05000528/LER-2006-001, Re Containment Spray Inoperable in Mode 4 with RCS Pressure Greater than 385 Psla

Re Containment Spray Inoperable in Mode 4 with RCS Pressure Greater than 385 Psla

ML061450321
Person / Time
Site:	Palo Verde  (NPF-041)
Issue date:	05/18/2006
From:	Eubanks C Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05495-CE/CKS/DLK LER 06-001-00
Download: ML061450321 (7)

LER-2006-001, Re Containment Spray Inoperable in Mode 4 with RCS Pressure Greater than 385 Psla

Event date:
Report date:
5282006001R00 - NRC Website

text

10 CFR 50.73 LAOS A subsidiary of Pinnade West Capitol Corporation Palo Verde Nuclear Generating Station Cliff Eubanks Vice President Nuclear Operations Tel (623)393-6116 Fax (623) 393-6077 Mail Station 7602 PO Box 52034 Phoenix, Arizona 85072-2034 1 02-05495-CE/CKS/DLK May 18, 2006 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528 License No. NPF 41 Licensee Event Report 2006-001-00 Attached please find Licensee Event Report (LER) 50-52812006-001-00 prepared and submitted pursuant to 10 CFR 50.73. This LER reports conditions prohibited by Technical Specifications where Unit I operated the reactor coolant system with pressurizer pressure above 385 pounds per square inch absolute (psia) in Mode 4 without both trains of Containment Spray Operable (two events).

In accordance with 10 CFR 50.73(d), copies of this LER are being forwarded to the NRC Regional Office, NRC Region IV and the PVNGS Senior Resident Inspector. If you have questions regarding this submittal, please contact James A. Proctor, Section Leader, Regulatory Affairs, at (623) 393-5730.

Arizona Public Service Company makes no commitments in this letter.

Sincerely, CE/CKS/DLK/gt Attachment cc:

B. S. Mallett M. B. Fields G. G. Wamick NRC Region IV Regional Administrator NRC NRR Project Manager - (send electronic and paper)

NRC Senior Resident Inspector for PVNGS

I NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06130/2007

(-2004)

, the NRC may digits/characters for each block) not conduct or sponsor, and a person i not required to respond to, the 3 PAGE Palo Verde Nuclear Generating Station Unit 1 05000528 1 OF 6

4. TITLE Containment Spray Inoperable in Mode 4 with RCS Pressure greater than 385 psia

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILMES INVOLVED SEQU-ENTIAL___

REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER REV MONTH DAY YEAR None 05000 FACILITY NAME DOCKET NUMBER 03 20 2006 2006

- 001 -

00 05 18 2006 None 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 0 20.2201(b) 0 20.2203(aX3XI) 0 50.73(aX2XIXC) 0 50.73(aX2XvIi) 4 0 20.2201(d) 0 20.2203(aX3XIi) 0 50.73(aX2XiiXA) 0 50.73(aX2XviiiXA) o0 20.2203(aXl) 03 20.2203(aX4) 0 50.73(aX2XiIXB) 0 50.73(aX2XvIii)(B) o 20.2203(aX2XI) 0 50.36(cXIXIXA) 0 50.73(a)(2XI) 0 50.73(aX2XIx)(A)

10. POWER LEVEL 0

20.2203(aX2Xii) a3 50.36(cXIXiiXA)

El 50.73(aX2XIvXA) 0 50.73(aX2Xx) o3 20.2203(aX2XIiI) 0 50.36(cX2) 0 50.73(aX2XvXA)

E3 73.71(aX4) oC 20.2203(aX2Xiv) 0 50.46(aX3Xii) 0l 50.73(aX2XvXB) 0 73.71(aX5) 0 3 20.2203(aX2Xv) 0 50.73(aX2XIXA) a 50.73(aX2Xv)(C) 0 OTHER 20.2203(aX2Xvi) 0 50.73(aX2)(IXB)

El 50.73(aX2XvXD)

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 (if more space is required, use additional copies of NRC Form 366A)

LER 529/2005-002 reported a condition in which a Mode change occurred with one of two required Low Pressure Safety Injection (LPSI) trains being inoperable due to a degraded mechanical pump seal. The cause of this event was attributed to an equipment problem.

LER 528/2005-002 reported a condition in which a Mode change occurred with a safety injection valve out of position. The cause of the event was attributed to cognitive personnel error.

The causes for these previously reported events were different than the root cause of the event discussed in this LER. As such, the corrective actions taken as a result of these previously reported events would not have prevented the event discussed in this LER.

This LER (50-528/2006-001-00) is related to the violation of Technical Specification 3.0.4 reported in LER 50-528/2006-002-00 in that the events described in both LERs had the same root cause and occurred during the same Unit I start up.

NRI, FORM 40A(I-WW1