05000339/LER-2010-001, For North Anna, Unit 2, Regarding Automatic Reactor Trip and ESF Actuation During Automatic Voltage Regulator Testing Due to Inadequate Procedure Guidance

For North Anna, Unit 2, Regarding Automatic Reactor Trip and ESF Actuation During Automatic Voltage Regulator Testing Due to Inadequate Procedure Guidance

ML101800262
Person / Time
Site:	North Anna
Issue date:	06/23/2010
From:	Lane N Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
10-288 LER 10-001-00
Download: ML101800262 (6)

LER-2010-001, For North Anna, Unit 2, Regarding Automatic Reactor Trip and ESF Actuation During Automatic Voltage Regulator Testing Due to Inadequate Procedure Guidance

Event date:
Report date:
Reporting criterion:	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) 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)(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
3392010001R00 - NRC Website

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-.ý i 1 OCFR50.73 Virginia Electric and Power Company North Anna Power Station P. 0. Box 402 Mineral, Virginia 23117 June 23, 2010 U. S. Nuclear Regulatory Commission Serial No.:

10-288 Attention: Document Control Desk NAPS:

JHL Washington, DC 20555-0001 Docket No.: 50-339 License No.: NPF-7 Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to North Anna Power Station Unit 2.

Report No. 50-339/2010-001-00 This report has been reviewed by the Facility Safety Review Committee and will be forwarded to the Management Safety Review Committee for its review.

Sincerely, Site Vice President North Anna Power Station Enclosure Commitments contained in this letter: None cc:

U. S. Nuclear Regulatory Commission, Region il Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 8/31/2010 (9-2007)

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

3. PAGE NORTH ANNA POWER STATION, UNIT 2 05000339 1 OF5

4. TITLE Automatic Reactor Trip and ESF Actuation During Automatic Voltage Regulator Testing Due to Inadequate Procedure Guidance

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

1 04 27 2010 2010

-- 001 --

00 06 23 2010 FACILITY NAME DOCUMENTINUMBER I1 05000

9. OPERATING MODE

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

E] 20.2201(b)

E]

20.2203(a)(3)(i)

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

E] 50.73(a)(2)(vii) 1 El 20.2201(d)

[]

20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A)

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

[] 20.2203(a)(1)

[

20.2203(a)(4)

H 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(g)

El 20.2203(a)(2)(i)

[

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

[]

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

10. POWER LEVEL

[]

20.2203(a)(2)(ii)

[

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

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

El 50.73(a)(2)(x)

LI 20.2203(a)(2)(iii)

[]

50.36(c)(2)

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

[E] 73.71(a)(4) 74%

Ej 20.2203(a)(2)(iv)

[

50.46(a)(3)(ii)

[

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

El 73.71(a)(5)

F-1 20.2203(a)(2)(v)

[]

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

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

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

[

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

[

50.73(a)(2)(v)(D)

VOLUNTARY LER

12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)

E. S. Hendrixson, Director Station Safety and Licensing (540) 894-2108CAUSE SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX D

TL RG S125 Y

14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR SUBMISSION

_.J YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

[

NO DATE moo I RAC I (bruit to 10uu spaces, i.e., approxrmaruey to strige-spaceu lypewrnifrn,ne)j On April 27, 2010 at 1637 hours0.0189 days <br />0.455 hours <br />0.00271 weeks <br />6.228785e-4 months <br />, with Unit 2 in Mode 1 at 74% power during recovery from a refueling outage, an automatic reactor trip occurred while testing a new digital automatic voltage regulator (AVR). A turbine trip due to a generator lockout caused the automatic reactor trip. The direct cause of the generator lockout protective relay actuation was the incorrect operability curve set points derived from the voltage regulator Minimum Excitation Level (MEL) tuning software.

Following the reactor trip, all control rods inserted into the core and decay heat was removed using the normal steam dump system. The Auxiliary Feedwater (AFW) Pumps received an automatic start signal due to low/low level in the steam generators following the reactor trip. Following the automatic start of the Turbine Driven AFW (TDAFW) pump, the Control Room received annunciator alarm (F-D8). This was an AFW Pump Trouble or Lube Oil Trouble alarm. An operator was dispatched and reported that oil was spraying from the pump bearings and reservoir. The TDAFW pump was secured and declared inoperable.

This event is reportable per 10 CFR 50.73(a)(2)(iv)(A) for the automatic actuation of the Reactor Protection System and AFW System. No significant safety consequences resulted from this event. Steam Generator inventory was restored to the normal operating level. Therefore, the health and safety of the public were not affected by this event.

NRC FORM 366 (9-2007)

PRINTED ON RECYCLED PAPER (if more space is required, use additional copies of (/f 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)

Utilize CM-AA-RSK-1 001, Engineering Risk Assessment Utilize DNAP-0306 Level I software classification requirements for software testing and code validation of non-safety related power block equipment operating software affecting power generation and/or reactivity.

Validate computer software design basis for operating and testing parameters.

" Software test plan incorporating all system operating and testing parameters.

Simulation of operating software on a simulator prior to use on plant equipment.

" Requirements to re-run software testing when adding or removing software parameters or features.

Maintenance was performed on the TDAFW pump to re-establish a vent path for the lube oil reservoir.

6.0 ACTIONS TO PREVENT RECURRENCE Actions to prevent recurrence from the RCE are being tracked in the Central Reporting System to completion.

7.0 SIMILAR EVENTS

None.

8.0 ADDITIONAL INFORMATION

Unit 1 was operating in Mode 1 at 100% power at the time of this event and remained at approximately 100% power for the duration of the event.

The Unit 1 TDAFW pump and both the Unit 1 and 2 motor driven AFW pumps have an installed vent cap in its lube oil reservoir. No problems have been reported due to over-pressurization on these lube oil systems.

Component Information Affected System: Voltage Regulator Component Manufacturer: Siemens Power Generation, Inc Sub-Contractor: Turbine Control Service Associates, IncPRINTED ON RECYCLED PAPER