05000325/LER-2008-001, Regarding High Pressure Coolant Injection (HPCI) System Inoperable Due to Main Pump Seal Leak

Regarding High Pressure Coolant Injection (HPCI) System Inoperable Due to Main Pump Seal Leak

ML081910149
Person / Time
Site:	Brunswick
Issue date:	06/30/2008
From:	Wills E Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 08-001-00
Download: ML081910149 (3)

LER-2008-001, Regarding High Pressure Coolant Injection (HPCI) System Inoperable Due to Main Pump Seal Leak

Event date:
Report date:
Reporting criterion:	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)(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
3252008001R00 - NRC Website

text

Progress Energy June 10, 2008 SERýIAL: BSEP 08-0086, U. S-.Nuclear Regulatory Commission AT, TNDcumen Control Desk Wshing;on, DC 20555-0001

- Subject:,-.,,

Brunswick Steam Electr

.i, Docket No. 50-325/Lice Licensee Event Report 10 CFR 50.73 el;.,:!+;

4 4i;+

++

+* ++44,4 ic Plant, UnitNo. 1 1*2e :6No.DPR-7-l

`,20080,0 11-,

L.adies and Gentlemen:

In accordance with the Code of Fed&ral -Regulations, Title 10 Part 50'.73, Caroliina Powver

& Light Company, now doing businessý,as-Progress -Energy Carolin-as -.Inc.,- submits the4 enclosed Licensee Event Report (LER). This report-fulfills.th'erequirementf oi-a wri-ntten report within sixty (60) days of a reportableocccurrence.

An engineering analysis is in progress+tO. substantiate the ablity of the affected system to fulfill its safety functions in the degraded 6conditioin This:LEI' illbe,supplemented, afid based on the results of the engineering qyaluationm'ay result in retraction',of Eve*nit Notification 44179 and withdrawal of this LER-'.+i Please refer any questions regarding this submittal:to Mr. Randy C*.Ivey, Mlanag.er -

Support Services, at (910) 457-2447.

Sincerely,

ýA4 4

Edward L. Wills, Jr.

Plant General Manager Brunswick Steam Electric Plant MAT/mat

Enclosure:

I ý 17 i UlU,1il3i Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 U2 V kwiL I-,Up U I L 4~4 4-

Document Control Desk BSEP 08-0086 / Page 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-05 10

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

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

4. TITLE High Pressure Coolant Injection (HPCI) System Inoperable due to Main Pump Seal Leak

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACLIY NAME DOCKET NUMBER5000 MOT DY YER YER NUMBER NO.05 0

FACILITY NAME DOCKET NUMBER 04 29 2008 2008 - 001 - 00 06 30 2008 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

[- 20.2201(b)

El 20.2203(a)(3)(i)

EL 50.73(a)(2)(i)(C)

LI 50.73(a)(2)(vii)

E L] 20.2201(d)

El 20.2203(a)(3)(ii)

EL 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

[L] 20.2203(a)(1)

[] 20.2203(a)(4)

[] 50.73(a)(2)(ii)(B)

[] 50.73(a)(2)(viii)(B)

El 20.2203(a)(2)(i)

F1 50.36(c)(1)(i)(A)

[] 50.73(a)(2)(iii)

[] 50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A)

LI 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x)

LI 20.2203(a)(2)(iii)

[I 50.36(c)(2)

[] 50.73(a)(2)(v)(A)

LI 73.71 (a)(4) 032 LI20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

[]50.73(a)(2)(v)(B)

LI 73.71(a)(5)

LI 20.2203(a)(2)(v)

[: 50.73(a)(2)(i)(A)

LI 50.73(a)(2)(v)(C)

E-OTHER LI 20.2203(a)(2)(vi)

E] 50.73(a)(2)(i)(B)

[

50.73(a)(2)(v)(D)

Specify in Abstract below or in NRC Form 366A

12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)

Mark Turkal, Lead Engineer - Licensing (910) 457-3066MANU-REPORTABLE' MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT

CAUSE

SYSTEM COMPONENT FACTURER TO EPIX FACTURER TO EPIXFCUE OEI

14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR SUBMISSION YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

[] NO DATE 07 31 2008 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On April 29, 2008, at approximately 2313 Eastern Daylight Time (EDT), during performance of the High Pressure Coolant Injection (HPCI) system operability test, the HPCI system was declared inoperable due to a leak on the main pump seal. When the pump seal leak developed, operators secured HPCI and isolated the leak by closing the pump suction isolation valves and the keep fill supply valves.

The safety consequences of this event were minimal. The Emergency Core Cooling Systems (ECCS) and the Reactor Core Isolation Cooling (RCIC) system were operable and would provide appropriate Loss-of-Coolant Accident (LOCA) response.

Investigation of this event found that inadequate post-maintenance venting of piping between the discharge of the HPCI booster pump and the suction of the HPCI main pump led to the seal faces overheating and subsequent failure.

An engineering analysis is in progress to substantiate the ability of the HPCI system to fulfill its safety functions in the degraded condition. This LER will be supplemented, and based on the results of the engineering evaluation, may result in retraction of Event Notification 44179 and withdrawal of this LER.

NRC FORM 366 (9-2007)