05000259/LER-2008-003, Regarding Main Steam Relief Valve as Found Setpoint Exceeded Technical Specification Lift Pressure

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Regarding Main Steam Relief Valve as Found Setpoint Exceeded Technical Specification Lift Pressure
ML090480086
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 02/11/2009
From: West R
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 08-003-00
Download: ML090480086 (7)


LER-2008-003, Regarding 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)(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
2592008003R00 - NRC Website

text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 11, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, P1-35 Washington, D. C. 20555-0001 10 CFR 50.73

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT (BFN) -

UNIT 1 - DOCKET 50-259 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-259/2008-003 The enclosed report provides details of a failure to meet the requirements of the Technical Specifications (TS) 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 TS. There are no commitments contained in this letter.

R. G. West Site Vice President, BFN cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 February 11, 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 Ms. Heather J. Gepford, 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 (VERIFY)

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) collection.

3. PAGE Browns Ferry Unit 1 05000259 1 of 5
4. TITLE: Main Steam Relief Valve As Found Setpoint Exceeded Technical Specification Lift Pressure
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MO YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR None N/A NUMBER NO.

FACILITY NAME DOCKET NUMBER 12 12 2008 2008 003 00 02 11 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)

[I 20.2203(a)(3)(i)

[I 50.73(a)(2)(i)(C) 0l 50.73(a)(2)(vii) 10 20.2201(d)

El 20.2203(a)(3)(ii) 0l 50.73(a)(2)(ii)(A)

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

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

[I 50.73(a)(2)(viii)(B) 0o 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A) 0l 50.73(a)(2)(iii)

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

10. POWER LEVEL 0l 20.2203(a)(2)(ii) 0l 50.36(c)(1)(ii)(A) 0l 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x) 0l 20.2203(a)(2)(iii)

El 50.36(c)(2)

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

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

El 50.46(a)(3)(ii) 0l 50.73(a)(2)(v)(B) 0l 73.71 (a)(5) 100 El 20.2203(a)(2)(v)

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

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

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

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

S ifin Abstract bel.r nNRC

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

Steve Austin, Licensing Engineer 1

256-729-2070MANU-REPORTABLE MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT FATRR T

PXCAUSE SYSTEM COMPONENT FCUE OEI FACTURER TO EPIX FACTURER TO EPIX B

SB RV T020 Y

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR' SUBMISSION El 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 December 12, 2008, TVA determined that 10 of the 13 Main Steam Relief Valves (MSRVs) removed from Unit 1 following Cycle 7 operation mechanically actuated at pressures greater than 3 percent above their Technical Specifications (TS) setpoint, thus inoperable. Unit 1 TS limiting condition for operation (LCO) 3.4.3 requires that twelve (12) MSRVs are operable in reactor modes 1, 2, and 3. If less than twelve MSRVS are operable, the unit is to be placed in Mode 3 hot 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 1 operated outside the TSs longer than allowed by the TSs. 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 Technical Specifications.

NRC FORM 366 (9-2007)

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

B.

PREVIOUS LERS ON SIMILAR EVENTS Numerous previous reports on similar events have been made by BFN. BFN plans to implement corrective actions that have been successful at other boiling water reactors.

C.

Additional Information

Corrective action document for this report is PER 159200.

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.