ML061100413
| ML061100413 | |
| Person / Time | |
|---|---|
| Site: | Oconee  (DPR-038, DPR-047, DPR-055) |
| Issue date: | 04/06/2006 |
| From: | Brandi Hamilton Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-04-002 | |
| Download: ML061100413 (8) | |
Text
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_Duke BRUCE H HAMILTON Vice President rOPowfere Oconee Nuclear Station Duke Power ONO1VP / 7800 Rocterster Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax April 6, 2006 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
Oconee Nuclear Station Docket Number 50-287 Supplement to License Amendment Request associated with New Reactor Building Emergency Sump (RBES)
Strainers, TSC Number 2004-08 This is a supplement to the License Amendment Request (LAR) submitted by Oconee Nuclear Station (ONS) on August 18, 2005.
In that submittal, ONS proposed to amend Appendix A, Technical Specifications (TS), for Renewed Facility Operating Licenses DPR-38, DPR-47 and DPR-55 for ONS Units 1, 2, and 3. The proposed change to Technical Specification (TS) Surveillance Requirement (SR) 3.5.2.6 and SR 3.5.3.6 removed reference to 1"trash racks and screens" and replaced this terminology with the word "strainers".
The intent of the request was to make the TS surveillance wording consistent with the as-built configuration which will exist after one or more replacement strainers are installed in response to Generic Letter 2004-02.
On November 1, 2005, NRC approved the request for Units 1 and 2, and issued amendments 348 and 350 to Renewed Facility Operating Licenses DPR-38 and DPR-47 respectively. NRC withheld approval for Unit 3 pending ONS' completion of (and NRC acceptance of) evaluation of the impact of pipe whip, jet impingement, and missile generation for Unit 3. The amended TS pages provided by the NRC along with the.approved amendments for Units 1 and 2 did not accurately reflect the status of Unit 3. Therefore, after conferring with the NRC, ONS made an administrative change to create two versions of the affected pages for implementation.
Thus the affected pages, 3.5.2-5 and 3.5.3-3, became 3.5.2-5a, 3.5.2-5b, 3.5.3-3a, and 3.5.3-3b. Pages 3.5.2-5a and 3.5.3-3a are applicable to Units 1 and 2, and pages 3.5.2-5b and 3.5.3-3b are applicable to Unit 3. These pages were provided to NRC by letter of January 5, 2006.
A-0° www.dukepower.com
U. S. Nuclear Regulatory Commission April 6, 2006 Page 2 The evaluations requested in your November 1, 2005 letter are now completed and owner-approved.
The evaluations concluded that there are no adverse effects on the post-accident function of the new RBES strainers resulting from jel: impingement, pipe whip, or internally generated missiles.
Copies of the approved analyses were provided to NRC (Mr. Lenny Olshan) by email on March 27, 2006.
Th:is supplement to the August 18, 2005 LAR, requests approval of that amendment request for Unit 3. The Technical Specification retyped pages submitted with that request are applicable to this supplement as well.
These pages are provided in Attachment 1.
The following conclusions from the August 18, 2005 LAR remain unchanged:
- 1) Implementation of these changes will not result in an undue risk to the health and safety of the public.
- 2) There are no significant hazards associated with the supplement.
- 3) There are no adverse environmental effects associated with the supplement.
Pursuant to 10 CFR 50.91, a copy of this supplement is being sent to the South Carolina Department of Health and Environmental Control.
Approval of this LAR supplement is requested by April 28, 20016 to support the upcoming Unit 3 refueling outage. ONS requests an implementation period of 60 days.
If there are any additional questions, please contact Russell Oakley at (864) 885-3829.
Very truly yours,
/V Bruce H. Hamilton, ice President Oconee Nuclear Site
U. S. Nuclear Regulatory Commission April 6, 2006 Page 3 cc:
Mr.
L.
N. Olshan, Project Manager Office of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C.
20555 Dr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission -
Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. C. Shannon Senior Resident Inspector Oconee Nuclear Station Mr. Henry Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201
U. S. Nuclear Regulatory Commission April 6, 2006 Page 4 Bruce H. Hamilton, being duly sworn, states that he is Vice President, Oconee Nuclear Site, Duke Energy Corporation, that he is authorized on the part of said Company to sign and file with the U. S. Nuclear Regulatory Commission this revision to the Renewed Facility Operating License No. DPR-55 and that all the statements and matters set forth herein are true and correct to the best of his knowledge.
Bruce H. Hamilton, Vice President Oconee Nuclear Site Sp)scribed and sworn to before me this day of t
2006 i
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U. S. Nuclear Regulatory Commission April 6, 2006 Page 5 bcc: w/attachments B.
Graham Davenport T.
P. Gillespie Robert L. Medlin Lisa F. Vaughn Paul M. Stovall David B. Coyle Steven D. Capps Robert L. Gill -
NAID Randall D. Hart -
CNS Charles J. Thomas -
MNS NSRB, EC05N ELL, ECO50 File -
T.S. Working BWOG Tech Spec Committee (5)
ONS Document Management Reene' V. Gambrell
U. S. Nuclear Regulatory Commission April 6, 2006 ATTACHMENT 1 TECHNICAL SPECIFICATION CHANGES Remove Page Insert Page 3.5.2-5a 3.5.2-5b 3.5.3-3a 3.5.3-3b 3.5.2-5 3.5.3-3
.3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify each HPI pump's developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing Program required developed head.
SR 3.5.2.4 Verify each HPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.5.2.5 Verify each HPI pump starts automatically on 18 months an actual or simulated actuation signal.
SR 3.5.2.6 Verify, by visual inspection, each HPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet strainers show no evidence of structural distress or abnormal corrosion.
SR 3.5.2.7 Cycle each HPI discharge crossover valve and 18 months LPI-HPI flow path discharge valve.
OCONEE UNITS 1,2, & 3 3.5.2-5 Amendment Nos.
1.
LPI 3.5.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.3.2
NOTE-------------------------
Not applicable to operating LPI pump(s).
Vent each LPI pump casing.
31 days SR 3.5.3.3 Verify each LPI pump's developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing required developed head.
Program SR 3.5.3.4 Verify each LPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.5.3.5 Verify each LPI pump starts automatically on 18 months an actual or simulated actuation signal.
S R 3.5.3.6 Verify, by visual inspection, each LPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet strainers show no evidence of structural distress or abnormal corrosion.
OCONEIE UNITS 1, 2, & 3 3.5.3-3 Amendment Nos.