05000219/LER-2005-003, Re Technical Specification Violation Due to Missing Test Cap
| ML052630373 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/12/2005 |
| From: | Swenson C AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-05-20176 LER 05-003-00 | |
| Download: ML052630373 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 2192005003R00 - NRC Website | |
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AmerGen SM AmerGen Energy Company www.exeloncorp.com An Exelon Company Oyster Creek US Route g South, P.O. Box 388 Forked River, NJ 08731-0388 10 CFR 50.73 September 12, 2005 2130-05-20176 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-1 6 NRC Docket No. 50-219
Subject:
Licensee Event Report 2005-003-00, Technical Specification Violation due to Missing Test Cap Enclosed is Licensee Event Report 2005-003, Revision 0. 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. Attachment 1 lists the regulatory commitments made in this LER submittal.
If any further information or assistance is needed, please contact William Stewart at 609-971-4775.
Sincerely, C. N. Swenson Vice President, Oyster Creek Generating Station CNSN/VS : Summary of Commitments
Enclosure:
NRC Form 366, LER 2005-003-00 cc:
S. J. Collins, Administrator, USNRC Region I P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 05046
ATTACHMENT 1 OCGS Licensee Event Report 2005-003-00 SUMMARY OF COMMITMENTS The following table identifies commitments made in this document by Exelon Nuclear. (Any other actions discussed in the submittal represent intended or planned actions by Exelon Nuclear. They are described to the NRC for the NRC's information and are not regulatory commitments.)
Commitment
Committed Date or "Outage' Applicable leak rate test procedures will be November 30, 2005 revised prior to next use to require the use of leak rate tags.
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BYOMB:NO.3150-0104 EXPIRES: 063012007 r320o4)
, 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 Oyite(Creek, Unit 1 05000 f21; 1
OF 04--
- 4. TITLE Tecnhical S ecif itsoin VgOlatiOn au e to Aissiri!Tet ap-i>
q Y
I.
S. EVENT DATE
- 6. LER NUMBER l
- 7. REPORT D l1 MONTH I DAY I
YEAR SEQUENTIALRV YEAR NUMBER NO ATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER YEAR 05000 2005 FACILITY NAME DOCKET NUMBER 05000 07 l; 12 20051 :2005
- - j 003 -- 00
- 9. OPERATING MODE N
- 10. POWER LEVEL 100
- 11. THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 120.2201 (b) 20.2201 (d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi)
I-20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4)
- - 50.36(c)(1)(i)(A) 50.36(c)(1 )(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)Qi)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71 (a)(4) 73.71 (a)(5)
OTHER Specify In Abstract below 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)
Additional Information
A. Failed Components:
None
B. Previous Similar Events
None C. Identification of Components referred to in this Report:
Components IEEE 805 System ID IEEE 803A Function Isolation Valve EIIS-BD EIIC-ISV Flow Recorder EIIS-LK EIIC-FR Containment Penetration EIIS-LK EIIC-PEN NRC FORM 366 (6-2004)