ASME Section III, Subsection NF (Class 1 ).
PO Box 620 Fulton, MD 65251 AmerenMissouri.com
ULNRC-06033 August 29,2013 Page 2 Through further discussions with Westinghouse, it was found the design basis code of record used in the final as-built stress report for the Seismic Category I CRDM seismic support assembly for the existing equipment is actually the 1977 Edition of ASME Section III, Subsection NF (Class 1) with no Addenda.
It should be noted that this letter does not contain new commitments.
Please contact Scott Maglio, Regulatory Affairs Manager, at (573) 676-8719 for any questions you may have regarding this amendment application.
I declare under penalty of perjury that the foregoing is true and correct.
Sincerely,
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Shannon L. Abel Director Engineering Projects DS/nls
Enclosure:
- 1) Response to Request for Additional Information License Amendment Request to Revise the Licensing Basis for Seismic Design as Described in the FSAR -SP
ULNRC-06033 August 29, 2013 Page 3 cc:
U.S. Nuclear Regulatory Commission (Original)
Attn: Document Control Desk Washington, DC 20555-0001 Mr. Steven A. Reynolds Acting 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
ULNRC-06033 August 29, 2013 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 Tech Spec ULNRC Distribution:
A. C. Heflin F. M. Diya C. 0. Reasoner III B.L.Cox D. W. Neterer L. H. Graessle S. L. Abel J. S. Geyer S. A. Maglio B. C. Daniels NSRB Secretary T. B. Elwood G. G. Yates STARS Regulatory Affairs Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)
Missouri Public Service Commission Ms. Leann Tippitt-Mosby (DNR)
T. W. Pettus W. P. Muskopf
ULNRC-06033 August 29, 2013 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Page 1 of 5 LICENSE AMENDMENT REQUEST TO REVISE THE LICENSING BASIS FOR SEISMIC DESIGN AS DESCRIBED IN THE FSAR-SP UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483
ULNRC-06033 August 29, 2013 Page 2 of 5 By application dated December 20, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13002A370), as supplemented by letter dated June 6, 2013 (ADAMS Accession No. ML13158A009), to the U.S. Nuclear Regulatory Commission (NRC),
Union Electric Company (dba Ameren Missouri, the licensee) submitted a license amendment request to revise a methodology in the licensing basis as described in the Final Safety Analysis Report -Standard Plant (FSAR-SP) to include damping values for the seismic design and analysis of the integrated head assembly that are consistent with the recommendations of NRC Regulatory Guide 1.61,.. Damping Values for Seismic Design of Nuclear Power Plants,..
Revision 1, March 2007.
The NRC staff has determined that the additional information requested below is needed to complete its review.
Mechanical and Civil Engineering Branch (EMCB)-Callaway-IHA-RAI-9 In section 3.1 (paragraph 2, page 6) of the letter dated December 20, 2012, the licensee indicated that the replacement reactor vessel closure head (RRVCH) includes a new structure called Integrated Head Assembly (IHA) that incorporates the functions of the former control rod drive mechanism (CRDM) seismic support structure, the CRDM ventilation cooling system, and the head lift rig. As a result of the new IHA structure, the licensee is requested to clarify the following items:
(a)
Are there any changes required to the CRDM system and its supports?
(b)
Is a re-analysis of the ASME class 1 CRDM system required?
(c)
If re-analysis of the CRDM system is required, please provide (i) the damping values used in the original CRDM class 1 analysis and in the re-analysis, (ii) a summary of the results (primary stresses, primary plus secondary stress intensity range, and cumulative usage factor (CUF) along with allowable limits based on the applicable code edition) from the original analysis and reanalysis for the critical locations such as CRDM latch housing, CRDM travel housing, CRDM nozzle between top of head and dissimilar metal weld, and CRDM nozzle at J-groove weld.
Callaway Response (a)
There are changes to the CRDM and supports. For example, the replacement CRDM housing is a two piece design compared to the original CRDM three piece design; and the number of tie rods restraining the CRDM seismic support structure has been reduced from six to four.
(b)
A re-analysis of the ASME Class 1 CRDM is required as a result of the changes in the CRDM design and support structure.
(c)
Although a reanalysis of the CRDM was required; the seismic analysis damping value used in the re-analysis is 5°AI (for OBE and SSE) which is the same as what was used in the original CRDM Class 1 analysis and is described in Callaway FSAR section 3. 7 (N).1.3. The LOCA analysis damping value used in the re-analysis is 4°AI which is also
ULNRC-06033 August 29, 2013 Page 3 of 5 the same as what was used in the original CRDM Class 1 analysis; however this was not previously described in the Callaway FSAR.
A summary of available results (primary stresses, primary plus secondary stress intensity range, and cumulative usage factor (CUF) along with allowable limits based on the applicable code edition) from the original analysis and reanalysis for the critical locations such as CRDM latch housing, CRDM travel housing, CRDM nozzle between top of head and dissimilar metal weld (DMW), and CRDM nozzle at J-groove weld are provided in Tables 1 and 2 respectively.
ULNRC-06033 August29,2013 Page 4 of 5 Table 1 Callaway Original CRDMs Results of ASME Code Stress Evaluation Load ASME Classification Combination Rod Travel HousinQ Design Pm Rod Travel HousinQ Design PI+ Pb Rod Travel HousinQ OBE Moment Rod Travel HousinQ Faulted Moment Latch HousinQ Design Pm Latch Housing Design PI+ Pb Latch Housing OBE Moment Latch Housing Faulted Moment CRDM Nozzle Design Pm CRDM Nozzle Design PI+ Pb CRDM Nozzle OBE Moment CRDM Nozzle Faulted Moment CRDM Nozzle Design Pm CRDM Nozzle Design PI+ Pb CRDM Nozzle Faulted Pm CRDM Nozzle Faulted PI+ Pb CRDM Nozzle Normal & Upset P+Q CRDM Nozzle Normal & Upse~t _ ~.-
CUF Notes:
- CRDM Nozzle between head and dissimilar metal weld
Where:
Pm = Primary Membrane Stress Intensity PI + Pb = Primary Membrane + Primary Bending Stress Intensity P + Q =Primary+ Secondary Stress Intensity Range CUF =Fatigue Cumulative Usage Factor Calculated Value 11.477 ksi 15.441 ksi 26.167 in-kips 121.428 in-kips 12.861 ksi 15.023 ksi 47.634 in-kips 124.660 in-kips 7.157 ksi 9.203 ksi 64.013 in-kips 178.348 in-kips 6.75 ksi 27.575 ksi 8.40 ksi 34.33 ksi 59.0 ksi 0.109 Allowable Value 16.1 ksi 24.15 ksi 89.675 in-kips 231.580 in-kips 16.1 ksi 24.15 ksi 245.513 in-kips 702.233 in-kips 16.1 ksi 24.15 ksi 110.000 in-kips 240.000 in-kips 23.3 ksi 34.95 ksi 39.0 ksi 83.8 ksi 69.9 ksi 1.0
ULNRC-06033 August 29, 2013 Page 5 of 5 Location CRDM Latch Housing CRDM Travel Housing CRDM Nozzle between Head and DMW CRDM Nozzle at J-Groove Weld Design Table 2 Callaway Replacement CRDMs Results of ASME Code Stress Evaluation Faulted<,,
Pm [ksi]
PI+ Pb [ksi]
Pm [ksi]
PI+ Pb [ksi]
Actual Allow Actual Allow Actual Allow Actual Allow 14.32 16.2 21.06 24.3 25.83 37.9 34.45 56.9 11.72 16.2 16.99 24.3 16.07 37.9 25.35 56.9 10.98 23.3 30.17 34.9 19.56 55.9 73.96 83.8 9.27 23.3 30.73 34.9 16.1 55.9 72.79 83.8 L_
- - - L__
(1) Faulted loads include SSE and LOCA combined Where:
Pm:
Primary Membrane Stress Intensity PI+Pb:
Primary Membrane+ Primary Bending Stress Intensity P+Q:
Primary+ Secondary Stress Intensity Range U:
Fatigue Usage Factor DMW: Dissimilar Metal Weld Normal & Upset P+Q [ksi]
Actual Allow Actual 41.03 48.4 0.061 41.24 48.4 0.005 39.06 69.9 0.0003 69.63 69.9 0.618 u
Allow 1.0 1.0 1.0 1.0