05000528/LER-2005-007, Regarding Potential Loss of Low Pressure Safety Injection (Lps) Due to a Seismic Event

Regarding Potential Loss of Low Pressure Safety Injection (Lps) Due to a Seismic Event

ML060530511
Person / Time
Site:	Palo Verde
Issue date:	02/10/2006
From:	Eubanks C Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05410-CE/SAB/DJS LER 05-007-00
Download: ML060530511 (6)

LER-2005-007, Regarding Potential Loss of Low Pressure Safety Injection (Lps) Due to a Seismic Event

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)(v), Loss of Safety Function
5282005007R00 - NRC Website

text

1 OCFR50.73

,cAFS A subsidiary of Pinnacle West Capital 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 102-0541 0-CE/SAB/DJS February 10, 2006 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit I Docket No. STN 50-528 License No. NPF-41 Licensee Event Report 2005-007-00 Attached please find Licensee Event Report (LER) 50-528/2005-007-00 prepared and submitted pursuant to 10 CFR 50.73. This LER is being submitted for an event or condition that could have prevented fulfillment of a Safety Function to remove residual heat and mitigate the consequences of an accident. Specifically, due to a maintenance error a seismic event could have caused the "A" train of the Low Pressure Safety Injection System to become inoperable.

In accordance with 10 CFR 50.4, a copy of this LER is being forwarded to the NRC Region IV Office and the Senior Resident Inspector. If you have questions regarding this submittal, please contact James A. Proctor, Section ILeader, Regulatory Affairs, at (623) 393-5730.

Arizona Public Service Company makes no commitments in this letter.

Sincerely, CE/SAB/DJS/ca Attachment cc:

B. S. Mallet M. B. Fields G. G. Warnick NRC Region IV Administrator NRC NRR Project Manager for PVNGS NRC Senior Resident Inspector for PVNGS (all w/attachment)

-I

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)

, the NRC may sfor each block) not conduct or sponsor, and a person is not required to respond to, the digits/characters

- o ah lc)Information collection.

3. PAGE Palo Verde Nuclear Generating Station (PVNGS) Unit 1 05000528 1 OF 5

4. TITLE Potential Loss of Low Pressure Safety Injection (LPSI) due to a Seismic Event

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YE-AR YEAR SEUMENTA REV MONTH DkY YEAR 05000 FACILITY NAME DOCKET NUMBER 10 04 2002 2005 - 007 -

00 02 10 2006 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b)

El 20.2233(a)(3)(i) 0 50.73(a)(2)(i)(C) a 50.73(a)(2)(vii) 6 a

20.2201(d)

[

20.2233(a)(3)(ii) 0 50.73(a)(2)(ii)(A) a 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.22)3(a)(4) a 50.73(a)(2)(ii)(B)

[

50.73(a)(2)(viii)(B)

O 20.2203(a)(2)(i) 0 50.36'c)(1)(i)(A) al 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL 0 20.2203(a)(2)(i) al 50.36'c)(1)(ii)(A)

El 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x) o 20.2203(a)(2)(iii)

E 50.36,c)(2)

[1 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv)

El 50.46'a)(3)(ii) 0 50.73(a)(2)(v)(B)

El 73.71(a)(5) 000 1

20.2203(a)(2)(v)

E 50.73:a)(2)(i)(A)

E 50.73(a)(2)(v)(C) al OTHER 20.2203(a)(2)(vi) 0 50.73i:a)(2)(i)(B) 0 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 n7ore space is required, use additional copies of (If more space is required, use additional copies of INRC Form 366A)

The root cause is attributed to poor work practices on the part of the technicians who performed the PM task and their failure to adequately utilize error prevention techniques and prevent events tools relative to Foreign Material Exclusion (FME), e.g., self-checking, peer checking, and two minute drills.

7.

CORRECTIVE ACTIONS

The October 2002 maintenance activity was reviewed with the technicians in the valve services shop and the responsible individuals were coached.

Corrective measures are in progress to address other FME concerns. One of these measures was the establishment of a Site FME coordinator in October 2005. The System Cleanliness and Foreign Material Exclusion Controls pnrcedure is currently being revised to be more prescriptive and user friendly.

Valve work order templates were revised to better emphasize system cleanliness and FME control requirements. Additionally, specific steps have been added to the "instructions" section of the valve work order templates that verify FME requirements are met. The additional requirements and increased focus on FME inspections and associated documentation should preclude future occurrences.

A significant investigation is currently ongoing and any resulting corrective actions will be implemented in accordance with the corrective action program.

8.

PREVIOUS SIMILAR EVENTS

There have been no previous similar licensee events reported in the last three years.

NXU IUKM ibiA(f-UU1)

NRC FORKM 366A (7-2001I)