05000530/LER-2007-001, Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Blockage

Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Blockage

ML081120111
Person / Time
Site:	Palo Verde
Issue date:	04/07/2008
From:	Mims D Arizona Public Service Co, Pinnacle West Capital Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05840-DCM/DFH LER-07-001-00
Download: ML081120111 (5)

LER-2007-001, Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Blockage

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
5302007001R00 - NRC Website

text

10 CFR 50.73 APS 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 102-05840-DCM/DFH April 07, 2008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 3 Docket No. STN 50-530 License No. NPF 74 Licensee Event Report 2007-001-00 Attached, please find Licensee Event Report (LER) 50-530/2007-001-00 which reports a condition prohibited by technical specifications resulting from blockage of two containment spray system spray nozzles.

In accordance with 10 CFR 50.4, copies of this LER are being forwarded to the NRC Regional Office, NRC Region IV and the Senior Resident Inspector. If you have questions regarding this submittal, please contact Russell Stroud, Section Leader, Regulatory Affairs, at (623) 393-5111.

Arizona Public Service Company makes no commitments in this letter.

Sincerely, DCM/TNW/DFH/gat Attachment cc:

'E. E. Collins Jr.

NRC Region IV Regional Administrator M. T. Markley 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 0 Diablo Canyon

• Palo Verde 0

South Texas Project

• Wolf Creek

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)

Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 LICENSEE EVENT REPORT (LER)

F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by intemet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to (See reverse for required number of impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not digits/characters for each block) required to respond to, the information collection.

3. PAGE Palo Verde Nuclear Generating Station (PVNGS) Unit 3 05000530 1 OF 4

4. TITLE Condition Prohibited by Technical Specification Resulting from Containment Spray Nozzle Blockage

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NO.

None NUMBER 04 21 o07 2007 1

00 04 07 2008 FACILITY NAME DOCKET 04 2007 0

None NUMBER

9. OPERATING MODE

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

El 20.2201(b)

El 20.2203(a)(3)(i) 0l 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii) 5 El 20.2201(d)

El 20.2203(a)(3)(ii)

E] 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)

E] 20.2203(a)(2)(i)

Cl 50.36(c)(1)(i)(A)

E] 50.73(a)(2)(iii)

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

10. POWER LEVEL El 20.2203(a)(2)(ii)

[] 50.36(c)(1)(ii)(A)

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

[I 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

E] 50.36(c)(2)

El 50.73(a)(2)(v)(A)

[1 73.71(a)(4)

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71(a)(5)

El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

[E OTHER E] 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 NRC Form 366A)

7.

CORRECTIVE ACTIONS

The following corrective actions have been implemented:

" CS train 'A' discharge valve, 3JSIAUV0672 was repaired on December 4, 2007.

" Partial performance of Unit 3 surveillance testing was completed on December 5, 2007, to verify the CS nozzles were unobstructed.

The two nozzles found during the partial surveillance testing to be obstructed were cleaned, inspected and returned to service on December 18, 2007.

• Personnel responsible for evaluating the U3 overfill event were coached on the effects of the overfill event on December 20, 2007. As part of the coaching, actions were discussed on how to prevent recurrence by draining the system though a flange and flushing the header with demineralized water.

" Procedure 40DP-9OP26, Operability Determination and Functional Assessment" has been revised to provide guidelines and instructions for evaluating the operability or functionality of structures, systems and components (SSCs) when a degraded or nonconforming condition is identified. The procedure establishes the methods for performing and documenting the operability decision. Every Palo Verde Action Request (PVAR) that describes a potential problem related to SSCs subject to TS will have an Operability Assessment documented. The Work Control and PVAR processes have procedural guidance to direct initiation of PVARs and require the Work Control Senior Reactor Operator to direct PVARs related to TS SSCs to the the control room for operability review.

The following additional action is planned:

Revise procedure 40OP-9SI02, "Recovery from Shutdown Cooling to Normal Operating Lineup," to include activating an Emergency Response Feature Data Acquisition Display System (ERFDADS) high alarm set points on the CS header.

Engineering will perform a training needs analysis on the issue of overfilling of the Containment Spray headers and potential for evaporation to cause the auxiliary spray nozzles to become clogged. Training will be provided on the ERFDADS modification to prevent recurrence.

Any additional corrective actions taken as a result of this event will be implemented in accordance with the APS corrective action program. If information is subsequently developed that would significantly affect a reader's understanding or perception of this event, a supplement to this LER will be submitted.

8.

PREVIOUS SIMILAR EVENTS

There have been no previous similar events in the past three years that had a similar failure mechanism or that should have prevented this event as a result of previously implemented