05000328/LER-2009-002, Regarding Manual Reactor Trip Because of Degrading Main Feedwater Pump Turbine Condenser Vacuum

Regarding Manual Reactor Trip Because of Degrading Main Feedwater Pump Turbine Condenser Vacuum

ML100270032
Person / Time
Site:	Sequoyah
Issue date:	01/25/2010
From:	Church C Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 09-002-00
Download: ML100270032 (6)

LER-2009-002, Regarding Manual Reactor Trip Because of Degrading Main Feedwater Pump Turbine Condenser Vacuum

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), 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
3282009002R00 - NRC Website

text

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 January 25, 2010 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Facility Operating License No. DPR-79 NRC Docket No. 50-328

Subject:

Licensee Event Report 328/2009-002, "Manual Reactor Trip Because of Degrading Main Feedwater Pump Turbine Condenser Vacuum" The enclosed licensee event report provides details concerning a manual reactor trip and automatic engineered safety feature actuation of the auxiliary feedwater system. The manual reactor trip was initiated because of degrading main feedwater pump turbine condenser vacuum. This report is being submitted in accordance with 10 CFR 50.73(a)(2)(iv)(A), a condition that resulted in an manual actuation of the reactor protection system.

Respectfully, Christopher R. Church Site Vice President Sequoyah Nuclear Plant

Enclosure:

cc:

NRC Regional Administrator-Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant

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, digits/characters for each block) and a person is not required to respond to, the information collection.

3. PAGE Sequoyah Nuclear,Plant (SQN) Unit 2 05000328 1 OF5

4. TITLE:

Manual Reactor Trip because of Degrading Main Feedwater Pump Turbine Condenser Vacuum

5. EVENT.DATE

6. LER NUMBER

7. REPORT'DATE

8. OTHER FACILITIES INVOLVED SEQUENTIAL

.REV MOT A

ERFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR UE R

MONTH DAY YEAR NUMBER NO.

FACILITY NAME DOCKET NUMBER 11 26 2009 2009 002 00

.01 25 2010

9. OPERATING MODE

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

DJ 20.2201(b)

LI 20.2203(a)(3)(i)

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

LI 50.73(a)(2)(vii) 1l 20.2201(d)

LI 20.2203(a)(3)(ii)

[] 50.73(a)(2)(ii)(A)

.E] 50.73(a)(2)(viii)(A)

[]

20.2203(a)(1)

LI 20.2203(a)(4)

L] 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)

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

LI 50.73(a)(2)(iii)

- 1 50.73(a)(2)(ix)(A)

10. POWER LEVEL F1 20.2203(a)(2)(ii)

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

- E 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x)

L0 20.2203(a)(2)(iii)

El 50.36(c)(2) 50.73(a)(2)(v)(A)

LI 73.71(a)(4)

L[I 20.2203(a)(2)(iv)

[-- 50.46(a)(3)(ii)

]

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

]

73.71(a)(5) 30 EL 20.2203(a)(2)(v)

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

L0i 50.73(a)(2)(v)(C)

LI OTHER LI 20.2203(a)(2)(vi)

LI 50.73(a)(2)(i)(B)

D 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)

VII.

ADDITIONAL INFORMATION

A.

Failed Components:

None.

B.

Previous LERs on Similar Events:

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

C.

Additional Information

None.

D.

Safety System Functional Failure:'

This event did not result in a safety system functional failure in accordance with 10 CFR 50.73(a)(2)(v).

E.

Unplanned Scram with Complications:

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

VIII.

COMMITMENTS

None.