05000413/LER-2008-001, Re Auxiliary Feedwater Declared Inoperable Due to Inadequate Design and Configuration of Floor Drain Flow Restrictor Cover Plates
| ML080940127 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/31/2008 |
| From: | Pitesa J Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 08-001-00 | |
| Download: ML080940127 (10) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
| 4132008001R00 - NRC Website | |
text
Duke dEnergy JAMES R. MORRIS Vice President Catawba Nuclear Station 4800 Concord Rd. / CNO1VP York, SC 29745-9635 803 831 4251 803 831 3221 fax March 31, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Power Company LLC d/b/a/ Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Units 1 Docket Nos. 50-413 Licensee Event Report 413/08-001 Attached is Licensee Event Report 413/08-001 entitled "Auxiliary Feedwater Pumps Declared Inoperable Due to Inadequate Design and Configuration of Floor Drain Floor Restrictor Cover Plates."
There are no regulatory commitments contained in this letter.
This event is considered to be of no significance with respect to the health and safety of the public. If there are any questions about this report, please contact A. Driver at 803.701.3445.
Sincerely, John W. Pitesa Attachment LU~r~
www. duke-energy. corn
Document Control Desk Page 2 March 31, 2008 Xc (with attachment):
V.M. McCree, Acting, NRC Region II Administrator U.S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. J.F. Stang, Jr., NRC Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop O-H4A Washington, D.C. 20555 Mr. A.T. Sabisch, NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.E. Jenkins, Section Manager Division of Waste Management S.C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201
Document Control Desk Page 3 March 31, 2008
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INPO T.M. Hamilton G. Helton S.F. Hatley (EPIX)
MK. Green R.D. Hart J.R. Ferguson, Jr.
C.W. Trezise S.L. Nader S. Chisholm K.D. Thomas G.F. Winkle R.G. Hull B.G. Davenport K.L. Ashe B.J. Horsley M.J. Brown lerevents @ inpo.org Bxc (hard copy) (with attachment):
R.L. Gill L.F. Vaughn G.F. Winkle M.J. Sawicki A.D. Jones-Young Phillip Barrett A. Jackson L. J. Rudy ELL Master File CN-801.01 LER File RGC Data File NCMPA-1 NCEMC PMPA SREC
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- 3. PAGE Catawba Nuclear Station, Unit 1 05000 413 1 OF 7
- 4. TITLE Auxiliary Feedwater Pumps Declared Inoperable Due to Inadequate Design and Configuration of Floor Drain Flow Restrictor Cover Plates
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR Catawba 2 05000414 FACILITY NAME DOCKET NUMBER 01 30 2008 2008 001 00 03 31 2008
- 9. OPERATING
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
MODE 1
20.2201 (b) 20.2203(a)(3)(ii)
X 50.73(a)(2)(ii)(B)
,_ 50.73(a)(2)(ix)(A)
- 10. POWER 20.2201 (d) 20.2203(a)(4)
,50.73(a)(2)(iii)
,50.73(a)(2)(x)
LEVEL 1000%
20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A)
,73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A)
,50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2)
X 50.73(a)(2)(v)(B)
OTHER Specify in Abstract below or in
Abstract
On January 30,
- 2008, at 12:20 hours, with Unit 1 and Unit 2 operating at 100 percent power, the Auxiliary Feedwater (AFW) pumps
.were declared inoperable upon discovery of missing flow restrictor plates in the floor drains of the Unit 1 and Unit 2 interior doghouses.
The identified internal flood protection deficiencies were caused by inadequate design and configuration control during original plant design. The flood barriers were corrected by installation of flow restrictor cover plates for the floor drains in the interior doghouses.
The health and safety of the public were not affected by this event.
This event does involve a safety system functional failure.
NRC FORM 366 (9-2007)
(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
During the time period in question, there were no flooding events in the interior doghouses, thus the AFW pumps for each unit were available.
The health and safety of the public was not adversely affected by this event.
ADDITIONAL INFORMATION
In review of the Duke Energy Problem Investigation Process (PIP) database and LER events for the previous three years, the LER 413/06-002-00 "Safe Shutdown Potentially Challenged by an External Flooding Event and Inadequate Design and Configuration Control" was reviewed for similar cause codes to determine if this was a recurring event.
Upon the final root cause investigation of LER 413/08-001-00 and the causal factors associated with LER 413/06-002-00 it was found that the two events shared the same cause factor.
Although the two events share the same cause factor, the 2006 LER involved exterior flooding concerns while this LER involves interior flooding concerns.
The corrective actions taken in response to LER 413/06-002-00 would not have prevented this most recent event from occurring.
Therefore, this event was determined to be non-recurring in nature.
Energy industry Identification System [EIIS] codes are identified in the text as [EISS: XX].
This event is not considered reportable to the Equipment Performance and Information Exchange (EPIX)program.
This event is considered to be a Safety System Functional Failure.
There were no releases of radioactive materials, radiation exposures, or personnel injuries associated with this event.