05000325/LER-2005-002, Re Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown

Re Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown

ML051720384
Person / Time
Site:	Brunswick
Issue date:	06/14/2005
From:	Hinds D Progress Energy Carolinas, Progress Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 05-0052 LER 05-002-00
Download: ML051720384 (7)

LER-2005-002, Re Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 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)(1) 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3252005002R00 - NRC Website

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• 43 Progress Energy JUN 1 4 2005 SERIAL: BSEP 05-0052 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 1 Docket No. 50-325/License No. DPR-71 Licensee Event Report 1-2005-002 Gentlemen:

In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power

& Light Company, now doing business as Progress Energy Carolinas, Inc., submits the enclosed Licensee Event Report. This report fulfills the requirement for a written report within sixty (60) days of a reportable occurrence.

Please refer any questions regarding this submittal to Mr. Edward T. O'Neil, Manager-Support Services, at (910) 457-3512.

--Sincerely, David H. Hinds Plant General Manager Brunswick Steam Electric Plant CRE/cre Enclosure: Licensee Event Report Progress Energy Carolinas, Inc.

_L Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461

Document Control Desk BSEP 05-0052 / Page 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-051

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1. FACILITnY NAME

2. DOCKET NUMBER

3. PAGE Brunswick Steam Electric Plant (BSEP), Unit 1' 05000325 1 OF 5

4. TITLE Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILIES INVOLVED 14N2005 FACIUTY NAME DOKET NUMBER MONTH DAY YEAR YEAR I SEQUER A NO MONTH FDY E

ARNE fOOcKEr NUMBER 04 15 l2005 2005 --

002 00 06 l 14 l2005 FACIUTlY NAME DOCKET NUMBER4

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TOTHE REQUIREMENTS OF 10 CFR §: (Check one or more) 3 0 20.2201 (b)

E 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)

E 50-73(a)X2)(vii)

D 20.2201 (d)

D 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) 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) 0 50.73(a)(2)(x) 00 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)(il) 0 50.73(a)(2)(v)(B)

D 73.71 (a)(5) 0 20.2203(a)(2)(v) 0 50.73(a)(2)(1)(A) 0 50.73(a)(2Xv)(C)

OTHER El 5.73a)()01()Specif Mn Abstract below 0

20.2203(a)(2)(vi) 0 50.73Ea)(2)(i)(B) 0 50.73(a)(2)(v)(D) o in NC (If more space Is required, use additional copies of (If more space Is required, use additional copies of NRC Form 366A) (17)Missed NRC Notification Upon discovery that the 8-hour notification requirement of 10 CFR 50.72(b)(3)(iv)(A) for the RCIC system actuation was not met, the resident inspector was informed and a Nuclear Condition Report (NCR) was written to address the issue through the corrective action program. Individuals were coached and reviewed the appropriate guidance in plant procedures and NUREG-1022, "Event Reporting Guidelines 10 CFR 50.72 and 50.73," Revision 2. Training for all licensed operators on this event is scheduled to be completed by November 9, 2005.

SAFETY ASSESSMENT

The safety significance of this occurrence is considered minimal. The RCIC system is designed to operate either automatically or manually following RPV isolation, accompanied by a loss of normal coolant flow from the Reactor Feedwater system, to provide adequate core cooling, and control of the RPV coolant level. The function of the RCIC system is to respond to transient events by providing makeup coolant to the reactor. For this event, the RPV was not isolated, but there was a loss of normal coolant flow from the Reactor Feedwater system. The RCIC system was manually started and successfully controlled RPV coolant level for approximately 37 minutes until Reactor Feedwater system flow could be restored to the RPV. All emergency core cooling systems were operable and ready for use, if needed, during this event. This transient is bounded by the analyses in the Updated Final Safety Analysis Report.

PREVIOUS SIMILAR EVENTS

LER 1-2003-001 documented a January 12, 2003, event in which loss of Reactor Feedwater flow to the RPV resulted in a RPS trip without RPV isolation and the subsequent manual starting of the RCIC system to maintain RPV coolant level. The cause of the event was attributed to RFP Turbine 1B trip due to lube oil pressure issues. None of the associated corrective actions would be reasonably expected to prevent the event documented herein.

NCR 124054 documented an April 9, 2004, failure of 1-FW-FV-46 during power ascension due to galling between the plug and cage assembly. The plug and cage assembly were replaced and the valve returned to service. This failure did not result in a reportable event. The cause of the galling could not be determined; however, foreign material initiation of the galling could not be ruled out. The problem with radial buckling of installed gaskets causing the presence of foreign material had not yet been identified.

COMMITMENTS

No regulatory commitments are contained in this report. Those actions discussed in this submittal will be implemented in accordance with corrective action program requirements.