05000328/LER-2009-001, Regarding Automatic Reactor Trip Following a Power Range Negative Rate Trip

Regarding Automatic Reactor Trip Following a Power Range Negative Rate Trip

ML092010458
Person / Time
Site:	Sequoyah
Issue date:	07/20/2009
From:	Clearly T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 09-001-00
Download: ML092010458 (7)

LER-2009-001, Regarding Automatic Reactor Trip Following a Power Range Negative Rate Trip

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 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)(v), Loss of Safety Function
3282009001R00 - NRC Website

text

Tennessee Valley Authority Post Office Box 2000 Soddy Daisy, Tennessee 37384-2000 Timothy P. Cleary Site Vice President Sequoyah Nuclear Plant July 20, 2009 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Docket No. 50-328 Washington, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT (SQN) UNIT 2 -

FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-328/2009-001-00 The enclosed LER provides details concerning an automatic reactor trip and automatic engineered safety feature actuation of the auxiliary feedwater system.

The reactor trip was the result of a power range negative rate trip.

This report is being submitted in accordance with 10 CFR 50.73 (a)(2)(iv)(A), a condition that resulted in an automatic actuation of the reactor protection system.

Sincerely, Timothy P.17 Cleary V

Enclosure cc:

See page 2 printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 July 20, 2009 Enclosure cc (Enclosure):

INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway, SE, Suite 100 Atlanta, Georgia 30339-5957 Mr. Siva P. Lingam, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379

NRC FORM 366 (9-2007)

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)

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

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Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk

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If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Sequoyah Nuclear Plant (SQN) Unit 2

2. DOCKET NUMBER 05000328

3. PAGE 1 OF 5

4. TITLE:

Unit 2 Automatic Reactor Trip Following a Power Range Negative Rate Trip

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 DOCKET NUMBER 05 27 2009 2009 001 00 07 20 2009 FACILITY NAME DOCKET NUMBER

9. OPERATING MODE 1

10. POWER LEVEL 100

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

50.73(a)(2)(vii)

50.73(a)(2)(vJii)(A)

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

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

50.73(a)(2)(x)

73.71 (a)(4)

73.71 (a)(5)

OTHER

20.2201 (b)

20.2201 (d)

20.2203(a)(1)

20.2203(a)(2)(i)

20.2203(a)(2)(ii)

20.2203(a)(2)(iii)

20.2203(a)(2)(iv)

20.2203(a)(2)(v)

20.2203(a)(2)(vi)

20.2203(a)(3)(i)

20.2203(a)(3)(ii)

20.2203(a)(4)

50.36(c)(1)(i)(A)

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

50.36(c)(2)

50.46(a)(3)(ii)

50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B)

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

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

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

50.73(a)(2)(iii)

[X]

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

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

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

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

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

B.

Previous LERs on Similar Events:

A review of previous reportable events did not identify any previous similar events within the last three years.

C.

Additional Information

None.

D.

Safety System Functional Failure:

This event did not result in a safety system functional failure in accordance with 10CFR50.73(a)(2)(v).

E.

Unplanned Scram with Complications:

This condition did not result in an unplanned scram with complications.

VIM.

COMMITMENTS

None.