05000528/LER-2005-009, Re Technical Specification Violation for Operation Without Both Reactor Coolant System Loops Operable

Re Technical Specification Violation for Operation Without Both Reactor Coolant System Loops Operable

ML061570211
Person / Time
Site:	Palo Verde
Issue date:	05/22/2006
From:	Eubanks C Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05498-CE/SAB/JAP/REB LER 05-009-00
Download: ML061570211 (12)

LER-2005-009, Re Technical Specification Violation for Operation Without Both Reactor Coolant System Loops Operable

Event date:
Report date:
5282005009R00 - NRC Website

text

10 CFR 50.73 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 102-05498-CE/SAB/JAP/REB May 22, 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"09-00 Attached please find Licensee Event Report (LER) 50-528/2005-009-00 prepared and submitted pursuant to 10 CFR 50.73. The LER reports a technical specification violation for reactor coolant system loops being inoperable.

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/SAB/JAP/REBlgt 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 zYt~ ~s

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 digis/carater foreac blck)information collection.

3. PAGE Palo Verde Nuclear Generating Station Unit 1 05000528 1 OF 11

4. TITLE Technical Specification Violation For Operation Without Both Reactor Coolant System Loops Operable

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED I

FACII~

fYNM KTNME MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR None 05000 NUMBER NO.

Nn 50 FACILITY NAME DOCKET NUMBER 12 21 2005 2005 - 009 -

00 05 22 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)

[3 20.2203(aX3Xi)

[3 50.73(aX2)(iXC)

[3 50.73(aX2Xvii) 3 0] 20.2201(d)

[3 20.2203(aX3XiI)

[3 50.73(a)(2XilXA)

[] 50.73(aX2XvIlXA) o 20.2203(a)(1)

[3 20.2203(a)(4)

[0 50.73(a)(2XiIXB) 0 50.73(aX2XvliiXB)

[o 20.2203(a)(2Xi) 0 50.36(cXIXiXA)

[3 50.73(aX2Xivi)

[3 50.73(aX2Xix)(A)

10. POWER LEVEL 0] 20.2203(a)(2)(11)

[] 50.36(cX1Xii)(A)

[3 50.73(aX2XivXA)

[3 50.73(aX2Xx)

[o 20.2203(aX2)(ii) 0 50.36(cX2)

[3 50.73(aX2)(v)(A)

[0 73.71(aX4) o 20.2203(aX2XIv)

[I 50.46(aX3)(il) 0 50.73(aX2XvXB)

[0 73.71(a)(5) 000 0 20.2203(aX2Xv)

[I 50.73(aX2XI)(A) 0 50.73(aX2XvXC)

[I OTHER [3 20.2203(aX2)(vI) 0 50.73(aX2Xi)(B)

[I 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 (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) existence of this predominant vibration frequency in Units 2 and 3 suggests that the latent design defect also exists in the train 'A' SDC suction line in these two units.

The train B SDC suction lines in all three units are unaffected because the associated suction isolation valve is located closer to the hot leg effecting a higher fundamental acoustic frequency.

If substantial information is identified in the completed investigation report that significantly changes the description, consequences, or cause of the condition as described in this LER, then an LER supplement will be submitted.

7.

CORRECTIVE ACTIONS

A modification of the Unit 1 Train A SDC suction line piping and relocation of valve SI 651 is in progress to change the fundamental frequency of the acoustic resonator formed by the SDC suction line. Design validation testing and vibration monitoring during restart and for the balance of UI C13 will evaluate the effectiveness of this modification. This modification will be completed prior to Unit I returning to operation.

Actions for Units 2 and 3 are under evaluation.

If the completed investigation report has substantial changes in the corrective actions for the condition, then an LER supplement will be submitted.

8.

PREVIOUS SIMILAR EVENTS

There has been no similar event reported to the NRC by APS in the last three years.

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