05000220/LER-2006-001, Re Technical Specification Required Shutdown Due to Increased Drywell Leakage
| ML062290262 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/10/2006 |
| From: | Hutton J Constellation Energy Group, Nine Mile Point |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-001-00 | |
| Download: ML062290262 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2202006001R00 - NRC Website | |
text
James A. Hutton Plant General Manager P.O. Box 63 Lycoming, New York 13093 315.349.2061 315.349.4308 Fax Constellation Energy, Nine Mile Point Nuclear Station August 10, 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 06-001, "Technical Specification Required Shutdown due to Increased Drywell Leakage" In accordance with 10 CFR 50.73(a)(2)(i)(A), we are submitting Licensee Event Report 06-001, "Technical Specification Required Shutdown due to Increased Drvwell Leakage."
Should you have questions regarding the information in this submittal, please contact M. H. Miller, Licensing Director, at (315) 349-1510.
Very truly yours, JAH/RF/sac
Attachment:
(1)
Licensee Event Report cc:
S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector
ATTACHMENT (1)
LICENSEE EVENT REPORT (LER)
Nine Mile Point Nuclear Station, LLC August 10, 2006
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 digits/characters for each block) or sponsor, and a person Is not required to respond to, the Information collection.
- 3. PAGE Nine Mile Point Unit 1 05000220 1 OF 3
- 4. TITLE Technical Specification Required Shutdown due to Increased Drywell Leakage
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I IJFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NUMBER NO.
FACILITY NAME DOCKET NUMBER 06 11 2006 2006 - 001 -
00 08 10 2006 ING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) ol 20.2201(b)
[I 20.2203(a)(3)(i)
[0 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
N 0l 20.2201(d)
[0 20.2203(a)(3)(ii)
[0 50.73(a)(2)(ii)(A)
[I 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)
Eo 20.2203(a)(2)(i) 0l 50.36(c)(1)(i)(A)
[0 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)
[I 50.73(a)(2)(x) o 20.2203(a)(2)(iii)
[] 50.36(c)(2)
[0 50.73(a)(2)(v)(A) 0 73.71(a)(4)
EO 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii)
[0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 45 01 20.2203(a)(2)(v)
ED 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 NRC Form 366A) (17)
IV. Corrective Actions
The RCS pump drain valve packing was replaced and the leaking weld downstream of the RCS pump drain valve was repaired. Replacement of incorrect packing on the redundant downstream valve, which was identified through extent of condition review, was entered in the corrective action program. The current NMP1 valve packing program provides adequate performance standards for packing installation.
V. Additional Information
A. Failed Components:
Reactor Coolant Recirculation System pump drain valve.
B. Previous similar events
Two similar events occurred in 1997 where lack of a valve packing program resulted in incorrect packing installation and caused shutdowns due to increased drywell leakage. The NMP1 valve packing program was established in November 1998. The failed valve in this event was in scope for replacement during the refueling outage in 2005, but was chosen not to be replaced because it was assessed as a low risk due to its function, infrequent use and absence of known seat leakage.
C. Identification of component referred to in this Licensee Event Report:
Component Pump Drain Valve Pump Dischage Valve Pump Suction Valve IEEE 805 System ID AD AD AD IEEE 803.A Function ISV ISV ISV