05000219/LER-2006-003, Re Local Leak Rate Test Results in Excess of Technical Specifications
| ML063530472 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/13/2006 |
| From: | Rausch T AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-06-20436 LER 06-003-00 | |
| Download: ML063530472 (5) | |
| 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)(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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2192006003R00 - NRC Website | |
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AmerGenm 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 December 13, 2006 2130-06-20436 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 2006-003-00, Local Leak Rate Test Results in Excess of Technical Specifications Enclosed is Licensee Event Report 2006-003-00, Local Leak Rate Test Results in Excess of Technical Specifications. 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 Laura Velez, Engineering, at 609-971-4410.
Sincerely, thy S. Rausch, Vice President Oyster Creek Generating Station
Enclosure:
NRC Form 366, LER 2006-003-00 cc:
Administrator, USNRC Region I USNRC Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 06049 jz_2
NRC F$)RM 366' U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or digits/characters 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 4
- 4. TITLE Local Leak Rate Test Results in Excess of Technical Specifications....
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO MONTH DAY YEAR 05000 10 16 2006 2006 003 00 12, 13 2006 FACILITY NAME DOCKET NUMBER j._'_.______
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)(ii)(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) 0 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 II 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 NRC Form 366A)
Corrective Actions
Strain Gauge diagnostic testing on NS03B was performed on October 22, 2006 to confirm total seating force, pilot poppet spring force, backseating force, open and closed packing loads, main seat disc contact profile, pilot poppet disc seat contact profile, main disc guide condition, main disc nose guide bore transition profile and total seating force. This test result was satisfactory.
Performance of an as-left LLRT following the diagnostic stroke and work on the NS04B to demonstrate that the leakage on the NSO3B remains acceptable. This test result was satisfactory giving a value of 2.416 scfh at 21.46 psig between the valves, well below our acceptance criteria of 11.9 scfh at 20 (+3/-0) psig.
Additional Information
A. Failed Components:
Main Steam Isolation Valve (MSIV) NS03B (V-1-008)
B. Previous similar events
LER 2000-010, Local Leak Rate Test Results in Excess of Technical Specifications, NS04B LER 2002-002, Local Leak Rate Test Results in Excess of Technical Specifications, NS03A LER 2004-005, Local Leak Rate Test Results in Excess of Technical Specifications, NS03A LER 2004-006, Local Leak Rate Test Results in Excess of Technical Specifications, NS04A C.
Identification of components referred to in this Licensee Event Report:
Components MSIV IEEE 805 System ID SB IEEE 803A Function ISV