05000219/LER-2006-002, Regarding Failure of MSIV Surveillance Due to Transcription Error
| ML062270440 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/07/2006 |
| From: | Rausch T AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-06-20372 LER 06-002-00 | |
| Download: ML062270440 (6) | |
| 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)(i)(B), Prohibited by Technical Specifications 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)(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 |
| 2192006002R00 - NRC Website | |
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AmerGen, M AmerGen Energy Company www.exeloncorp.Com An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 10 CFR 50.73 August 7, 2006 2130-06-20372 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Licensee Event Report 2006-002-00, Failure of MSIV Surveillance Due to Transcription Error Enclosed is Licensee Event Report 2006-002-00, Failure of MSIV Surveillance Due to Transcription Error. 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 Rich Milos, Regulatory Assurance at 609-971-4973 or Jim Frank, Engineering, at 609-971-4114.
Sincerely, noi*S. Rausch, Vice President Oyster Creek Generating Station
Enclosure:
NRC Form 366, LER 2006-002-00 cc:
Administrator, USNRC Region I USNRC Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 06038
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or digitstcharacters for each block) sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Oyster Creek, Unit 1 05000 219 1
OF 5
- 4. TITLE Failure of MSIV Surveillance Test Due to Transcription Error
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL IREV
- - ACILTY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO MONTH DAY YEAR 05000 06 20 2006 2006 002
- - 00 08 07 2006 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201 (b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
N 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(i)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 000 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below I
_or in (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)
Additional Information
A. Failed Components:
Main steam isolation valve NS04A (plant component ID V-1-9) was determined to be inoperable per surveillance test acceptance criteria.
B. Previous Similar Events
Oyster Creek Nuclear Generating Station has previously failed MSIV full closure surveillance tests. Of these previous failures all were identified in a timely manner and work performed to restore the respective valve's operability. No previous events at Oyster Creek have involved unknowingly starting the plant up with an MSIV inoperable.
C. Identification of Components Referred to in this Licensee Event Report:
Components IEEE 805 System ID Main Steam Isolation Valve (MSIV)
Plant Process Computer (PPC)
Reactor Protection System (RPS)
EIIS: SB EIIS: ID EIIS: JC IEEE 803A Function EIIC: RV EIIC: CPU EIIC: XC-RCT NRC FORM 366 (6-2004)