05000259/LER-2007-008, For Browns Ferry, Unit 1, Manual Reactor Scram Due to an Electro Hydraulic Control System Leak

For Browns Ferry, Unit 1, Manual Reactor Scram Due to an Electro Hydraulic Control System Leak

ML073090091
Person / Time
Site:	Browns Ferry
Issue date:	11/02/2007
From:	O'Grady B Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 07-008-00
Download: ML073090091 (8)

LER-2007-008, For Browns Ferry, Unit 1, Manual Reactor Scram Due to an Electro Hydraulic Control System Leak

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(B), System Actuation 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)(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
2592007008R00 - NRC Website

text

November 2, 2007 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 1 - DOCKET 50-259 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-259/2007-008-00 The enclosed report provides details of a manual reactor scram due to a electro hydraulic control system leak. TVA is reporting this in accordance with 10 CFR 50.73(a)(2)(iv)(A), as an event that resulted in a manual or automatic actuation of the systems listed in paragraph 10 CFR 50.73(a)(2)(iv)(B) (i.e., Reactor Protection System including reactor scram or trip, and general containment isolation signals affecting containment isolation valves in more than one system). There are no commitments contained in this letter.

Sincerely, Original signed by:

Brian O'Grady cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 November 2, 2007 Enclosure cc (Enclosure):

Ms. Eva 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 November 2, 2007 JEE:SWA:BAB cc:

G. P. Arent, EQB 1B-WBN W. R. Campbell, LP 6A-C R. H. Bryan, Jr., LP 4J-C D. C. Matherly, Jr., BFT 2A-BFN J. C. Fornicola, LP 6A-C R. G. Jones, POB 2C-BFN G. V. Little, NAB 1D-BFN R. F. Marks, Jr., PAB 1C-BFN B. A. Wetzel, BR 4X-C E. J. Vigluicci, ET 11A-K NSRB Support, LP 5M-C INPO:LEREvents@inpo.org EDMS WT CA - K S:lic/submit/lers/259 2007 005.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 1

2. DOCKET NUMBER 05000259

3. PAGE 1 of 5

4. TITLE: Manual Reactor Scram due to an Electro Hydraulic Control System 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 09 03 2007 2007-008-00 11 02 2007 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 1

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)

X 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) 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

10. POWER LEVEL 072 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 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 (If more space is required, use additional copies of NRC Form 366A) (17) The ASCO solenoid valve on 1-FCO-064-0010 was replaced. Following post maintenance testing operations released the secondary containment clearance, exiting TS 3.6.4.2, Action A.

B.

Corrective Actions to Prevent Recurrence Prior to restart, TVA performed a walkdown of the remaining EHC lines and confirmed proper protective isolation of the EHC tubing from nearby support steel.

VII.

ADDITIONAL INFORMATION

A.

Failed Components None.

B.

Previous LERs on Similar Events Unit 1 License Event Report 259/2007-002 provides details of a manual scram of the Unit 1 Reactor due to an un-isolatable EHC leak. Although both LERs discuss manual shutdown of Unit 1 because of an EHC leak, the root cause of 259/2007-002 was over tightening of a compression fitting. As such, the corrective actions taken in 259/2007-002 would not preclude the event discussed in this LER.

C.

Additional Information

Corrective action document for this event is PER 129791.

D.

Safety System Functional Failure Consideration:

This event is not considered 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.