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LER-2005-004, Re Operation Prohibited by Technical Specifications Due to Unrevealed Inoperability of One Off-Site Power Source |
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| Reporting criterion: |
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)(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 |
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| 2202005004R00 - NRC Website |
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text
Constellation Energy-Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 February 17, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
SUBJECT:
Document Control Desk Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Licensee Event Report 05-004. "Operation Prohibited by Technical Specifications due to Unrevealed Inoperability of One Off-site Power Source" In accordance with 10 CFR 50.73(a)(2)(i)(B), we are submitting Licensee Event Report 05-004, "Operation Prohibited by Technical Specifications due to Unrevealed Inoperability of One Off-site Power Source."
Should you have questions regarding the information in this submittal, please contact M. HI. Miller, Licensing Director, at (315) 349-1510.
Very truly yours, General Manager JAH/RF/sac Attachment cc:
S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector I E0,1A
Document Control Desk February 17, 2006 Page 2 bcc:
L. S. Larragoite C. W. Fleming, Esquire T. J. O'Connor J. A. Hutton M. H. Miller J. L. Lyon NMP1L 2025 COMMITMENTS IDENTIFIED IN THIS CORRESPONDENCE:
NONE Responsible Person/Organization:
Due Date:
SAR/TSB Revision Required? If yes, No Type:
Initiation Date:
NCTS No.:
Posting Requirements for Responses -- NOVWOrder No
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct digits/characters for each block) or sponsor, and a person is not required to respond to, the information
- 3. PAGNE Nine Mile Point Unit 1 05000220 1
OF 4
- 4. TITLE Operation Prohibited by Technical Specifications due to Unrevealed Inoperability of One Off-site Power Source
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR S
EQUENTIAL REV.
MONTH DAY YEAR I FACILITY NAME DOCKET NUMBER 12 19 2005 2005 - 004 -
00 02 17 2006
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check al that apply) o 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1 El 20.2201(d) 0 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) 03 20.2203(a)(2)(i)
El 50.36lc)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.361c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) o 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A)
El 73.71(a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B)
El 73.71 (a)(5) 100 a 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
E 50.73(a)(2)(v)(C)
El OTHER o
20.2203(a)(2)(vi) i 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (if more space is required, use additional copies of NRC Foim 366A) (17)
V. Additional Information
A. Failed Components:
None
B. Previous similar events
None C. Identification of components referred to in this Licensee Event Report:
Components 115 kV Offsite Power Emergency Diesel Generators IEEE 805 System ID FK EK IEEE 803,A Function N/A DG
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| 05000220/LER-2005-001, Regarding Automatic Reactor Scram Due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch | Regarding Automatic Reactor Scram Due to a Failure in the Circuitry for a Moisture Separator Tank Level Switch | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) | | 05000410/LER-2005-001, Regarding Both Standby Gas Treatment Subsystems Inoperable Due to an Original Design Deficiency | Regarding Both Standby Gas Treatment Subsystems Inoperable Due to an Original Design Deficiency | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000220/LER-2005-002, Re Fuel Moved with an Inoperable Source Range Monitor Due to Human Error Resulting in a Technical Specification Violation | Re Fuel Moved with an Inoperable Source Range Monitor Due to Human Error Resulting in a Technical Specification Violation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000220/LER-2005-003, Regarding Automatic Reactor Scram During Surveillance Testing Due to Inadvertently De-energizing 4160 Vac Power Board 11 | Regarding Automatic Reactor Scram During Surveillance Testing Due to Inadvertently De-energizing 4160 Vac Power Board 11 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000220/LER-2005-004, Re Operation Prohibited by Technical Specifications Due to Unrevealed Inoperability of One Off-Site Power Source | Re Operation Prohibited by Technical Specifications Due to Unrevealed Inoperability of One Off-Site Power Source | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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