ML101310225

Supplement to Amendment Request Associated with Administrative Changes - New Retyped Technical Specification Page

ML101310225
Person / Time
Site:	Palo Verde
Issue date:	04/29/2010
From:	Mims D Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-06179-DCM/RJR
Download: ML101310225 (4)

Text

10 CFR 50.90 LA 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 102-06179-DCM/RJR April 29, 2010 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

References:

1. Letter No. 102-05960-DCM/GAM, dated February 19, 2009, From D.

C. Mims, APS to U.S. Nuclear Regulatory Commission, "Request for Technical specification Amendment and Exemption from 10 CFR 50, Appendix G, to Relocate the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection Enable Temperatures"

2. Letter No. 102-06088-DCM/RJR, dated October 30, 2009, from D.C.

Mims, APS, to U.S. Nuclear Regulatory Commission, "Application for Amendment to License Condition C.(1) Maximum Power Level (Units 1 and 3 only), and Various Technical Specifications to Implement Administrative Changes"

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN-50-528, 50-529, and 50-530 Supplement to Amendment Request Associated with Administrative Changes - New Retyped Technical Specification Page The License Amendments requested in References 1 and 2 contained changes to Technical Specification (TS) page 1.1-6. On February 25, 2010, the NRC issued License Amendment 178 to PVNGS Units 1, 2, and 3 in response to Reference 1.

Reference 2 remains under review with the NRC staff which is required to be revised as a result of the issuance of License Amendment 178.

The enclosure to this letter contains retyped TS page 1.1-6 incorporating the changes approved in License Amendment 178.

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak 0 Diablo Canyon 0 Palo Verde 0 San Onofre 0 South Texas 0 Wolf Creek Oa

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission

Subject:

Administrative Changes - New Retyped TS Page Page 2 No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.

I declare under penalty of perjury that the foregoing is true and correct.

4A1-7 // 0 Executed on (Date)

Sincerely, DCM/RAS/RJR/gat

Enclosure:

Retyped Technical Specification Page 1.1-6 cc:

E. E. Collins Jr.

J. R. Hall L. K. Gibson R. I. Treadway A. V. Godwin T. Morales NRC Region IV Regional Administrator NRC NRR Project Manager + (send electronic and paper)

NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency Arizona Radiation Regulatory Agency

ENCLOSURE Retyped Technical Specification Page 1.1-6

Definitions 1.1 1.1 Definitions (continued)

PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

RATED THERMAL POWER (RTP)

REACTOR PROTECTIVE SYSTEM (RPS)

RESPONSE

TIME SHUTDOWN MARGIN (SDM)

The PTLR is the site specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period.

These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.9.

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3990 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for selected componehts provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a.

All full strength CEAs (shutdown and regulating) are fully inserted except for the single CEA of highest reactivity worth, which is assumed to be fully withdrawn.

With any full strength CEAs not capable of being fully inserted, the withdrawn reactivity worth of these CEAs must be accounted for in the determination of SDM and

b.

There is no change in part strength CEA position..

PALO VERDE UNITS 1,2,3 1.1-6 AMENDMENT NO.