05000528/LER-2009-003, Regarding Surveillance Test Procedure Inadequate to Meet the Requirements of TS
| ML092090194 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/13/2009 |
| From: | Mims D Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06032-DCM/DFH LER 09-003-00 | |
| Download: ML092090194 (6) | |
| 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)(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 |
| 5282009003R00 - NRC Website | |
text
10 CFR 50.73 A LPS A subsidiary of Pinnacle West Capital Corporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Regulatory Affairs and Plant Improvement Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06032-DCM/DFH July 13, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3 Docket No. STN 50-528, 50-529 and 50-530 License No. NPF-41, NPF-51 and NPF-74 Licensee Event Report 2009-003-00 Enclosed, please find Licensee Event Report (LER) 50-528/2009-003-00 that has been prepared and submitted pursuant to 10 CFR 50.73. This LER reports a condition where PVNGS did not fully meet the requirements of Technical Specification Surveillance Requirement 3.8.9.1. Specifically, the correct supply breaker alignment for the Class 1 E 125 VDC distribution panels was not verified.
In accordance with 10 CFR 50.4, copies of this LER are being forwarded to the Nuclear Regulatory Commission (NRC) Regional Office, NRC Region IV and the Senior Resident Inspector. If you have questions regarding this submittal, please contact James Proctor, Section Leader, Regulatory Affairs, at (623) 393-5730.
Arizona Public Service Company makes no commitments in this letter.
Sincerely, DCM/JAP/DFH/gat Enclosure cc:
E. E. Collins Jr.
NRC Region IV Regional Administrator J. R. Hall -
NRC NRR Project Manager - (send electronic and paper)
R. I. Treadway NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- San Onofre - South Texas
- Wolf Creek
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010
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- 3. PAGE Palo Verde Nuclear Generating Station (PVNGS) Unit 1 05000528 1 OF 5
- 4. TITLE Surveillance Test Procedure Inadequate to Meet the Requirements of TS
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE 1
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR REV FACILITY NAME DOCKET NUMBER MA YEAR ENUMBER NO.
MONTH DAY YEAR PVNGS Unit 2 05000529 FACILITY NAME DOCKET NUMBER 05 13 2009 2009 - 003 -
00 07 13 2009 PVNGSUnit3 05000530
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[1 20.2201(b)
. El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1 /1 /5 [1 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A)
E] 20.2203(a)(1)
E] 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
E] 20.2203(a)(2)(i)
[] 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
[j 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL U 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)
[] 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
[I 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100 / 100 / 0 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 (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) 01AP-OAP01, Procedure Process, was revised to clearly define the roles and responsibilities of the organizations reviewing changes to station procedures.
In addition to the above actions, a Component Design Basis Review (CDBR) project is currently in progress to identify and correct latent design basis deficient conditions.
- 8.
PREVIOUS SIMILAR EVENTS
There was one similar event reported in LER 50-528/2007-003 where Auxiliary Feedwater Pump AFA-P01 Monthly Valve Alignment did not adequately meet its intent to satisfy TS Surveillance Requirement (SR) 3.7.5.1 for position verification of the steam admission bypass valves to Auxiliary Feedwater (AFW) Pump AFA-P01. Similar to the event described in this LER, the condition was the failure to incorporate the new SR into the ST procedure.
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PRIN I EU UN XEUYULEU PAI-'EX NRC; FORM 366A (9-2007)
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