05000287/LER-2009-001, For Oconee, Unit 3, Regarding Two Pals CIVs Inoperable Due to Use of Unqualified Seat Material
| ML090480080 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/10/2009 |
| From: | Baxter D Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 09-001-00 | |
| Download: ML090480080 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 2872009001R00 - NRC Website | |
text
Duke DAVE BAXTER Duker Vice President "Energy Oconee Nuclear Station Duke Energy Corporation ON01 VP17800 Rochester Highway Seneca, SC 29672 864-885-4460 864-885-4208 fax February 10, 2009 dabaxter@dukeenergy.com U.S. Nuclear Regulatory, Commission Document Control Desk Washington, D.C.
20555
Subject:
Oconee Nuclear Station Docket No. 50-287 Licensee Event Report 287/2009-01, Revision 0 Problem Investigation Process No.: 0-08-8339 Gentlemen:
Pursuant to 10 CFR 50.73 Sections (a) (1) and (d),
attached is Licensee Event Report 287/2009-01, Revision 0, regarding inoperability of two containment isolation valves in the Post-Accident Liquid Sampling System.
This report is being submitted in accordance with 10 CFR 50.73 (a) (2) (i) (B).
This event is considered to be of no significance with respect to the health and safety of the public.
There are no regulatory commitments contained in this report.
Any questions regarding the content of this report should be directed to Russ Oakley at 864-885-3829.
Very truly yours, Dave Baxter, Vice President Oconee Nuclear Site Attachment www. duke-energy. cornm-
Document Control Desk Date: February 10, 2009 Page 2 cc:
Mr. Luis Reyes Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S.
W.,
Suite 23T85 Atlanta, GA 30303 Mr.
John Stang Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Mr. Andy Hutto NRC Senior Resident Inspector Oconee Nuclear Station INPO (Word File via E-mail)
NRC FdRM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO, 3150-0104 EXPIRES: 08/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Oconee Nuclear Station, Unit 3 05000287 1 OF 4
- 4. TITLE Two PALS CIVs Inooerable Due to Use of Unaualified Seat Material
- 5. EVENT DATE
- 6. LER NUMBER __
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NoneIT 05000CETNUBE NUMBER NO.
ne 0000 FACILITY NAME DOCKET NUMBER 12 12 2008 2009 -
01 0
02 10 2009 None 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[1 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1E 20.2201(d)
[: 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
"El 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
El 50..73(a)(2)(viii)(B)
__ 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
Ml 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100%
[1 20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
Z 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (f more space is required, use additional copies of NRC Form 366A)
- 1) Confirmed that the condition did not exist on equivalent valves installed in the Unit 1 and 2 PALS system.
These valves (l&2RC-164&165) are hard'-seated designs which are not susceptible to the same failure modes as the soft-seated design.
Planned:
SAFETY ANALYSIS
This event did not include a loss of' safety system function.
Since 3RC-162 and 3RC-163 have hard seat materials which would not be degraded by exposure to high temperature and pressure conditions associated with sampling activity, these valves would have been capable of performing the containment isolation safety function.
These are normally-closed valves which are re-closed by procedure following post-accident sampling evolutions.
Since there was no loss of safety function, there was no impact on core damage frequency.
No fission product barriers were compromised by this event.
Therefore, there was no actual impact on the health and safety of the public due to this event.
ADDITIONAL INFORMATION
A search of Oconee's corrective action database found no similar occurrences of this type of eventwith same cause.
There were no releases of radioactive materials, radiation exposures or personnel injuries associated with this event.
Energy Industry Identification System (EIIS) codes are identified in the text within brackets [].
This event is not considered reportable under the Equipment Performance and Information Exchange (EPIX) program.