ML071140173
| ML071140173 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 04/13/2007 |
| From: | Gordon Peterson Duke Power Co |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| RG-1.082, Rev 0 | |
| Download: ML071140173 (8) | |
Text
Duke GARY R. PETERSON
- Power, Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MGO1 VP / 12700 Hagers Ferry Rd.
Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy.com April 13, 2007 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-001
Subject:
Duke Power Company LLC d.b.a. Duke Energy Carolinas, LLC McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Response to a Request for Additional Information Regarding License Amendment Request Revising McGuire Units 1 and 2 Commitments to USNRC Regulatory Guide 1.82, Revision 0, "Sumps For Emergency Core Cooling and Containment Spray Systems" and Revising McGuire Units 1 and 2 Technical Specification Surveillance Requirement (SR) 3.5.2.8 and Associated Bases (TACs MD 4748 and 4749)
Please find the Duke Power Company LLC d.b.a. Duke Energy Carolinas, LLC (Duke) response to the Request for Additional Information (RAI) transmitted electronically on April 9, 2007. The License Amendment Request was originally submitted by letter dated March 8, 2007. The RAI responses are included as Enclosure 1 to this letter.
There are no regulatory commitments contained in this letter or the associated enclosure.
Please direct any questions you may have in this matter to K. L. Ashe at (704) 875-4535.
Very truly yours, G. ZRerson xc w/ Attachments:
www. dukepower. com
April 13, 2007 Nuclear Regulatory Commission Page 2 W. D. Travers Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, Suite 23T85 Atlanta, GA 30303 J. F. Stang, Jr. (addressee only)
NRC Senior Project Manager (MNS)
U.S. Nuclear Regulatory Commission Mail Stop 0-8 H4A Washington, DC 20555-0001 J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station B. 0. Hall, Senior Chief Division of Radiation Section 1645 Mail Service Center Raleigh, NC 27699-1645
April 13, 2007 Nuclear Regulatory Commission Page 3 Gary R. Peterson affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowled e.
Gary. R. Peterson, Vice President, McGuire Nuclear Station Subscribed and sworn to me: 13, ?0oo0-Date Notary Public My commission expires: ( 0" acoB Date
Enclosure 1 Response to NRC Request for Additional Information License Amendment Request Revising McGuire Units 1 and 2 Commitments to USNRC Regulatory Guide 1.82, Revision 0, "Sumps for Emergency Core Cooling and Containment Spray Systems" and Revising McGuire Units 1 and 2 Technical Specification Surveillance Requirement (SR) 3.5.2.8 and Associated Bases (TACs MD 4748 and 4749)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
- 1. Licensee's response, dated March 27, 2007 to RAI in Licensee's Attachment A (page 1 of 4) states that a new rupture restraint and jet barrier is required to protect the sump screen from these (RHR line) postulated breaks. On page 24 of 44 of Licensee's attachment #3 (Dukes evaluation of LAR) and page 1 of 1 of Licensee's Attachment #5 (Regulatory Commitments) address installation of pipe rupture restraint in RHR system, and not the new jet barrier mentioned above. Provide clarification whether the new jet barrier is the ICW stainless steel enclosure for the strainer assembly inside crane wall.
Response
The RHR rupture restraint and jet barrier is one integrated structure. The ICW enclosure is not credited as a jet barrier.
- 2. Page 24 of 44 of Licensee's Attachment #3 (Dukes evaluation of LAR):
Are the drawing reviews and evaluations made for pipe whip and jet impingement documented in calculations, documents, or reports? Provide reference by citing the specific document numbers.
Response
The evaluation documentation is part of the Modification package (Unit 1 Mod package MD1 00374). A summary of the pipe whip and jet impingement evaluation for Unit 1 is provided as Appendix 1 below, Unit 2 is similar. Please note that Pipe Break IDs ND01-54, ND01 -57 and ND01-58 in Appendix 1 represent the commitment made in Attachment 5 of our March 8, 2007 letter requesting the License Amendment.
- 3. Page 30 of 44 of Licensee's Attachment #3 (Dukes evaluation of LAR):
Provide the reference or basis for 10 psid load for the design of sump strainer modules. Also, specify or summarize all of the load components, such as seismic loads, strainer assembly weight, debris weight, hydrodynamic mass, thermal loads, loads due to differential pressure or head loss used in the structural design of the ECCS sump strainer assembly. Also, include a reference of the sump strainer structural design calculation establishing its design adequacy.
Response
The qualification of the subcomponent (sump strainer modules - top hat) for a 10 psid load is contained in Enercon analysis DUK008-CALC-01 Rev 1, Analysis of Sump Strainer Top Hat Unit 1, and Enercon analysis DUK007-CALC-01 Rev 2, Analysis of Sump Strainer Top Hat Unit 2.
Page 1 of 4
The sump strainer assembly is designed to include consideration of the following load types:
Seismic (horizontal and vertical accelerations), dead weights, operating loads (differential pressure and live loads, where applicable), thermal expansion, buoyancy, and pipe support load where applicable. These are documented in Enercon calculations, DUK008-CALC-02 (Sump Strainer Structure Located Inside Crane Wall), DUKE008-CALC-03 (Sump Strainer Structure Located in Original ECCS Sump Area), DUKE008-CALC-05 (Sump Strainer Enclosure Structure Located Inside Crane Wall), and DUK008-CALC-06 (Vortex Suppression Structure).
Enercon has an accepted Appendix B QA program to perform calculations and analyses, in addition, Duke accepts the Enercon products through our Appendix B QA Program. The verification of final design adequacy will be completed in accordance with these programs after chemical effects have been evaluated and incorporated into the design.
Page 2 of 4
Appendix 1 Unit 1 Postulated Pipe Breaks Near ECCS Sumps (Inside Containment, Pipe Chase, & Annulus)
Composite Pipe Break ID Description ID 2 BB-01 -34 Break is at elevation 731'- 7". Pipe whip and jet spray act in horizontal plane, therefore ECCS components are not targets.
Reference Attachments # 1 & 2.
6 BB-02-01 Break is at elevation 748'- 7 9/16". Pipe whip and jet spray act in horizontal plane, therefore ECCS components are not targets.
Reference Attachment # 3.
7 BB-02-26 Break is at elevation 728'- 0". Pipe whip and jet spray act in vertical plane on containment side of crane wall. ECCS components are not targets. Reference Attachment # 4.
8 BB-03-51 Break is at elevation 728'- 0". Pipe whip and jet spray act in horizontal plane on containment side of crane wall. ECCS components are not targets. Reference Attachment # 6.
9 BB-03-64 Break is at elevation 748'- 7 9/16", and a rupture restraint is provided (existing).
13/389 BB-04-42/NM- Break is at elevation 731'- 3", and rupture 04-21 D restraints are provided (existing).
381 NM-02-X3 Break is at elevation 728'- 0". Pipe whip and jet spray act in vertical plane on pipe chase side of crane wall. ECCS components are not targets. Reference Attachment # 5.
384 NM-03-X7 Break is at elevation 728'- 0". Pipe whip and jet spray act in vertical plane on pipe chase side of crane wall. ECCS components are not targets. Reference Attachment # 7.
385 NM-03-B32 Break is at elevation 734'- 1". Pipe whip and jet spray act in horizontal plane in the pipe chase. Pipe whip and jet act in vertical plane (upward) in the annulus. ECCS components are not targets. Reference Attachments # 8
&9. 1 461 SM1-05R Break is at elevation 809'-0 9/16", and a rupture restraint is provided (existing).
462 SM1-06R Break is at elevation 760'-6", and rupture restraints are provided (existing).
464 SM1-08R Break is at elevation 809'-0 9/16", and a rupture restraint is provided (existing).
Page 3 of 4
Appendix 1 Unit 1 Postulated Pipe Breaks Near ECCS Sumps (Inside Containment, Pipe Chase, & Annulus)
Composite Pipe Break ID Description ID 465 SM1-09R Break is at elevation 760'-6", and rupture restraints are provided (existing).
10 BB-03-3 Break is at elevation 748'-7 9/16". Pipe whip and jet spray act in vertical plane. ECCS components are not targets. Reference Attachment # 25.
33 CAl-02R Break is at elevation 786'-8 9/16", and rupture restraints are provided (existing).
34 CA1-03R Break is at elevation 786'-8 9/16", and rupture restraints are provided (existing).
92 NC01-15 Break is at elevation 740-2 1/2"", and rupture restraints are provided (existing).
314 ND01-3 Break is at elevation 741'-8 5/8", and rupture restraints are provided (existing).
315 ND01-54 This break is in close proximity to breaks ND01 -57 & 58. Rupture restraints are provided for breaks "57 & 58", but they protect targets above the piping. ECCS components ARE targets of jet impingement.
Impingement plates incorporated in to the design of the rupture restraint. Reference Attachment # 26.
316 ND01 -57 Break is at elevation 737'-2 7/16", and rupture restraints are provided.
317 ND01 -58 Break is at elevation 737'-2 7/16", and a rupture restraint is provided, but it protects targets above the piping. ECCS components ARE targets of jet impingement.
Impingement plates incorporated in to the design of the rupture restraint. Reference Attachment # 26.
378 NM02-2 Break is at elevation 787'-0 5/8". ECCS components are not targets of pipe whip or jet spray.
386 NM03-NI Break is at elevation 787'-0 5/16". ECCS components are not targets of pipe whip or jet spray.
460 SM1-04R Break is at elevation 809'-0 9/16", and rupture restraints are provided (existing).
463 SM1-07R Break is at elevation 809'-0 9/16", and rupture restraints are provided. (existing).
Page 4 of 4