05000325/LER-2006-004, Regarding As-Found Values for Safety Relief Valve Lift Setpoints Outside Technical Specification Allowed Tolerance

Regarding As-Found Values for Safety Relief Valve Lift Setpoints Outside Technical Specification Allowed Tolerance

ML062140098
Person / Time
Site:	Brunswick
Issue date:	07/26/2006
From:	Waldrep B Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 06-0082 LER 06-004-00
Download: ML062140098 (5)

LER-2006-004, Regarding As-Found Values for Safety Relief Valve Lift Setpoints Outside Technical Specification Allowed Tolerance

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
3252006004R00 - NRC Website

text

Progress Energy JUL 2 6 2006 SERIAL: BSEP 06-0082 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 1-2006-004 Ladies and 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.

Please refer any questions regarding this submittal to Mr. Randy C. Ivey, Manager - Support Services, at (910) 457-2447.

Sincerely, B. C. Walle1 Plant General Manager Brunswick Steam Electric Plant MAT/mat

Enclosure:

Licensee Event Report Progress Energy Carolinas, Inc.

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

Document Control Desk BSEP 06-0082 / 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

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 06130/2007 (6-2004)

Estimated burden per response to comply wih this rmandatory information 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 LICENSEE EVENT REPORT (LER) industry. Send comments regarcing burden estimate to the Records and FOMNdvacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Conrsission, Washington, DC 20555-0001, or by (See reverse for required number of Internet e-mail to Infocollects@nrc.

v, and to the Desk Officer, Office of tIfornation and digits/characters for each block)

Regulatory Affairs. NEOB-10202 (3150-0104), Office of Management and Budget, Washington.

DC 205M0. It a means used to impose an information collection does not dsplay a currently valid OMB control nurrber, the NRC may not conduct or sponsor, and a person is not required to respond to the information ccdlection.

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

4. TITLE As-Found Values for Safety/Relief Valve Lift Setpoints Outside Technical Specification Allowed Tolerance

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER I

NUMBER NO j

05000 06 02 2006 2006 --

004 00 07 26 2006 FACILITY NAME DOCKETNUMBER 1____________

J_ _

05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 1 0

20.2201(b)

E0 20.2203(a)(3)(i)

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

El 50.73(a)(2)(vii)

[] 20.2201(d) 0l 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

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

El 20.2203(a)(1)

[I 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

El 20.2203(a)(2)(i)

[I 50.36(c)(1)(i)(A)

[I 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

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

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

[]

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

Q 50.73(a)(2)(x) 100 El 20.2203(a)(2)(iii)

El 50.36(c)(2)

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

El 73.71(a)(4)

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71(a)(5)

El 20.2203(a)(2)(v)

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

El 50.73(a)(2)(v)(C)

E] OTHER Specf in Abstract below

_________EI 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)

[]

50.73(a)(2)(v)(D) ori C (If more space is required, use additional copies of NRC Form 366A) (17)

EVENT CAUSE

The root cause evaluation of this event has not been completed; pending disassembly and inspection of the SRVs which are being performed in August 2006. A supplement to this LER is planned.

SAFETY ASSESSMENT

The safety significance of this condition is considered minimal.

The as-found condition of the Unit 1 SRVs was compared to the current overpressure analysis prepared in support of extended power uprate and it was concluded that this analysis remained bounding. As such, the applicable acceptance criteria for design basis events would have been met and the SRVs remained capable of performing their intended safety function.

CORRECTIVE ACTIONS

The 11 SRV pilot valve assemblies were replaced with certified spares during the BI 16R1 refueling outage.

Additional corrective actions, if necessary, will be established based on the root cause evaluation results.

PREVIOUS SIMILAR EVENTS

Target Rock SRV setpoint drift has been an industry issue since the early 1980s. The last reportable condition for BSEP occurred on Unit 2 and was reported in LER 2-1999-005, dated June 7, 1999, as supplemented on December 8, 1999.

COMMITMENTS

No regulatory commitments are contained in this report.