05000219/LER-2006-001, Regarding Unplanned Manual Scram Inserted During Planned Reactor Shutdown to Expedite Plant Cooldown
| ML061880302 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/05/2006 |
| From: | Randich J AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-06-20357 LER 06-001-00 | |
| Download: ML061880302 (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)(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 |
| 2192006001R00 - NRC Website | |
text
AmerGen.
AmerGen Energy Company www.exeloncorp.com An Exelon Company Oyster Creek US Route 9 South, RO. Box 388 Forked River, NJ 08731-0388 10 CFR 50.73 July 5, 2006 2130-06-20357 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 2006-001-00, Manual Scram Inserted During Planned Reactor Shutdown to Expedite Plant Cool-down Enclosed is Licensee Event Report 2006-001-00, Manual Scram Inserted During Planned Reactor Shutdown to Expedite Plant Cool-down. 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 Jeff Dostal, Operations, at 609-971-4572.
Sincerely, Plant Manager, Oyster Creek Generating Station
Enclosure:
NRC Form 366, LER 2006-001-00 cc:
Administrator, USNRC Region I USNRC Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 06035
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/3012007 (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.
PAGE Oyster Creek, Unit 1 05000 219 1
OF 3
- 4. TITLE Unplanned Manual Scram Inserted During Planned Reactor Shutdown to Expedite Plant Cooldown
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBERI NO MONTH DAY IYEAR 105000 05 06 2006 2006 001
- - 00 07 05 2006 FACILITYNAME DOCKET NUMBER
_ L 1
105000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
N 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)
X 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
<1%
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) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below I
I_
I I or in (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
Corrective Actions
(1) Repaired the leaking tubes in the SPE Cooling Condenser.
(2) Performed a Root Cause Evaluation to prevent recurrence.
Additional Information
A. Failed Components:
The Steam Packing Exhauster Cooling Condenser failed and was the cause for entering the Forced Outage.
B. Previous similar events
None C. Identification of components referred to in this Licensee Event Report:
Components IEEE 805 System ID IEEE 803A Function Steam Packing Exhauster Cooling Condenser EIIS: SE EIIC: CDU Radiological Liquid Waste Processing Systems (Radwaste).
EIIS: WD EIIC: PFR Reactor Protection System EIIS: JC EIIC: XC-RCT NRC FORM 366 (6-2004)