05000483/LER-2007-001, Re Single Train Inoperability in the Essential Service Water System Due to Inadequate Valve Closure Setup
| ML071090161 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/16/2007 |
| From: | Diya F AmerenUE |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| ULNRC05398 LER 07-001-00 | |
| Download: ML071090161 (13) | |
| 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 |
| 4832007001R00 - NRC Website | |
text
AmerenUE Callaway Plant PO Box 620 Fulton, MO 65251 10CFR50.73 April 16, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 1Ameren UF ULNRC05398 Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2007-001-00 Single Train Inoperability in the Essential Service Water System due to Inadequate Valve Closure Setup The enclosed Licensee Event Report, 2007-001-00, is prepared and submitted in accordance with 10CFR50.73 to report an event involving a single train of the Essential Service Water System being Inoperabe due to inadequate valve closure setup.
This letter does not contain new commitments.
Sincerely, Fadi M. Diya Director, Plant Operations FMD/EWH/tdp Enclosure
~2c~
a subsidiary of Ameren Corporation
ULNRC05398 April 16, 2007 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
ULNRC05398 April 16, 2007 Page 3 bcc:
C. D. Naslund A. C. Heflin C. R. Younie D. T. Fitzgerald G. A. Hughes D. E. Shafer S. L. Gallagher (100)
L. M. Belsky (NSRB)
K. A. Mills P. M. Bell msp@nrc.gov ded@nrc.gov LEREvents@inpo.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 and 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 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 10
- 4. TITLE Single Train Inoperability in the Essential Service Water System due to Inadequate Valve Closure Setup
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR SEQUENTIAL REV MIYFACILITY NAME DOCKET NUMBER YEAR NUMBER NO.
MONTH DAY YEAR None FACILITY NAME DOCKET NUMBER 02 28 2007 2007 - 001 -
00 04 12 2007
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
[1 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
MODE 1 [E 20.2201(d)
El 20.2203(a)(3)(ii)
[] 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)
El 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 El 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)
E] 50.36(c)(2)
[E 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[E 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
[E 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)
[I OTHER El 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
[E 50.73(a)(2)(v)(D)
Specify in Abstract below or in SUMMARY OF THE EVENT, INCLUDING DATES AND APPROXIMATE TIMES During a preventive maintenance (PM) task on February 7, 2007, excessive leakby was identified on one of four isolation valves between the non-safety related Service Water (SW) System and the 'A' train safety related Essential Service Water (ESW) system. The scope of the PM includes testing the
'A' train SW to ESW supply cross-connection isolation valves EFHV0023 and EFHV0025; and return isolation valves EFHV0039 and EFHV0041. All four valves are Anchor-Darling Model 2498-30-100, 30 inch butterfly valves [BI - ISV]. During the restoration portion of the PM, any leakage is quantified and compared to calculation M-EF-37, Revision 0, Addendum 3, External Leakage Allowance for ESW Pressure Boundary Leakage, to determine if the leak rate is acceptable.
The SW to ESW cross-connect piping has redundant isolation valves in series, which are tested as a set. During testing of the 'A' train supply line isolation valves on February 7, 2007, EFHV0025 exhibited leakage through the valve. Although the leakage could not be quantified, it was assumed to be in excess of the calculated allowable leakage. A job was initiated to correct the leakage, where it was determined that the valve required approximately six hand wheel turns to place the valve disk in the correctly seated position. There was no evidence of degradation, correction of the leakage required only an adjustment of the valve operator closure limits to ensure the valve disk and valve seat were properly mated when the operator reached the closed position. Following motor operator adjustment, the final leak rate was much less than 1 gpm (approximately one quart per minute) and acceptable.
During testing the valves are isolated and do not affect ESW operability. However, a review was performed to assess potential impact of the identified leakage on past operability of the 'A' ESW train.
A review of work history on EFHV0025 revealed that work performed in July, 2006, could have impacted the valve closure limits. Post Maintenance Testing (PMT) included Motor Operated Valve (MOV) diagnostics testing to set or verify the closure limits. Because this valve is a large butterfly valve without a hard seat, MOV diagnostics are not the preferred method for establishing closure limits as it is difficult to determine the actual fully-seated position without a hard seat to provide indication. As such, since the work performed could have affected the closure limits and the MOV diagnostics may not have established the proper closure limits, the leakage was assumed to have existed since restoration of the valve to service on July 28, 2006.
(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 Summary.
V.
ADDITIONAL INFORMATION
None.