05000483/LER-2006-007, Re Inoperability of a Containment Cooler Longer than Allowed by Technical Specifications
| ML062850294 | |
| Person / Time | |
|---|---|
| Site: | Callaway  (NPF-030) |
| Issue date: | 10/06/2006 |
| From: | Thibault L AmerenUE |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC05337 LER 06-007-00 | |
| Download: ML062850294 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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 |
| 4832006007R00 - NRC Website | |
text
AmerenUE Cal/away Plant PO Box 620 Fulton, MO 65251 October 6, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 ULNRC05337 S'Ameren Uf Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2006-007-00 Unexpected Inoperability of 'A' Containment Cooling System due to a Lack of Documentation.
The enclosed licensee event report is submitted in accordance with 1 OCFR50.73(a)(2)(i)(B) and 50.73(a)(2)(v)(D) to report an unexpected inoperability of the 'A' Containment Cooling System due to a lack of documentation.
This letter does not contain new commitments.
Sincerely, L. E. Thibault Director Plant Operations LET/DWG/slk Enclosure il~ 62A a subsidiary of Ameren Corporation
ULNRC05337 October 6, 2006 Page 2 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-7D1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339
ULNRC05337 October 6, 2006 Page 3 bcc:
C. D. Naslund A. C. Heflin C. R. Younie K. D. Young G. A. Hughes D. E. Shafer (470)
S. L. Gallagher (100)
L. M. Belsky (NSRB)
K. A. Mills P. M. Bell mspDa nrc.gov ded@nrc.gov LEREvents(iinpo.org babrook@wcnoc.com A160.0761 Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards aiid public disclosed).
Send the following without attachments:
Ms. Diane M. Hooper Supervisor, Licensing WCNOC P.O. Box 411 Burlington, KS 66839 Mr. Scott Bauer Regulatory Affairs Palo Verde NGS P.O. Box 52034, Mail Station 7636 Phoenix, AZ 85072-2034 Mr. Scott Head Supervisor, Licensing South Texas Project NOC Mail Code N5014 P.O. Box 289 Wadsworth, TX 77483 Mr. Dennis Buschbaum TXU Power Comanche Peak SES P.O. Box 1002 Glen Rose, TX 76043 Mr. Stan Ketelsen Manager, Regulatory Services Pacific Gas & Electric Mail Stop 104/5/536 P.O. Box 56 Avila Beach, CA 93424 Mr. John O'Neill Pillsbury Winthrop Shaw Pittman LLP 2300 N. Street N.W.
Washington, DC 20037
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 information collection.
- 3. PAGE Callaway Plant Unit 1 05000483 1 OF 5
- 4. TITLE Inoperability of A Containment Cooler longer than allowed by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I, ~
iIYNM OKTNME MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR
- - FACILITY NAME DOCKET NUMBER 08 07 2006 2006 007 00 10 06 2006
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[O 20.2201(b)
[I 20.2203(a)(3)(i) 0l 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
Mode 1 0l 20.2201(d)
El 20.2203(a)(3)(ii) 0l 50.73(a)(2)(ii)(A)
[E 50.73(a)(2)(viii)(A) o1 20.2203(a)(1)
El 20.2203(a)(4)
[I 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 [0 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
[I 50.73(a)(2)(x)
[I 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
[I 73.71(a)(4)
E] 20.2203(a)(2)(iv)
[I 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
[I 73.71(a)(5) 100 %
El 20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C) 0l OTHER El 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify in Abstract below or in SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES Callaway Plant received NRC report "Callaway Plant - NRC Integrated Inspection Report 05000483/2006003" on August 7, 2006. The report stated the performance data for the Train A Containment Coolers did not demonstrate the Containment Coolers were capable of performing their required design bases function during the time period between August 16, 2005 and September 17, 2005 due to fouling. The report further indicated the evaluation performed by Callaway Plant prior to returning the containment cooler to service is inadequate. Callaway Licensing and Engineering representatives met with one of the NRC Resident Inspectors on October 23, 2006 to discuss this issue plus the bases and calculations used to reach the Inspectors' conclusions on this issue. The Inspectors analyzed the performance and trending data for Cycle 14 associated with the Containment Coolers and independently performed calculations to verify operability of the Containment Coolers using a method different than that used by Callaway Engineering. The calculations resulted in identifying a data point at which the cooling capacity of the Train A Containment Coolers was not within limits.
Callaway Plant entered Refuel 14 on September 17, 2005. The inside of the cooling coils of the A Containment Cooler was cleaned during the Refuel 14 outage between September 21, 2005 and October 12, 2005. The cooler flow and as left differential pressure readings were measured and recorded after the coil cleaning was complete. However, the as found differential pressure was not measured and recorded prior to cleaning the cooling coils. Because the as found differential pressure for the A Containment Cooler was not procedurally required to be measured and recorded prior to cleaning the A Containment Cooler coils, Callaway Plant could not perform the calculations required to prove the past operability of the Train A Containment Coolers for the time period in question.
(Continued)
(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)
III. CAUSE(S) OF THE EVENT AND CORRECTIVE ACTION(S)
A root cause analysis team has been formed to evaluate the applicable data and determine the root cause of the inoperabilty of the A Containment Cooler and corrective actions to prevent recurrence. A revision to this report will be submitted with the results of this evaluation and any additional corrective actions.
The apparent cause of inoperabilty of the A Containment Cooler is the lack of documentation of the as found differential pressure of the Containment Coolers because of a procedure deficiency, which did not allow for validation of the past operability of the A Containment Cooler.
Corrective actions, which have been performed or are in progress, include:
Cleaned the inside of the cooling coils of A Containment Cooler in Refuel 14.
As found flow balance values for both Containment Cooler trains were found acceptable during Refuel 14.
Continuing monthly trending of Containment Cooler flow values.
Verified Containment Cooler flows did not degrade during Cycles 13 and 14.
Pending actions related to this issue include:
Change surveillance procedure to record as found values for differential pressure of Containment Coolers prior to cleaning the coils.
Reevaluate the required cooling capacity for accident conditions.
Review and revise the current methodology to better predict Containment Cooler performance.
IV.
PREVIOUS SIMILAR EVENTS
No previous similar events have been identified within the past three years.
V. ADDITIONAL INFORMATION
The system and component codes listed below are from the IEEE Standard 805-1984 and IEEE Standard 803A-1984 respectively.
System:
BK Component: CLR The manufacturer of the replacement Containment Cooler coils is Aerofin Corporation.
Manufacturer's Code:
A089