05000483/LER-2008-002, Regarding Void Found in Line EM-023-HCB - Residual Heat Removal Pump a to Safety Injection Pumps
| ML090070032 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/23/2008 |
| From: | Patterson J AmerenUE |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 08-002-00 | |
| Download: ML090070032 (15) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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 |
| 4832008002R00 - NRC Website | |
text
AmerenUE Callaway Plant PO Box 620 Fulton, MO 65251 December 23, 2008 ULNRC-05574 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 WA meren Ladies and Gentlemen:
YE 10CFR50.73(a)(2)(i)(B) 1 OCFR50.73(a)(2)(vii)
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2008-002-00 VOID FOUND IN LINE EM-023-HCB - RESIDUAL HEAT REMOVAL PUMP "A" TO SAFETY INJECTION PUMPS
Reference:
NRC Letter dated October 29, 2008 from Vincent G. Gaddy, Chief, Projects Branch B Division Reactor Projects Region IV, to Adam C. Heflin, Senior Vice President and Chief Nuclear Officer - Union Electric Company, "Callaway Plant - NRC Integrated Inspection Report 05000483/2008004" The enclosed licensee event report is submitted in accordance with 10CFR50.73(a)(2)(i)(B) and 10CFR50.73(a)(2)(vii) to report a void found in line EM-023-HCB (i.e., the line between residual heat removal pump "A" and the safety injection pumps).
This letter does not contain new commitments.
Plant Director CSP/nls Enclosure a subsidiary of Ameren Corporation
ULNRC-05574 December 23, 2008 Page 2 cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator U.S. Nuclear Regulatory Commission Region IV 612 E. Lamar BlvdL, 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)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-8G14 Washington, DC 20555-2738
ULNRC-05574 December 23, 2008 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.)
LEREventsginpo.org (must send the WORD) version of1the 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 T. E. Herrmann J. T. Patterson L. S. Sandbothe S. A. Maglio S. L. Gallagher L. M. Belsky (NSRB)
T. L. Woodward (NSRB)
T. B. Elwood D. E. Dumbacher (NRC)
B. A. Brook (WCNOC)
Ms. Diane M. Hooper (WCNOC)
Mr. Dennis Buschbaum (TXU)
Mr. Scott Bauer (Palo Verde)
Mr. Stan Ketelsen (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: 06/30/2007 (6-2004)
, 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 Callaway Plant Unit 1 05000483 1 OF 12
- 4. TITLE Void Found in Line EM-023-HCB - Residual Heat Removal Pump "A" to Safety Injection Pumps
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED fFAEVTYoAMIDOKE NUBE MONTH DAY YEAR k YEAR SEQUENTIAL REV MONTH DAY YEAR FAILIYNMOKTNME NUMBER NO.I IFACILITY NAME DOCKET NUMBER 05 21 2008 2008 -
002 -
00 12 23 2008[
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
E] 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(.2)(i)(C)
Z 50.73(a)(2)(vii)
El 20.2201(d)
[E 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
_[I 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E!l 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
Ej 50.73(a)(2)(v)(A)
[] 73.71(a)(4)
[I 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 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)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
.0 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in Summary of the Event section below, the void was introduced during maintenance on the safety injection (SI) [EIIS system: BQ]
system during Refuel Outage 15 but was unknowingly not removed during the fill and vent procedure completed prior to restart from that outage. The SI system was not required to be operable at the time the void was created and left in place.
D. NARRATIVE SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES NOTE: A listing of some of the terms used in this Licensee Event Report (LER) is provided in section V, ADDITIONAL INFORMATION, of this report.
BACKGROUND:
The Emergency Core Cooling System (ECCS) at Callaway consists of three separate subsystems: centrifugal charging (CC) (high head) [EIIS system: BQ], safety injection (SI)
(intermediate head) [EIIS system: BQ], and residual heat removal (RHR) (low head) [EIIS system: BP]. Each subsystem consists of two redundant, 100% capacity trains. The ECCS flow paths consist of piping, valves, heat exchangers, and pumps such that water from the Refueling Water Storage Tank (RWST) [EIIS system: BP component: TK ] can be injected (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 (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)
Workman's Protection Assurance (WPA) - Callaway plant's program for establishing conditions to prevent personnel injury during maintenance or repair of equipment. It also establishes measures to prevent unauthorized operation of out-of-service equipment or systems [system: BQ, component: P ].
CCP, Centrifugal Charging Pump, high head pump, part of the Emergency Core Cooling System [system: BQ, component: P ].
RHR Heat Exchanger [system: BP, component: HX].
RWST, Refueling Water Storage Tank, [system: BP, component: TK].
RHR pump, Residual Heat Removal [system: BP, component: P ]
SI pump, Safety Injection Pump - intermediate head pump, part of the Emergency Core Cooling System