05000410/LER-2006-002, Regarding RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition

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Regarding RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition
ML062140044
Person / Time
Site: Nine Mile Point 
Issue date: 07/25/2006
From: Hutton J
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 06-002-00
Download: ML062140044 (6)


LER-2006-002, Regarding RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

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)(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
4102006002R00 - NRC Website

text

0 Constellation Energy*

Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 July 25, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:

SUBJECT:

Document Control Desk Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 Licensee Event Report 06-002, "RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition" In accordance with 10 CFR 50.73(a)(2)(ii)(B), we are submitting Licensee Event Report 06-002, "RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition."

Should you have questions regarding the information in this submittal, please contact M. H. Miller, Licensing Director, at (315) 349-1510.

Very truly yours,

/ames A. Hutton Plant General Manager JAH/KSE/sac Attachment cc:

S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector

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 digit"s/characters for each b

,oc-or sponsor, and a person is not required to respond to, the information digis/carater foreac blck)collection.

3. PAGE Nine Mile Point Unit 2 05000410 1 OF 5
4. TITLE RCIC Exhaust Piping Vacuum Breakers Isolated Resulting in an Unanalyzed Condition
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED IFACILITY NAME LDOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NUMBER NO.

OPEATIG MDE I. HISREPRTFACILITY NAME DOCKET NUMBER 05 26 2006 2006 - 002 -

00 07 25 2006

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b)

[I 20.2203(a)(3)(i) 0l 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii) 10 20.2201(d)

[I 20.2203(a)(3)(ii)

[0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A)

[o 20.2203(a)(1)

[0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0] 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)

[] 50.73(a)(2)(iii)

[0 50.73(a)(2)(ix)(A)

10. POWER LEVEL [0 20.2203(a)(2)(ii)

[0 50.36(c)(1)(ii)(A)

[0 50.73(a)(2)(iv)(A)

[0 50.73(a)(2)(x) o 20.2203(a)(2)(iii)

[0 50.36(c)(2)

[0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv)

[0 50.46(a)(3)(ii)

[0 50.73(a)(2)(v)(B)

[0 73.71(a)(5) 100 0 20.2203(a)(2)(v)

[0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 0 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 (If more space is required, use additional copies of NRC Form 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 Reactor Core Isolation Cooling System (BWR)

High Pressure Coolant Injection System (BWR)

Containment Leakage Control System Vacuum Breaker Valves Isolation Valves RCIC Turbine IEEE 805 System ID BN BJ BD IEEE 803A Function CKV ISV TRB