ML14184B413
| ML14184B413 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/27/2014 |
| From: | Weber T N Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 102-06877-TNW/TMI | |
| Download: ML14184B413 (8) | |
Text
- taps 10 CFR 50.59 I10 CFR 72.48Palo Verde102-06877-TNW/TMI Nuclear Generating StationP.O. Box 52034June 27, 2014 Phoenix, AZ 85072Mali Station 7636ATTN: Document Control Desk Tel: (623) 393-5764U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, & 3 and Independent Spent Fuel Storage Installation (ISFSI)Docket Nos. STN 50-528/529/530 and 72-4410 CFR 50.59, 10 CFR 72.48, and Commitment ChangeAnnual Reports and Notifications Enclosed please find the Arizona Public Service Company (APS) 10 CFR 50.59 and10 CFR 72.48 report for January 1, 2013 through December 31, 2013. TheCommitment Change Report is for the period of January 1, 2013, throughJune 27, 2014.In accordance with 10 CFR 50.59(d)(2),
APS is providing a brief description and summaryof the evaluations required by 10 CFR 50.59(d)(1) for each change completed during theperiod. This report contains the evaluations written during 2013, regardless of theimplementation status of the evaluated action, and is included as an enclosure to thisletter.In accordance with 10 CFR 72.48(d)(2),
APS is reporting that there were no changescompleted during the period that were required to be reported pursuant to 10 CFR 72.48.In accordance with the APS commitment management
- program, APS is reporting oneNRC commitment change made during the period that was not otherwise reported.
TheCommitment Change Report is included as Enclosure 2 of this letter.No new commitments are being made to the NRC by this letter. Should you needfurther information regarding this submittal, please contact Thomas N. Weber,Regulatory
- Affairs, Department Leader, at (623) 393-5764.
Sincerely, Thomas N. WeberDepartment Leader, Regulatory AffairsTNW/TMJ/hsc
Enclosures:
- 1. 10 CFR 50.59 and 10 CFR 72.48 Report January 2013 -December 20132. Commitment Change Report January 2013 -June 2014A member of the STARS (Strategic Teaming and Resource Sharing)
Alliance e7 Ce 7Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- Wolf Creek 102-06877-TNW/[IMJ June 27, 2014NRC Document Control DeskAnnual 10 CFR 50.59, 10 CFR 72.48, and Commitment Change ReportPage 2cc: M. L. DapasJ. K. RankinM. M. WatfordM. A. BrownV. L. OrdazNRC Region IV Regional Administrator NRC NRR Project Manager (electronic and hard copy)NRC NRR Project Manager (electronic and hard copy)NRC Senior Resident Inspector for PVNGS (electronic)
- Director, Division of Spent Fuel Storage and Transportation ENCLOSURE IPALO VERDE NUCLEAR GENERATING STATION10 CFR 50.59 and 10 CFR 72.48 ReportJanuary 2013 -December 2013 10 CFR 50.59 and 10 CFR 72.48 REPORT (JANUARY 2013 through DECEMBER 2013)Log Doc Doc Number Description SummaryTypeE-1 0-0007 LDCR 1 0-F047 Evaluates the third cycle use of eight (8) This change does not require priorRev. 2 Westinghouse lead fuel assemblies (LFAS) in the NRC approval in accordance withPalo Verde Unit 3 Cycle 18 (U3C18) Core. The 10 CFR 50.59(c)(1).
scope includes, the 4 degree F increase in peakclad temperature in the emergency core coolingsystem performance evaluation models and theincrease in peak cladding oxidation upon fueldesign limits.E-1 1-0007 LDLB 15.6.2.ROOO Addresses changes to the evaluation of double- This change does not require priorRev. 1 LDCR 2011-F029 ended break of a letdown line outside containment NRC approval in accordance withdescribed in PVNGS UFSAR chapter 15.6.2. 10 CFR 50.59(c)(1).
LDCR 2012-F003 CALC 13-NC-ZY-0247 R.009E-1 2-0001 PROC 40AL-9RL4A R.035 Temporarily lowers the Pressurizer Pressure This change does not require priorRev. 1 Control System (PPCS) master setpoint in NRC approval in accordance withresponse to Pressurizer Safety Valve (PSV) 10 CFR 50.59(c)(1).
leakage.E-1 2-0006 PROC 40ST-9EC03 R. 15 Reviews the compensatory measures to be taken This change does not require priorRev. 0 PROC 40AP-9ZZ20 R. 05 in the event of a loss of cooling function of the NRC approval in accordance withEssential Safety Feature (ESF) equipment room 10 CFR 50.59(c)(1).
Air Handling Units (AHUS) HJA-Z04 or HJB-Z04.Reviews the DMWO 3270069 Reviews the replacement of the -Legacy This change does not require priorRev. 0 Honeywell Plant Computer (PC) system and NRC approval in accordance withassociated software with a new Rolls Royce 10 CFR 50.59(c)(1).
System. The proposed change is applicable toUnits 2 and 3.E-1 3-0002 DMWO 2579403 Reviews the replacement of the Legacy Core This change does not require priorRev. 0 Monitoring Computer portion of the Plant NRC approval in accordance withMonitoring System (PMS), including the Honeywell 10 CFR 50.59(c)(1).
computer system along with the associated process input units (PlUs) and local controlstations.
The CMC processor will be replaced withIntel based redundant computers.
This change alsoincludes software replacement.
Enclosure 1Page I of 2 10 CFR 50.59 and 10 CFR 72.48 REPORT (JANUARY 2013 through DECEMBER 2013)Log Doc Doc Number Description SummaryTypeE-13-0006 VDP Al 7994 Reviews the addition of Westinghouse Electrical This change does not require priorRev. 0 Company (WEC) suppliers documents to the NRC approval in accordance withPVNGS Design Basis. This included the stress and 10 CFR 50.59(c)(1).
fatigue analysis for the Unit I Reactor PressureVessel (RPV) bottom head shell and BottomI_ Mounted Instrument (BMI) nozzles.ACRONYM N/ABBREVIATION LISTDFWO Deficiency Work OrderDMWO Design Modification Work OrderLDCR Licensing Document Change RequestCECOR Combustion Engineering Core (CECOR) method for estimating the Palo Verde reactor power distributions NOTE: There were no 10 CFR 72.48 evaluations in 2013.Enclosure 1Page 2 of 2 ENCLOSURE 2Commitment Change ReportJanuary 2013 -June 2014 COMMITMENT CHANGE BOP ESFAS TESTINGThe commitment change related to BOP ESFAS testing frequency below wasfinalized June 25, 2014.Commitment Number: RCTSAI 7673Source Document(s):
Action H Response (ANPP-19591-PE PA6) APSresponse to open items concerning PVNGS ESF load sequencer (Dated 12-03-81)
Existing Commitment
==
Description:==
BOP ESFAS System will be fully tested at least every 18 months at time ofrefueling.
Tests will include testing of all sequence modes and ESFAS logiccircuits.
Sequencer timing will also be checked.Revised Commitment
==
Description:==
BOP ESFAS System will be fully tested at periodicities defined by thesurveillance frequency control program.
Tests will include testing of all sequencemodes and ESFAS logic circuits.
Sequencer timing will also be checked.Justification of Change:The commitment stated in RCTSAI 7673 was originally made by APS in a letterdated December 3, 1981. This letter addressed the APS responses to openitems from a design review meeting between the NRC and APS which addressed questions about the reliability and design of the BOP ESFAS sequencer.
Reviewof this letter and related documents from the PVNGS Safety Evaluation Report(SER) shows that the NRC concerns that led to the commitment were focused onthe reliability of this first of a kind microprocessor based sequencer system in thePVNGS electrical power distribution systems.
Section 8.4.6 of the UFSARSafety Evaluation Report and Supplement 5 also address the Load Sequencer.
The NRC Staff concluded that the ESF load sequencer design was acceptable.
License Amendment 188 implemented the Surveillance Frequency ControlProgram (SFCP) at PVNGS (Technical Specification 5.5.18).
The programprovides an NRC-approved process for changing the frequency of testing forsurveillance requirements.
Changes to the BOP ESFAS System Testing wereaddressed in Surveillance Test Risk-Informed Documented Evaluations (STRIDEs) 7, 15 and 16. STRIDEs 7, 15 and 16 provide justification to changethe frequency of testing from 18 months to 18 months on a STAGGERED testbasis (one train per outage).Enclosure 2Page 1 of 2 COMMITMENT CHANGE BOP ESFAS TESTING (continued)
The reliability of the components (discussed in the deterministic review inSTRIDE 7) summarizes the results for a 10 year test history ending in March2012. During the review period, there were 46 performances of Integrated Safeguards
- Testing, including A and B trains in all 3 Units. Each of thesesurveillances encompassed the testing/verification of 164 components.
Thus,the total number of component tests during the review period was 46 x 164 =7,544 individual component tests/verifications.
Source Documents/Databases were reviewed to identify any work activities that were initiated during theperformance of the surveillances.
The work activities were reviewed to identifyany deficiencies or failures with the components that could be considered assurveillance test failures.
Of this, there were 16 such instances in the 10 yearperiod. When compared to the total number of 7,544 individual component testsover the last 10 years, the 16 failures noted represent an extremely low 0.2%failure rate. Of the 16 failures identified, none were the result of a loadsequencer failure.
Thus, the success rate of the surveillance tests has beenexcellent.
No failures were found that had causal factors either associated with,or affected by, testing frequency.
Enclosure 2Page 2 of 2