05000443/LER-2009-001, Reactor Protection System on Steam Generator Low Water Level
| ML093430243 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/30/2009 |
| From: | St.Pierre G NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SPK-L-09248 LER 09-001-00 | |
| Download: ML093430243 (4) | |
| 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)(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)(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 |
| 4432009001R00 - NRC Website | |
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NEXTeraM EN ERG'YP AEABROK November 30, 2009 Docket No. 50-443 SBK-L-09248 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Licensee Event Report (LER) 2009-001-00 Reactor Protection System Actuation on Steam Generator Low Water Level Enclosed is Licensee Event Report (LER) 2009-001-00. This LER reports an event that occurred at Seabrook Station on October 1, 2009. This event is being reported pursuant to the requirements of 10 CFR 50.73(a)(2)(iv)(A).
Should you require further information regarding this matter, please contact Mr. Michael O'Keefe, Licensing Manager at (603) 773-7745.
Sincerely, NextEra Energy Seabrook, LLC Gene St. Pierre Vice President North cc:
S. J. Collins, NRC Region I Administrator D. L. Egan, NRC Project Manager W. J. Raymond, NRC Senior Resident Inspector NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)
- Estimated
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Seabrook Station 05000443 1 OF 3
- 4. TITLE Reactor Protection Svstem Actuation on Steam Generator Low Water Level
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE 1
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MNH DY YA YERSEQUENTIAL REV MONH0AY0EA YER NUMBER NO.
05000AY EA 10 0 IFACILITY NAMEDOKTNME 10 01 2009 2009
- - 001 00 11 30 2009 05000
- 9. OPERATING MODE 11.-THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 4 El 20.2201(d)
[I 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
_[_]
20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [I 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
ED 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
[I 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[] 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
E 50.73(a)(2)(v)(B)
El 73.71(a)(5) 000 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
[E 50.73(a)(2)(i)(B)
El 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 Form 366A) (17)
This event resulted in a valid actuation of the RPS and met the reporting criterion of 10CFR50.72(b)(3)(iv)(A). An eight-hour report (event # 45403) was made to the NRC at 0418 on October 2, 2009. This event is of regulatory significance because it resulted in the actuation of a system provided to mitigate the consequences of an accident.
This event had no adverse impact on the plant oron the health and safety of the public. No equipment was actuated following actuation of the RPS and no consequences resulted from the event. No inoperable structures, systems, or components contrbuted to this event. This condition did not involve a Safety System Functional Failure.
IV. Corrective Action
The planned corrective actions for this event include: (1) remediation for the control room operator who failed to adequately monitor and control SG levels, (2) revising the Operations department's expectations document to address procedure compliance with major plant evolution procedures, (3) discussing in operator training procedure compliance expectations with a review of this event, and (4) revising the major plant evolution procedures so that the procedure strategy is maintained by specifically identifying steps that may be performed in parallel or out of sequence.
V.
Additional Information
The Energy Industry Identification System (EIIS) codes are included in this LER in the following format: [EIIS system identifier, EIIS component identifier].
VI.
Similar Events
A review of LERs for the last five years found no other occurrences of an engineered safety features system actuation as a result of inappropriate procedure implementation.