05000244/LER-2006-002, R. E. Ginna Nuclear Power Plant Regarding Off-Site Power Systems Declared Inoperable

R. E. Ginna Nuclear Power Plant Regarding Off-Site Power Systems Declared Inoperable

ML062610164
Person / Time
Site:	Ginna
Issue date:	09/12/2006
From:	Korsnick M Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NUREG-1022 LER 06-002-00
Download: ML062610164 (8)

LER-2006-002, R. E. Ginna Nuclear Power Plant Regarding Off-Site Power Systems Declared Inoperable

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)(B) 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
2442006002R00 - NRC Website

text

Maria Korsnick Site Vice President R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick@constellation.com Constellation Energy Generation Group September 12, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 LER 2006-002. Off-site Power Systems Declared Inonerable The attached Licensee Event Report (LER) 2006-002 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(v)(A). This report covers three separate events as provided for in NUREG 1022, Revision 2, Event Reporting Guidelines 10CFR 50.72 and 50.73, Section 2.3. These events in no way affected the public's health and safety. There are no new commitments contained in this submittal. Should you have questions regarding the information in this report, please contact Mr. Robert Randall at (585) 771-3734 or Robert.Randall @constellation.com.

Very truly yous,

/

00161q

Document Control Desk September 12, 2006 Page 2 MK/MR Attachments: (1) LER 2006-002 cc:

S. J. Collins, NRC P.D. Milano, NRC Resident Inspector, NRC (Ginna) 1001629

ATTACHMENT (1)

LER 2006-002 R.E. Ginna NPP September 12, 2006

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)

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

3. PAGE R.E. Ginna Nuclear Power Plant 05000244 1 OF 5

4. TITLE Off-site Power Systems Declared Inoperable

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEUMETALREVO MONTH DAY YEAR 05000 NUMBER NO.

050 FACILITY NAME DOCKET NUMBER 07 17 2006 2006 - 002 -

0 09 12 2006 05000

9. OPERATING MODE

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

[1 20.2201(b)

[] 20.2203(a)(3)(i)

[] 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii)

[ 1l 20.2201(d)

[E 20.2203(a)(3)(ii)

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

[I 50.73(a)(2)(viii)(A)

[o 20.2203(a)(1)

El 20.2203(a)(4)

[I 50.73(a)(2)(ii)(B)

[l 50.73(a)(2)(viii)(B)

C_ 20.2203(a)(2)(i)

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

[E 50.73(a)(2)(iii)

[I 50.73(a)(2)(ix)(A)

10. POWER LEVEL 0

20.2203(a)(2)(ii)

[E 50.36(c)(1)(ii)(A)

[I 50.73(a)(2)(iv)(A)

[E 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2)

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

El 73.71 (a)(4)

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

[] 50.73(a)(2)(v)(B)

El 73.71(a)(5) 100 El 20.2203(a)(2)(v)

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

[E 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

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

El 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)

2) Extension of circuit 909 to Station 122. This will add a third transmission tie of Station 13A to the 345 kV system.

These long term actions are scheduled for a 12/2007 completion as part of the Rochester Transmission Project. This project was not initiated by this event, but was a system upgrade project initiated by RG&E due to increased system loading and local generation retirements.

VI.

ADDITIONAL INFORMATION

A.

FAILED COMPONENTS:

There were no failed components associated with this event.

B.

PREVIOUS LERs ON SIMILAR EVENTS:

There are no previous LERs associated with the post contingency low voltage alarm.

C.

THE ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) COMPONENT FUNCTION IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN THIS LER:

COMPONENT IEEE 803 FUNCTION IDENTIFIER IEEE 805 SYSTEM IDENTIFICATION Off-site Power Emergency Diesel Generators Jx DG EA EK D.

SPECIAL COMMENTS:

Off-site power was never lost to the site and the DGs were not required to operate.

The post contingency alarm is a conservative estimate of the voltage following a trip of the unit with full safeguards loading on the vital busses (design basis accident). In all cases both DGs were operable and capable of performing their design function if the off-site voltage was not sufficient. Therefore, the undervoltage system would strip the vital busses from off-site power and load them on the DGs, assuring that adequate power is available to the required safeguards equipment.