05000327/LER-2009-004, Manual Reactor Trip Following Isolation of Two Intermediate Pressure Feedwater Heater Strings

Manual Reactor Trip Following Isolation of Two Intermediate Pressure Feedwater Heater Strings

ML091800457
Person / Time
Site:	Sequoyah  (DPR-077)
Issue date:	06/29/2009
From:	Cleary T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 09-004-00
Download: ML091800457 (8)

LER-2009-004, Manual Reactor Trip Following Isolation of Two Intermediate Pressure Feedwater Heater Strings

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 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) 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 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x)
3272009004R00 - NRC Website

text

Tennessee Valley Authority Post Office Box 2000 Soddy Daisy, Tennessee 37384-2000 Timothy P. Cleary Site Vice President Sequoyah Nuclear Plant June 29, 2009 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN:

Document Control Desk Washington, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT (SQN) UNIT 1 DOCKET NO. 50-327 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-327/2009-004-00 The enclosed LER provides details concerning a manual reactor trip and automatic engineered safety feature actuation of auxiliary feedwater following the isolation of two strings of intermediate pressure feedwater heaters.

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

Sincerely, Timothy P. Cleary J

Enclosure cc:

See page 2 printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 June 29, 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)

APPROVED BY OMB NO.

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Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52),

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

Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104),

Office of Management and Budget, Washington, DC 20503.

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, Unit 1

2. DOCKET NUMBER 05000327

3. PAGE 1 OF 6

4. TITLE:

Unit 1 Manual Reactor Trip Following Isolation of Two Intermediate Pressure Feedwater Heater Strings

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 04 28 2009 2009 004 00 06 29 2009 FACILITY NAME DOCKET NUMBER

9. OPERATING MODE 1

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF

10. POWER LEVEL 018

20.2201 (b)

20.2201 (d)

20.2203(a)(1)

20.2203(a)(2)(i)

20.2203(a)(2)(ii)

20.2203(a)(2)(ili)

20.2203(a)(2)(iv)

20.2203(a)(2)(v)

20.2203(a)(2)(vi) 20.2203(a)(3)(l) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A)

U 50.36(c)(2)

50.46(a)(3)(il)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(i)(B) 50.73(a)(2)(i)(C) 50.73(a)(2)(li)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 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) 10 CFR §: (Check all that apply)

50.73(a)(2)(vii)

50.73(a)(2)(viii)(A)

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

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

D 50.73(a)(2)(x)

D 73.71 (a)(4)

73.71 (a)(5)

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

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.