05000410/LER-2006-001, Regarding Automatic Reactor Scram Due to a Loss of Main Turbine Gland Sealing Steam
| ML061360217 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/05/2006 |
| From: | Hutton J Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-001-00 | |
| Download: ML061360217 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 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)(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 |
| 4102006001R00 - NRC Website | |
text
Constellation Energy, Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 May 5, 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 06-001. "Automatic Reactor Scram due to a Loss of Main Turbine Gland Sealing Steam" In accordance with 10 CFR 50.73(a)(2)(iv)(A), Nine Mile Point Nuclear Station is submitting Licensee Event Report 06-001, "Automatic Reactor Scram due to a Loss of Main Turbine Gland Sealing Steam."
Should you have questions regarding the information in this submittal, please contact M. H. Miller, Licensing Director, at (315) 349-1510.
Very truly yours, S.Hutton
/Plant General Manager JAH/RF/sac Attachment (1)
Licensee Event Report (LER) cc:
S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector d,7f2-2
Document Control Desk May 5, 2006 Page 2 bcc:
L. S. Larragoite C. W. Fleming, Esquire T. J. O'Connor J. A. Hutton M. H. Miller J. L. Lyon NMP2L 2133 COMMITMENTS IDENTIFED IN TIlS 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
ATTACHMENT (1)
Licensee Event Report (LER)
Nine Mile Point Nuclear Station, LLC May 5,2006
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are Incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Recors and FOIAlPrivacy Service Branch (T7-5 F62), U.S. Nuclear LICENSEE EVENT REPORT (LER)
Regulatory Commission, Washington, DC 20555-0001, or by Intemet e-mail to infocollectstdnrcgv, and to the Desk Officer, Office of Information and
.RegulatoryAfairs, NEOB-10202, (3150-0104), Office of Management and Budget
.Washington, DC 20503. If a means used to impose an Information collection (See reverse for required number of does not displaya curentl valid 0MB conl number, the NRC may not conduct digits/characters for each block) or sponsor, and a person I not required to respond to, the information
- 3. PAGE Nine Mile Point Unit 2 05000410 1 OF 4
- 4. TITLE Automatic Reactor Scram due to a Loss of Main Turbine Gland Sealing Steam
- 6. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNIA E
ACILITY NAME DOCKET NUMBER MO hTH DAY YEAR YEAR SUE R
EV MONTH DAY YEAR
_FACILnlY NAME DOCKET NUMBER 03 09 2006 2006 - 001 - 00 05 05 2006 9.OP ERATING MODE I1. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
D 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 1 0
20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(Ii)(A) 0 50.73(a)(2)(viii)(A)
D 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) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 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) 03 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4) 0 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 86 E 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER El 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 Forn 366A) (17)
Ill. Analysis of Event This event is reportable in accordance with 10 CFR 50.73(aX2)(iv)(A) because of the automatic reactor scram while critical.
There were no actual safety consequences associated with this event. There were no automatic initiations of safety systems, and operators effectively stabilized reactor parameters. The conditional core damage probability for the event was calculated as 7.OE-7.
Based on the above, the event did not pose a threat to the health and safety of the public or plant personnel.
IV. Corrective Actions
NOTE: There are no NRC regulatory commitments in this Licensee Event Report.
The following corrective actions have been developed such that, when completed, will prevent a similar event.
Improve maintenance procedures for overhauling/calibrating pneumatic controllers by including checks to ensure linkages and other critical components are properly reassembled following maintenance.
Correct the Emergency Steam Supply Backup System design deficiency to reduce the effects of a pressure transient.
Conduct training to enhance problem solving skills for operations and engineering.
Inspected and replaced air regulating valves for critical pneumatic controllers, where appropriate.
NRC ;ORM 366A (1-2001)
(if more space is required, use additional copies of NRC Form 366A) (17)
V. Additional Information
A. Failed Components:
Mechanical linkage between the pressure indicating controller and the process pointer of the Emergency Steam Supply Backup System to the Turbine Generator Gland Seal and Exhaust System (TME).
Pressure regulating valve which supplies air to the TME 'A Clean Steam Reboiler level transmitter.
B. Previous similar events
None C. Identification of components referred to in this Licensee Event Report:
Components Reactor Protection System Turbine Generator Gland Seal and Exhaust System Condenser Main Turbine Pressure Indicating Controller Clean Steam Reboiler Pressure Regulating Valve Level Transmitter Mechanical Linkage IEEE 805 System ID JC TC SG TA TC TC TC TC TC IEEE 803.A Function N/A N/A COND TRB PIC BLR PCV LT CON