05000528/LER-2007-005, Inadequate Surveillance Test Procedure Resulted in Failure to Meet Surveillance Requirement

Inadequate Surveillance Test Procedure Resulted in Failure to Meet Surveillance Requirement

ML073040057
Person / Time
Site:	Palo Verde
Issue date:	10/22/2007
From:	Mims D Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05761-DCM/REB LER 07-005-00
Download: ML073040057 (8)

LER-2007-005, Inadequate Surveillance Test Procedure Resulted in Failure to Meet Surveillance Requirement

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
5282007005R00 - NRC Website

text

10 CFR 50.73 L,-ý A subsidiary of Pinnacle West Capital Corporation Palo Verde Nuclear Generating Station Dwight C. Mims Vice President Regulatory Affairs and Plant Improvement Tel. 623-393-5403 Fax 623-393-6077 102-05761-DCM/REB October 22, 2007 Mail Station 7605 P.O. Box 52034 Phoenix, Arizona 85072-2034 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 Nos. STN 50-528, 50-529 and 50-530 License No. NPF 41, NPF 51 and NPF 74 Licensee Event Report 2007-005-00 Attached, please find Licensee Event Report (LER) 50-528/2007-005-00 which reports operation in a condition prohibited by Technical Specifications due to an inadequate procedure for Surveillance Testing.

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 Ray E. Buzard, Section Leader, Regulatory Affairs, at (623) 393-5317.

Arizona Public Service Company makes no commitments in this letter.

Sincerely, DCM/REB/gat Attachment cc:

E. E. Collins Jr.

M. T. Markley G. G. Warnick NRC Region IV Regional Administrator NRC NRR Project Manager - (send electronic and paper)

NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak 9 Diablo Canyon Palo Verde South Texas Project 9 Wolf Creek

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

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

3. PAGE Palo Verde Nuclear Generating Station (PVNGS) Unit 1 05000528 1 OF 7

4. TITLE Inadequate Surveillance Test Procedure Resulted In Failure To Meet Surveillance Requirement

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MNH DY

.YA YERSEQUENTIAL REV MOT A

ERFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBERN NO MONTH DAY YEAR PVNGS Unit 2 05000529 j

FACILITY NAME DOCKET NUMBER 08 21 2007 2007 - 005 -

00 10 22 2007 PVNGS Unit 3 05000530

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)

[I 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii) 1 /[1/1 E 20.2201(d)

C3 20.2203(a)(3)(ii)

El 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)

[I 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

[I 50.73(a)(2)(ix)(A)

10. POWER LEVEL

[] 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)

[1 20.2203(a)(2)(iii)

El 50.36(c)(2)

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

El 73.71(a)(4)

El 20.2203(a)(2)(iv)

[] 50.46(a)(3)(ii)

[I 50.73(a)(2)(v)(B)

El 73.71(a)(5) 100 / 100/100 El 20.2203(a)(2)(v)

[I 50.73(a)(2)(i)(A)

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

El OTHER El 20.2203(a)(2)(vi)

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

Should additional corrective actions, including actions to prevent recurrence, be established following the completion of the root cause analysis review, they will be included in the supplement to this LER.

8.

PREVIOUS SIMILAR EVENTS

LER 1-2007-004-00 reported a condition where existing STPs did not adequately meet a TS SR to ensure the Containment Spray system headers were full of water. The corrective actions from the 004 LER could not have prevented the condition in the current LER due to the length of time the condition described in the current LER has existed nor would the extent of condition from the 004 LER have been expected to identify the condition in the current LER.

LER 1-2004-005-01 reported a condition where a revision to existing STPs resulted in the removal of required testing of Shutdown Cooling isolation valve interlocks. The cause of this event was personnel error during performance of the 1 OCFR 50.59 review for the STP revision. The corrective actions for that event would not have prevented this event due to the different nature of the cause.