05000483/LER-2010-003, Regarding Safety System Actuation After Loss of a Switchyard Bus

Regarding Safety System Actuation After Loss of a Switchyard Bus

ML101100487
Person / Time
Site:	Callaway
Issue date:	04/20/2010
From:	Neterer D AmerenUE, Union Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05695 LER 10-003-00
Download: ML101100487 (9)

LER-2010-003, Regarding Safety System Actuation After Loss of a Switchyard Bus

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
4832010003R00 - NRC Website

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wAmeren UE AmerenUE Callaway Plant April 20, 2010 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 ULNRC-05695 PO Box 620 Fulton, MO 65251 1 OCFR50. 73 (a)(2)(iv)(A)

Ladies and Gentlemen:

DOCKET NUMBER 50-483 CALLA WAY PLANT UNIT 1 UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2010-003-00 SAFETY SYSTEM ACTUATION AFTER LOSS OF A SWITCHY ARD BUS The enclosed licensee event report is submitted in accordance with 10CFRSO.73(a)(2)(iv)(A) to report a valid automatic actuation of systems listed in 1 OCFR50. 73 (a)(2)(iv)(B):

(3) Emergency core cooling systems (ECCS) for pressurized water reactors (PWR),

(6) PWR auxiliary or emergency feedwater systems, (8) Emergency AC electrical power systems, and (9) Emergency service water systems which do not normally run.

This letter does not contain new commitments.

CSP/nls Enclosure a subsidiary of Ameren Corporation Sincerely,

~

David W. Neterer Plant Director

ULNRC-05695 April 20, 2010 Page 2 cc:

Mr. Elmo E. Collins, Jr.

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mohan C. Thadani (2 copies)

Senior Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8G 14 Washington, DC 20555-2738

ULNRC-05695 April 20, 2010 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)

LEREvents@inpo.org (must send the WORD version ofthe LER to this address)

Electronic distribution for the following can be made via LER ULNRC Distribution:

A. C. Heflin F. M. Diya D. W. Neterer L. S. Sandbothe C. O. Reasoner III S. A. Maglio S. L. Gallagher T. L. Woodward (NSRB)

T. B. Elwood D. E. Dumbacher (NRC)

B. A. Brook (WCNOC)

Ms. Diane M. Hooper (WCNOC)

Mr. Dennis Buschbaum (Luminant Power)

Mr. Ron Barnes (APS)

Mr. Tom Baldwin (PG&E)

Mr. Wayne Harrison (STPNOC)

Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)

Missouri Public Service Commission Records Center (INPO)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (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.

1. FACIUTY NAME

2. DOCKET NUMBER

13. PAGE Callaway Plant Unit 1 05000483 1 OF 6

4. TITLE Safety System Actuation After Loss of a Switchyard Bus

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 02 19 2010 2010 003 00 04 20 2010

9. OPERATING MODE

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

D 20.2201(b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(i)(C)

D 50.73(a)(2)(vii) 1 D 20.2201 (d)

D 20.2203(a)(3)(ii)

D 50.73(a)(2)(ii)(A)

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

D 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(ii)(B)

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

D 20.2203(a)(2)(i)

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

D 50.73(a)(2)(iii)

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

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

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

~ 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

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

D 73.71(a)(4) 100%

D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

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

D 73.71 (a)(5)

D 20.2203(a)(2)(v)

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

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

D OTHER D 20.2203(a)(2)(vi)

D 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) (17)

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