ML101530485
| ML101530485 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/21/2010 |
| From: | Weber T Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| 102-06196-TNW/KAR | |
| Download: ML101530485 (14) | |
Text
10 CFR 50.59, 10 CFR 72.48 Thomas N. Weber Mail Station 7636 Palo Verde Nuclear Department Leader, Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 102-06196-TNW/KAR ATTN: Document Control Desk May 21, 2010 U.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 72-44 Twenty-Four Month 10 CFR 50.59, 10 CFR 72.48 and Commitment Change Reports (January 2009 - December 2009)
Enclosed please find Arizona Public Service Company's (APS') 10 CFR 50.59, 10 CFR 72.48 and Commitment Change Reports for the period of January 1, 2009 through December 31, 2009.
In accordance with 10 CFR 50.59(d)(2), APS is providing a brief description of each change and a summary of the evaluation required by 50.59(d)(1) for each change. This report contains all evaluations written during 2009, regardless of the implementation status of the evaluated action and is included as Enclosure I to this letter.
In accordance with 10 CFR 72.48(d)(2), APS is reporting that there were no changes completed during the period that were required to be reported pursuant to 72.48, as stated in Enclosure 2 to this letter.
In accordance with commitment management program requirements, APS is reporting three NRC commitment changes made during the period that were not otherwise reported. The report of commitment changes is included as Enclosure 3 to this letter.
No new 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.
Sincerely, TNW/RAS/KAR/gat A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway ° Comanche Peak - Diablo Canyon
- Palo Verde
- San Onofre
- South Texas ° Wolf Creek A
5
U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Annual 10 CFR 50.59, 10 CFR 72.48 and Commitment Change Report (January 2009-December 2009)
Page 2 Enclosure 1.
2.
3.
cc:
E. E. Collins J. R. Hall L. K. Gibson R. I. Treadwa E. W. Brach Acronym/Abbreviation List, 10 CFR 50.59 Report 10 CFR 72.48 Report Commitment Change Report Jr.
NRC Region IV Regional Administrator NRC NRR Project Manager NRC NRR Project Manager
]y NRC Senior Resident Inspector for PVNGS Director, Spent Fuel Project Office
ENCLOSURE 1 PALO VERDE NUCLEAR GENERATING STATION ACRONYMIABBREVIATION LIST, and 10 CFR 50.59 Report January 2009 - December 2009
ACRONYMN / ABBREVIATION LIST (Acronyms included in calculation or document numbers are not included in this list)
ACE ACT AOR Calc CENTS CRAI CRDR CS DFWO DMWO ECCS EDC EDG EPAC FWLBLOPSF HDP HPSI LDCR LOCA LOF LPSI LTA MSLB MTC NFM NRC OBE PAC PC PLC/HMI PLCSM PLS PO-EDC PROC PSV PVAR PVNGS RP RSG RTD RWT SABD SBCSM Apparent Cause Evaluation Action Analysis of Record Calculation Combustion Engineering Nuclear Transient Simulation Condition Report Action Item Condition Report/Disposition Request Containment Spray Deficiency Work Order Design Modification Work Order Emergency Core Cooling System Engineering Document Change Emergency Diesel Generator Equivalence Table for PAC Feedwater Line Break with Loss of Offsite Power and Single Failure Heater Drain Pump High Pressure Safety Injection Licensing Document Change Request Loss of Coolant Accident Loss of Flow Low Pressure Safety Injection Lead Test Assembly Main Steam Line Break Moderator Temperature Coefficient Nuclear Fuel Management Nuclear Regulatory Commission Operating Basis Earthquake Physics Assessment Checklist Protective Clothing Programmable Logic Controller with Human Machine Interface Pressurizer Level Control System Malfunction Portable Laundry Skid Paper Only Engineering Document Change Procedure Primary Safety Valve Palo Verde Action Request Palo Verde Nuclear Generating Station Radiation Protection Replacement Steam Generator Resistance Temperature Detector Refueling Water Tank Safety Analysis Basis Document Steam Bypass Control System Malfunction
ACRONYMN / ABBREVIATION LIST (continued)
(Acronyms included in calculation or document numbers are not included in this list)
SBLOCA SBOG SBOGTG SCFM SDC SDOC SG SIRCP SOE TMOD TRM TTA UFSAR VDP VTD Small Break Loss of Coolant Accident Station Blackout Generator Station Blackout Gas Turbine Generator Standard Cubic Feet per Minute Shutdown Cooling Supplier Document Steam Generator Startup of an Inactive Reactor Coolant Pump Sequence of Events Temporary Modification Technical Requirements Manual Sodium Tolytriazole (Copper corrosion inhibitor)
Updated Final Safety Analysis Report Vendor Document Package Vendor Technical Document
10 CFR 50.59 Report (January 2009 through December 2009)
Log Doc Type Doc Number Description Summary E-08-0005 DMWO 2578794 The proposed change is to replace the following This change does not require prior NRC Rev 1 and 3 solenoid operated valves with motor operated approval in accordance with valves in Units 1, 2, 3: JSGAUVO134A, S/G #1 10CFR50.59(c)(1).
Steam Supply to AFA-P01 Bypass Valve and JSGAUV0138A, S/G #2 Steam Supply to AFA-P01 Bypass Valve.
E-08-0014 Analysis of TA-13-C00-2002-The new analysis of record (AOR) is changing This change DOES require prior NRC Record 002, Rev 05 various input parameters in accordance with approval to implement changes.
current plant design, is using the latest revision of applicable computer codes, and is removing discretionary conservatisms in the previous AOR.
CRDR# 2830075.
E-08-0022 TRM TRM 3.8.103 A new section is being added to the Technical This change does not require prior NRC LDCR LDCR 07-R004 Requirements Manual (TRM Section 3.8.103) to approval in accordance with specify the TRM requirements for the Station 10CFR50.59(c)(1).
Blackout Generator (SBOG) system. The SBOG system is defined to include the two gas turbine generators (SBOGs) and the following support systems: fuel oil, lube oil, diesel hydraulic start and electrical distribution. Rev. 1 of this evaluation is being issued to correct the the stated TLCO requirements for when both Station Blackout Generators (SBOGs) must be operable.
E-09-0001 Temp Mod and DW-08-001 Rev 0, A temporary drain valve is to be installed on the This change does not require prior NRC Temporary DW-14 to WROP-DW system vacuum degasifier air water approval in accordance with Instruction 8DWO1 Rev 17 separator. Temporary instruction will be issued for 10CFR50.59(c)(1).
it's use.
E-09-0002 LDCR 08-F052, Rev 0 Clarify UFSAR Sections 8.3.1.1.4.3 (EDG Tripping This change does not require prior NRC Devices) and 9.5.7.3 (EDG Lube Oil System approval in accordance with Safety Evaluation) to include statements that EDG 10CFR50.59(c)(1).
control air must be available for the "EDG overspeed", "low lube oil pressure", "generator differential", and "manual trip at the control panel" engine protective trips to be in effect.
E-09-0004 DFWO 3315351 This DFWO documents the impact on the Reactor This change does not require prior NRC Coolant System and connected NSSS systems of approval in accordance with a Use-As-Is Disposition for leaving degraded 10CFR50.59(c)(1).
Reactor Coolant Pump (RCP) diffuser wedge
10 CFR 50.59 Report (January 2009 through December 2009)
Log Doc Type Doc Number Description Summary assemblies in-place for Unit-3 RCP 1A.
E-09-0005 DFWO 3322244 Replace the damaged NEMA 4 cast iron junction This change does not require prior NRC box with a NEMA 12 sheet metal junction box for approval in accordance with EDG 3A.
E-09-0006 DMWO 3190342 The replacement of the PVNGS Units 1, 2 and 3 This change does not require prior NRC reactor vessel closure heads (RRVCH) requires approval in accordance with modifications to site facilities. These changes are 10CFR50.59(c)(1).
covered by DMWO 3190342 and include temporary modifications to the RRVCH haul route and protection for plant commodities that are located alongside and/or under the haul route, as required. DMWO 3190342 also covers installation and subsequent removal of the Elevated Cantilevered Handling Device (ECHD) and Erection Crane, both installed outside of Containment adjacent to the equipment hatch/missile shields.
E-09-0007 DMWO 3095435 Palo Verde will install a Simplified Head Assembly This change does not require prior NRC (SHA) that is designed to reduce the time, approval in accordance with associated dose, and number of polar crane picks 10CFR50.59(c)(1).
for the disassembly and reassembly of the reactor vessel closure head (RVCH) as well as to increase personnel safety.
E-09-0008 DMWO 2992340 Palo Verde Units 1, 2, and 3 will install a This change does not require prior NRC Replacement Reactor Vessel Closure Head approval in accordance with (RRVCH) to include a new reactor head (including 10CFR50.59(c)(1).
inconel 690 nozzles and reactor head vent nozzle extension), new CEDM housings, new CEDMs, new reactor head insulation, and new Reactor Vessel Level Monitoring System (RVLMS) housings.
E-09-0010 DMWO 2650413, Rev 0 This change adds automatic static transfer This change does not require prior NRC switches to Unit 1 inverters 1 EPNAN 11, approval in accordance with 1EPNBN12, 1EPNCN13, and 1EPNDN14.
10 CFR 50.59 Report (January 2009 through December 2009)
Log Doc Type Doc Number Description Summary E-09-0012 Calc N001-1900-01331, This Screening/Evaluation applies to the three This change does not require prior NRC LDCR REV2 (CN-LAM-Westinghouse LOCA related calculations - LOCA approval in accordance with 09-33, Rev. 00),
Checklist calculations MN725-A01518 Rev. 02 10CFR50.59(c)(1).
MN725-A01518,
[CN-OA-05-53, Rev. 02 and CN-OA-05-53, Rev.
REV 2 (CN-OA 03] and LBLOCA calculation N001-1900-01331 53, Rev. 02 and Rev. 02 [CN-LAM-09-33, Rev.00] and the LDCR CN-OA-03-53, Rev.
2009-F063, which is based on the LBLOCA
- 03) analysis.
LDCR 2009-F063 E-09-0013 Calc RDROP-15.4.3-TA, The WEC calculation, MN725-A00206, Rev 3, Full This change does not require prior NRC Rev. 0, NA-13-COO-Length CEA Drop (A-PV2-FE-0169), (Ref. 2) was approval in accordance with 2002-005, Rev 02, reformatted to the AAOR project standards and 10CFR50.59(c)(1).
TA-13-COO-2005-005, brought in house as an APS calculation, RDROP-Rev 05, and 40AO-15.4.3-TA, Rev. 0 (Ref. 1). In the process, a 9ZZ 11, Rev 14 number of errors were identified and corrected.
The impact of these corrections are changes to the COLR figures 3.1.5-1 and 3.2.4-1 and PAC limits on the sub-group drop distortion factor. The changes to COLR figure 3.1.5-1 affect procedure, 40AO-9ZZ1 1, CEA MALFUNCTIONS Rev 13, (Ref. 3). This 50.59 covers changes discussed in Appendix A of RDROP-15.4.3-TA, Rev. 0, and NA-13-COO-2002-005, Rev 02, and applicable changes to TA-1 3-COO-2005-005, Rev 05, and 40AO-9ZZ1 1, Rev 13. Appendix E of Ref. 1are the proposed changes to the UFSAR 15.4.3.
E-09-0014 LDCR LDCR 08-F049 LDCR 08-F049 is being submitted to update This change does not require prior NRC UFSAR Section 11.2 to reflect the current approval in accordance with operation of the Liquid Radwaste System (LRS) 10CFR50.59(c)(1).
as described in the associated LRS operating procedures and design drawings.
E-09-0015 Calc TA-1 3-COO-2004-Revision 03 of TA-13-COO-2004-003 (PVNGS This change does not require prior NRC LDCR 003, Rev. 03, Chapter 15 EAB & LPZ Dose Consequences) approval in accordance with LDCR 2009-FO16 corrects several inputs for the offsite radiological 10CFR50.59(c)(1).
dose calculations in Revision 01 and changes the calculation of an internal Dose Conversion Factor.
This screening also addresses UFSAR updates in LDCR 2009-F016.
10 CFR 50.59 Report (January 2009 through December 2009)
Log Doc Type
[Doc Number
] Description Summary E-09-0016 Analysis Analysis EXCESSLOAD-TA Rev. 0.
Analysis EXCESSLOAD-TA Rev. 0, "Augmented Analysis of Record for the Excess Load Events in UFSAR Chapters 15.1.1, 15.1.2, 15.1.3 and 15.1.4." was generated as part of the Augmented Analysis of Record Project. This 10 CFR 50.59 includes the applicable changes made in analysis EXCESSLOAD-TA Rev. 0., in addition to the proposed changes to the UFSAR described in ADDendix E of the analysis.
This change does not require prior NRC approval in accordance with 10CFR50.59(c)(1).
ENCLOSURE 2 10 CFR 72.48 Report January 2009-December 2009
10 CFR 72.48 Annual Report (January 2009 - December 2009)
No changes were made per 10 CFR 72.48 from January 1, 2009 through December 31, 2009 that are required to be reported.
ENCLOSURE 3 Commitment Change Report January 2009-December 2009
Regulatory Commitment/Action Change Evaluation Summary COMMITMENT CHANGE A The commitment clarification below was made on March 25, 2009.
Commitment Number:
RCTSAI 8994 Source Document(s):
Letter ANPP-30760 TQ/KLM Existing Commitment
Description:
Molded case circuit breakers associated with safe-shutdown power sources will be inspected and tested on a periodic basis.
Revised Commitment
Description:
Molded case circuit breakers associated with safe-shutdown power sources will be inspected on a periodic basis. All non-single pole molded case breakers will be tested on a periodic basis.
Justification of Change:
GE Letter GE-APS-090484-BG1 dated Sept 4, 1984, and 84-002-419.3 dated May 10, 1984, describes the overall negative impact on breaker life and function through instantaneous trip testing.
COMMITMENT CHANGE B The commitment clarification below was made on August 13, 2009.
Commitment Number:
RCTSAI 12022 Source Document(s):
CRAI 3346129 Existing Commitment
Description:
Provide Preventive Maintenance (PM) tasks for calibration of the class 1 E switchgear UV & DIG protective relays required during each refueling outage.
Revised Commitment
Description:
Provide PM tasks for calibration of the class 1 E switchgear UV & D/G protective relays required every two (2) years.
Justification of Change:
The NRC-endorsed EPRI PMBD 2.0 template states that the recommendation for critical relays in severe environments is two years as-found testing and calibration. The recommendation for mild environments, like these relays are in, is four years. In addition, PVNGS operating experience does not indicate a history of failures attributed to the optimized PM frequency.
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Regulatory CommitmentlAction Change Evaluation Summary COMMITMENT CHANGE C The commitment below was closed on August 28, 2009.
Commitment Number:
RCTS 13226 Source Document(s):
CRDR 3324447,161-00108-JGH, 455-00150-MSB, 450-00138-JHH Existing Commitment
Description:
Design change packages will be developed to provide 1 E power to containment temperature and humidity detectors, RMS mini-computer, containment radwaste sump level indication and key radiation monitors that are used in the Diagnostic flow chart. Note that an RCTSAI was apparently never generated for this action. However, this action is being handled as a commitment.
Revised Commitment
Description:
Commitment tracking closed. Modification installed in Unit 3, the modification was canceled for Unit 1 and Unit 2.
Justification of Change:
After the installation of the modification in Unit 3, APS determined that the modification was not required due to alternate containment temperature indication from a reliable power source that can be supplied from class 1 E diesel generators. Based upon availability of these alternate temperature indicators, the modification was cancelled. Containment temperature and humidity indication can be supplied by a bus with an emergency diesel generator. At least two breakers separate class power supply from the non-class inverter in all units.
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