05000413/LER-2010-001, Catawb, Unit 1, Regarding Technical Specification Violation Associated with Failure to Perform Offsite Circuit Verification
| ML100920062 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/31/2010 |
| From: | Morris J Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 10-001-00 | |
| Download: ML100920062 (10) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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 |
| 4132010001R00 - NRC Website | |
text
P Duke dEnergy JAMES R. MORRIS Vice President Duke Energy Corporation Catawba Nuclear Station 4800 Concord Road York, SC 29745 803-701-4251 803-701-3221 fax March 31, 2010 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Units 1 and 2 Docket Nos.
50-413 and 50-414 Licensee Event Report 413/2010-001 Attached is Licensee Event Report 413/2010-001, Revision 0 entitled, "Technical Specification Violation Associated with Failure to Perform Offsite Circuit Verification".
There are no regulatory commitments contained in this letter or its attachment.
This event is considered to be of no significance with respect to the health and safety of the public.
If there are any questions on this report, please contact L.J. Rudy at (803) 701-3084.
Sincerely, James R. Morris LJR/s Attachment www. duke-energy. corýn
Document Control Desk Page 2 March 31,.2010 xc (with attachment):
L.A. Reyes Regional Administrator U.S. Nuclear Regulatory Commission -
Region II Marquis One Tower 245 Peachtree Center Ave.,
NE Suite 1200
- Atlanta, GA 30303-1257' J.H. Thompson (addressee only)
NRC Project Manager U.S,. Nuclear Regulatory Commission Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto, III NRC Senior Resident Inspector Catawba Nuclear Station INPO Records Center 700 Galleria Place
- Atlanta, GA 30339-5957
Document Control Desk Page 3 March 31, 2010 bxc (electronic copy) (with attachment):
INPO lerevents@inpo.org K.W. Phillips R.D.
Hart G.Y.
Helton S.F. Hatley (EPIX)
M.K.
Green D.R. Brenton S.L. Nader A.M.
Peterman K.D. Thomas R.G.
Hull T.W.
King K.R. Alter H.D.
Brewer K.L. Ashe B.J. Horsley M.J.
Brown bxc (hard copy) (with attachment):
R.L. Gill, Jr.
L.F. Vaughn G.F. Winkel L.J. Rudy ELL Master File CN-801.01 LER File RGC Date File NCMPA-I NCEMC PMPA
NRC FORM.366 U.S. NUCLEAR REGULATORY APPROVED BY OMB: NO. 3150,0104
. EXPIRES: 08/31/2010 (9-2007)
COMMISSION Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch LICENSEE EVENT REPORT (LER)
(T-5 F52), U.S. 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-1 0202, (3150-0104), Office of Management and Budget, Washington, DC 20503.
(See reverse for required number of If a means used to impose an information collection does not display a currently valid OMB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not required to respond to. the information collection
- 3. PAGE Catawba Nuclear Station, Unit 1 05000 413 1 OF 7
- 4. TITLE Technical Specification Violation Associated with Failure to Perform Offsite Circuit Verification
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER SEQUENTIAL REV Catawba Unit 2 05000 414 MO DAY YEAR YEAR NUMBER NO MO DAY YEAR" FACILITY NAME DOCKET NUMBER 02 01 2010 2010 001 00 03 31 2010
- 9. OPERATING
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
MODE 1
20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
- 10. POWER 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL 1 00 120.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 120.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER Specify in Abstract below S20.2203(a)(2)(iii) 50.46(a)(3)(ii) 150.73(a)(2)(v)(C) or in
Abstract
On February 1, 2010, Technical Specification (TS) 3.8.1, "AC Power Sources
- - Operating" was violated for Units 1 and 2.
The violation occurred following the racking out of a 6.9 kV bus tie breaker for preventive maintenance.
Due to unclear TS Bases, plant personnel did not recognize that with the tie breaker racked out, one offsite circuit was inoperable.
Licensed Operations personnel failed to adequately evaluate and perform the required actions associated with the inoperability of the offsite circuit in a timely manner.
Surveillance Requirement (SR) 3.8.1.1 was not performed within one hour as required to verify that the other offsite circuit was operable.
SR 3.8.1.1 was subsequently performed for both units and the tie breaker was subsequently racked back in, thereby restoring the inoperable offsite circuit to operable status.
Planned corrective actions include enhancing the affected TS Bases.
Throughout this event, all 4.16 kV Engineered Safety Feature buses remained energized and backed by available Diesel Generators.
The health and safety of the public were not adversely affected by this event.
NRC FORM 366 (9-2007)
(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 (If more space is required, use additional copies of NRC Form 366A) (17)
SAFETY ANALYSIS
There was no safety significance to this evenet.
At no time was offsite power lost to either of the 4.16 kV ESF buses ETA or ETB.
With the tie breaker removed from service, the only adverse effect upon the plant was the inability to comply with SR 3.8.1.8.
Although-SR 3.8.1.1 was performed late, the surveillance demonstrated that the required offsite circuits were, in fact, operable.
Also, both train's DGs remained available throughout this event, thereby ensuring that standby emergency power was available to the ESF buses, had it been required.
The health and safety of the public were not adversely affected by this event.
ADDITIONAL INFORMATION
.Within the previous three years, there were no LER events involving the failure to perform SR 3.8.1.1 within one hour as.required by TS 3.8.1.
Therefore, this event.is considered to be non-recurring.
Energy Industry Identification System (EIIS) codes are identified in the text as [EIIS: XX].
- This event'is not considered reportable to the Equipment Performance and Information Exchange (EPIX)'program.
This event is not considered to constitute a Safety System Functional Failure.;
There was no release.of radioactive material, radiation overexposure, or personnel injury associated with the event described in this LER.