05000443/LER-2005-005, Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6

Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6

ML051600448
Person / Time
Site:	Seabrook
Issue date:	06/06/2005
From:	Warner M Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SBK-L-05121 LER 05-005-00
Download: ML051600448 (5)

LER-2005-005, Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6

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) 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
4432005005R00 - NRC Website

text

FPL Energy Seabrook Station FPL Energy Seabrook Station P.O. Box 300 Seabrook, NH 03874 (603) 773-7000 JUN 6 2005 Docket No. 50-443 SBK-L-05121 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Licensee Event Report (LER) 2005-005-00 for Reactor Protection System Actuation on Low Steam Generator Level in Mode 6 Enclosed is Licensee Event Report (LER) 2005-005-00. This LER reports an event that occurred at Seabrook Station on April 13, 2005. 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. James M.

Peschel, Regulatory Programs Manager (603) 773-7194.

Very truly yours, FPL ENERGY SEABROOK, LLC Mark E. Warner Site Vice President cc:

S. J. Collins, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector 9,

J"ee

an FPL Group company

ENCLOSURE TO SBK-L-05121

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150.0104 EXPIRES: 06130/2007

<.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 Records and FOlAJPrivacy Service Branch (T-5 F52), U.S.

LICENSEE EVENT REPORT (LER)

Nuclear Regulatory Commission. Washington. DC 20555-0001, or by Internet e-mail to infocollects~nrcgov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of ManaQement and Budget, Washington. DC 20503. If a means used to impose an information (See reverse for required number of collectiondoesnotdisplayacurrenttyvalidOMBcontrolnumber,theNRC may r fr e ach b

not conduc or sponsor, and a person Is not required to respond to, the digits/characters for each block) information collection.

I. FACILITY NAME

2. DOCKET NUMBER

3. PAGE Seabrook Station 05000 443 1 OF 3

4. TITLE Reactor Protection System Actuation on Steam Generator Low Level in Mode 6

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL RENV O

MONTH DAY YEAR N/A 05000 FACILITY NAME DOCKET NUMBER 04 13 2005 2005 - 005 -

00 06 06 2005 N/A 05000

9. OPERATING MODE

1. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check althat apply)

El 20.2201(b)

El 20.2203(a)(3)(i) a 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii) 6 0 20.2201(d) 0 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) o 20.2203(a)(1)

El 20.2203(a)(4) 0l 50.73(a)(2)(ii)(B)

ED 50.73(a)(2)(viii)(B)

El 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

E 50.73(a)(2)(ix)(A)

10. POWER LEVEL 0

20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A) 0 50.73(a)(2)iv)(A)

D 50.73(a)(2)(x) o 20.2203(a)(2)(iii)

E 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71(a)(4) 0 20.2203(a)(2)(iv)

El 50A6(a)(3)(ii) 0l 50.73(a)(2)(v)(B)

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

El 50.73(a)(2)(i)(A)

E 50.73(a)(2)(v)(C) 0 OTHER El 20.2203(a)(2)(vi)

El 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)

IV. Corrective Action

The procedures utilized to drain, fill, and recirculate the steam generators will be revised to provide the appropriate coordination between the processes.

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].

Similar Events

A review of LERs submitted in the last five years found no similar events involving a valid system actuation as a consequence of an inadequate procedure.