05000260/LER-2009-003, Main Steam Relief Valve as Found Setpoint Exceeded Technical Specification Lift Pressure

Main Steam Relief Valve as Found Setpoint Exceeded Technical Specification Lift Pressure

ML092220501
Person / Time
Site:	Browns Ferry
Issue date:	08/07/2009
From:	West R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 09-003-00
Download: ML092220501 (7)

LER-2009-003, Main Steam Relief Valve as Found Setpoint Exceeded Technical Specification Lift Pressure

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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) 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
2602009003R00 - NRC Website

text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 August 7, 2009 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, P1-35 Washington, D. C. 20555-0001 Browns Ferry Nuclear Plant Unit 2 Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

LICENSEE EVENT REPORT (LER) 50-260/2009-003 The enclosed report provides details of a failure to meet the requirements of the Technical Specifications (TSs) Limiting Condition for Operation (LCO) 3.4.3 concerning the main steam relief valve operability.

TVA is reporting this in accordance with 10 CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by the plant's TSs. There are no commitments contained in this letter. Should you have any questions concerning this submittal, please contact F. R. Godwin, Site Licensing and Industry Affairs Manager, at (256) 729-2636.

Respectfully, Vice President cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 August 7, 2009 Enclosure cc (Enclosure):

Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Eugene F. Guthrie, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970

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 digits/characters for each block) colaction.

3. PAGE Browns Ferry Unit 2 05000260 1 of 5

4. TITLE: Main Steam Relief Valve As Found Setpoint Exceeded Technical Specification Lift Pressure

6. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR None N/A M H NUMBER NO.

FACILITY NAME DOCKET NUMBER 06 09 2009 2009 003 00 08 07 2009 None N/A

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) o 20.2201(b)

El 20.2203(a)(3)(i)

[I 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii) 4l 20.2201(d)

El 20.2203(a)(3)(ii)

D 50.73(a)(2)(ii)(A)

[I 50.73(a)(2)(vifi)(A) o 20.2203(a)(1) 0l 20.2203(a)(4)

Dl 50.73(a)(2)(ii)(B)

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

[] 20.2203(a)(2)(i) 0l 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

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

10. POWER LEVEL EJ 20.2203(a)(2)(ii) 0l 50.36(c)(1)(ii)(A)

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

El 50.73(a)(2)(x) ol 20.2203(a)(2)(iii) 0l 50.36(c)(2) 0l 50.73(a)(2)(v)(A) 0l 73.71 (a)(4) o 20.2203(a)(2)(iv) 0l 50.46(a)(3)(ii)

[I 50.73(a)(2)(v)(B) 0l 73.71 (a)(5) 0 E-I20.2203(a)(2)(v)

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

EJ 50.73(a)(2)(v)(C)

E0 OTHER El 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)

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

SFoim i366ractbeo...iiNRC

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

Steve Austin, Licensing Engineer 256-729-2070CAUSE SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX B

SB RV T020 Y

14. SUPPLEMENTAL REPORT EXPECTED

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

NO DATE N/A N/A N/A ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On June 8, 2009, TVA determined that 7 of the 13 Main Steam Relief Valves (MSRVs) removed from Unit 2 following Cycle 15 operation mechanically actuated at pressures greater than 3 percent above their Technical Specifications (TSs) setpoint, and thus were inoperable. Unit 2 TS limiting condition for operation (LCO) 3.4.3 requires that twelve (12) MSRVs are operable in reactor modes 1, 2, and 3. With one or more required MSRVs inoperable, the unit is required to be placed in Mode 3 (hot shutdown) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Mode 4 (cold shutdown) within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. As such, it is probable that Unit 2 operated outside the TSs longer than allowed. Therefore, TVA is submitting this report in accordance with 10 CFR 50.73(a)(2)(i)(B), as any operation or condition prohibited by the plant's TSs.

NRC FORM 366 (9-2007)

(if more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)

C.

Additional Information

Corrective action document for this report is Problem Evaluation Report 175990.

D.

Safety System Functional Failure Consideration:

This event is not a safety system functional failure according to NEI 99-02.

E.

Scram With Complications Consideration:

This event was not a complicated scram according to NEI 99-02.

VIII. COMMITMENTS

None.