05000296/LER-2007-004, Re Manual Isolation of High Pressure Core Injection Due to Steam Leak

Re Manual Isolation of High Pressure Core Injection Due to Steam Leak

ML080290046
Person / Time
Site:	Browns Ferry
Issue date:	01/28/2008
From:	Skaggs M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 07-004-00
Download: ML080290046 (7)

LER-2007-004, Re Manual Isolation of High Pressure Core Injection Due to Steam Leak

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2962007004R00 - NRC Website

text

January 28, 2008 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN: Document Control Desk Mail Stop: OWFN, P1-35 Washington, D. C. 20555-0001

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT (BFN)

- UNIT 3 - DOCKET 50-296 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-296/2007-004-00 The enclosed report provides details of the manual isolation of High Pressure Coolant Injection Due to steam leak. TVA is submitting this report in accordance with 10 CFR 50.73(a)(2)(v)(B) and 10 CFR 50.73(a)(2)(v)(D) as "any event or condition that could prevented the fulfillment of a safety function of structures of systems that are needed to: Remove residual heat or mitigate the consequences of an accident." There are no commitments contained in this letter.

Sincerely, Original signed by:

M. D. Skaggs, Interim, Site Vice President, BFN cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 January 28, 2008 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 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

U.S. Nuclear Regulatory Commission Page 3 January 28, 2008 DTL:JEE:SWA:BAB Enclosure cc (Enclosure):

G.P. Arent, EQB 1B-WBN W. R. Campbell, Jr. LP 3R-C J. R. Douet, LP 3R-C R. F. Marks, Jr., PAB 1C-BFN D. C. Matherly, BFT 2A-BFN L. E. Nicholson, BR 4X-C B. A. Wetzel, BR 4X-C S. A. Vance, WT 6A-K E. J. Vigluicci, ET 11A-K INPO: LEREvents@inpo.org NSRB Support, LP 5M-C EDMS WT CA-K, S:lic/submit/lers/296-2007-004.doc

NRC FORM 366 (6-2004)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-2004)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB NO. 3150-0104 EXPIRES 06/30/2007

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

1. FACILITY NAME Browns Ferry Unit 3

2. DOCKET NUMBER 05000296

3. PAGE 1 of 4

4. TITLE: Manual Isolation of High pressure Core Injection Due to Steam Leak

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.

MONTH DAY YEAR FACILITY NAME None DOCKET NUMBER N/A 11 30 2007 2007-004-00 01 28 2008 FACILITY NAME None DOCKET NUMBER N/A

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

9. OPERATING MODE 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii)

X 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 3

10. POWER LEVEL 0

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

X 50.73(a)(2)(v)(D) specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17) VI. CORRECTIVE ACTIONS A.

Immediate Corrective Actions

Operations closed the HPCI steam supply line outboard containment isolation valve and entered TS LCO 3.5.1.C.

B.

Corrective Actions to Prevent Recurrence (1)

The valve stem packing in the HPCI steam line condenser inboard drain valve was replaced.

A section of one inch pipe with the through wall leak was replaced. Pipe wall thickness checks were performed on the piping adjacent to the leak and the wall thickness met the design calculation requirements.

VII. ADDITIONAL INFORMATION

A.

Failed Components None.

B.

Previous LERs on Similar Events None.

C.

Additional Information

Corrective action document for this report is PER 134495.

D.

Safety System Functional Failure Consideration:

This event involves a safety system functional failure according to NEI 99-02.

E.

Scram With Complications Consideration:

This event did not result in a complicated scram according to NEI 99-02.

VIII. COMMITMENTS

None.

(1) TVA does not consider the corrective actions a regulatory requirement. The completion of the action will be tracked in TVA's Corrective Action Program.