05000219/LER-2009-002, Failure to Take the Appropriate Tech Spec Action When Primary Containment Isolation Valve Became Inoperable
| ML091000290 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/31/2009 |
| From: | Rausch T Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-09-028 LER 09-002-00 | |
| Download: ML091000290 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(viii)(B) 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), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2192009002R00 - NRC Website | |
text
Exelý,n@
Oyster Creek Generating Station www.exe]oncorp.com Nuclear Route 9 South PO Box 388 Forked River, NJ 08731 10 CFR 50.73 March 31, 2009 RA-09-028 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-1 6 NRC Docket No. 50-219
Subject:
Licensee Event Report (LER) 2009-002-00, Failure to Take the Appropriate Tech Spec Action when Primary Containment Isolation Valve Became Inoperable Enclosed is Licensee Event Report 2009-002-00, Failure to Take the Appropriate Tech Spec Action when Primary Containment Isolation Valve Became Inoperable. This event did not affect the health and safety of the public or plant personnel. This event did not result in a safety system functional failure. There are no new regulatory commitments made in this LER submittal.
If any further information or assistance is needed, please contact James Barstow, Regulatory Assurance Manager at 609-971-4947.
Sincerely, Tý.
uch Vice President, Oyster Creek Nuclear Generating Station
Enclosure:
NRC Form 366, LER 2009-002-00 cc:
Regional Administrator, USNRC Region I USNRC Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 09053
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 19-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the infnrmatinn nollection.
- 3. PAGE Oyster Creek, Unit 1 05000219 1 OF 3
- 4. TITLE Failure to Take the Appropriate Tech Spec Action when Primary Containment Isolation Valve Became Inoperable
- 5. EVENT DATE
- 6. LER NUMBER J
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH
" DAY YEAR YEAR NUMBER NO.
I FACILTYNAME DOCKET NUMBER NSEQUENTIAL REVN MONTH DAY YEAR N/A N/A FACILITY NAME DOCKET NUMBER 02 02 2009 2009 002 001 03 31 2009 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[j 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
E: 50.73(a)(2)(vii)
N El 20.2201(d)
[l 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)
El 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) nl 50.36(c)(1)(ii)(A)
[I 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
[E 20.2203(a)(2)(iii)
E: 50.36(c)(2)
El 50.73(a)(2)(v)(A)
E] 73.71 (a)(4) 000 [j 20.2203(a)(2)(iv)
[1 50.46(a)(3)(ii)
[I 50.73(a)(2)(v)(g)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
[D 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in
Corrective Actions
Operating crews were briefed on this event. The fundamental of a questioning attitude was reinforced with all operators to ensure the proper technical rigor is applied when issues are identified.
Previous Occurrences
There have been no similar Licensee Event Report events at Oyster Creek in the last three years.
Component Failure Data
Component: RWCU System Trip Control Relay Manufacturer: General Electric Model No.# CR120AD04241AA
Cause
High Contact Resistance