ML033580629
| ML033580629 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/17/2003 |
| From: | Bauer S Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-05019-SAB/TNW/CJJ | |
| Download: ML033580629 (8) | |
Text
JLI Scott A. Bauer Department Leader 10 CFR 50.59 Regulatory Affairs Tel: 623/393-5978 Mail Station 7636 Palo Verde Nuclear Fax: 623/393-5442 P.O. Box 52034 Generating Station e-mail: sbauer@apsc.com Phoenix, AZ 85072-2034 102-05019-SAB/TNW/CJJ December 17, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, & 3 Docket Nos. STN 50-528/529/530 10 CFR 50.59 Report (January-December 2002)
Pursuant to 10 CFR 50.59(d)(2), Arizona Public Service Company is submitting the enclosed report. This report contains a brief description of each change and a brief summary of the evaluation required by 10 CFR 50.59(d)(1) for each change. This report contains all evaluations written during 2002, regardless of the implementation status of the evaluated action.
No commitments are being made to the NRC by this letter. Should you have any questions, please contact Thomas N. Weber at (623) 393-5764.
Sincerely, SAB/TNW/CJJ/kg I V WS (C' Enclosure 35 SaQ (2-(-
cc: B. S. Mallett M. B. Fields N. L. Salgado A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
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ENCLOSURE PALO VERDE NUCLEAR GENERATING STATION ACRONYM/ABBREVIATION DEFINITION SHEET AND 10 CFR 50.59 REPORT JANUARY - DECEMBER 2002
Acronym/Abbreviation Definition Sheet ASGT - Asymmetric Steam Generator Transient CALC - Calculation CE - Combustion Engineering CEA - Control Element Assembly CENTS - Combustion Engineering Nuclear Transient Simulation CESEC - Computer Code used to Simulate the Nuclear Steam Supply System CoC - Certification of Compliance CPC - Core Protection Calculator DMWO - Design Modification Work Order DW - Demineralized Water System EC - Essential Chilled Water EW - Essential Cooling Water FWLB - Feedwater Line Break kV - Kilovolt LDCR - Licensing Document Change Request LOCV - Loss of Condenser Vacuum LOP - Loss of Offsite Power NRC - Nuclear Regulatory Commission PROC - Procedure PUR - Power Uprate PVNGS - Palo Verde Nuclear Generating Station RSG - Replacement Steam Generator SDC - Shutdown Cooling SG - Steam Generator SGTR - Steam Generator Tube Rupture SGTRLOP - Steam Generator Tube Rupture with Loss of Offsite Power Event TMOD - Temporary Modification UFSAR - Update Final Safety Analysis Report WO - Work Order
10 CFR 50.59 Annual Report (January - December 2002)
Log Number. Doc Type Doc Number Description Summary E-02-00001 PROC 43OP-3EW02 R23 The proposed procedure revision provides instructions to This change does not require prior "Feed and Bleed' the EW System to improve system NRC approval in accordance with chemistry while maintaining the EW System OPERABLE. The 10CFR50.59(c)(1).
Feed and Bleed is accomplished by maintaining adequate level in the EW Surge Tank via normal make-up flow (DW) while manually draining EW, either from the Essential Chiller (EC) or the SDC Heat Exchanger. Operators will maintain constant communication capability with the Control Room while in attendance at the EW Surge Tank and selected EW Drain throughout the draining evolution.
E-02-00003 LDCR 02-F002 This proposed revision to the UFSAR will reflect revised grid This change does not require prior stability study results showing the effect of synchronizing the NRC approval in accordance with new Redhawk and Arlington Valley generating stations to the 10CFR50.59(c)(1).
525 kV transmission system near Palo Verde.
E-02-00006 LDCR 01-F059 This proposed revision to UFSAR section 15.4.8 (Control This change does not require prior Element Assembly Ejection) Analysis of Record Calculation NRC approval in accordance with was revised for Unit 2 Cycle 11. Part of this revision included 10CFR50.59(c)(1).
using the CENTS computer code in accordance with License Amendment 137 and Generic Letter 83-11, Supplement 1.
E-02-00007 CALC A-PV2-FE-0156 R2 The current CESEC based ASGT analysis has been revised This change does not require prior with the new CENTS based ASGT Analysis, and will be NRC approval in accordance with implemented for reloads beginning with Cycle 11. Use of the 10CFR50.59(c)(1).
CENTS has been approved for PVNGS in accordance with License Amendment 137 and Generic Letter 83-11 Supplement 1 Guidelines.
E-02-00008 CALC A-PV2-FE-154 R1 This CALC will be revised to replace CESEC based analyses This change does not require prior "Verification of CPC Filters Penalties (for Unit 2 Cycle 7)" with NRC approval in accordance with CENTS based 'Verification of PVNGS CPC Dynamic Filters 10CFR50.59(c)(1).
Coefficients for RSG and Power Uprate".
E-02-00009 PROC Various Various procedures will be revised regarding the use of a This change does not require prior Temporary Reactor Vessel Cover. The evaluation addresses NRC approval in accordance with the general use of a Temporary Reactor Vessel Cover during 10CFR50.59(c)(1).
refueling outages.
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Log Number Doc Type Doc Number Description Summary E-02-00010 LDCR 01-F059 This revision to the UFSAR revises the Hot Zero This change does not require prior Power/Subcritical CEA Withdrawal Events safety analyses and NRC approval in accordance with incorporates the CENTS code. Use of the CENTS code has 10CFR50.59(c)(1).
been approved for PVNGS in accordance with License Amendment 137 and Generic Letter 83-11, Supplement 1 guidelines.
E-02-00011 LDCR 01 -F059 This revision to the UFSAR revises the CEA Withdrawal at This change does not require prior Power safety analyses and incorporates the CENTS code. NRC approval in accordance with Use of the CENTS code has been approved for PVNGS in 10CFR50.59(c)(1).
accordance with License Amendment 137 and Generic Letter 83-11, Supplement 1 guidelines.
E-02-00012 LDCR 01-F059 This revision to the UFSAR revises the Full-Length CEA Drop This change does not require prior safety analyses and incorporates the CENTS code. Use of the NRC approval in accordance with CENTS code has been approved for PVNGS in accordance 10CFR50.59(c)(1).
with License Amendment 137 and Generic Letter 83-11,
.______________________Supplement 1 guidelines.
E-02-00013 CALC CN-TAS-01 -7 RO This calculation analyzes the Reload Analysis Methodology This change does not require prior Reactor Power Cutback Events using the CENTS code. Use NRC approval in accordance with of the CENTS code has been approved for PVNGS in 10CFR50.59(c)(1).
accordance with License Amendment 137 and Generic Letter 83-11, Supplement 1 guidelines.
E-02-00014 LDCR 01-F056 This revision to the UFSAR incorporates new and revised This change does not require prior Increase in Heat Removal by Secondary Systems safety NRC approval in accordance with analyses and incorporates the CENTS code. Use of the 10CFR50.59(c)(1).
CENTS code has been approved for PVNGS in accordance with License Amendment 137 and Generic Letter 83-11, Supplement 1 guidelines.
E-02-00015 LDCR 01-F061 This revision to the UFSAR revises Section 15.6.2, Double- This change does not require prior Ended Break of a Letdown Line Outside Containment as a NRC approval in accordance with result of the replacement of the CESEC computer code with 10CFR50.59(c)(1).
the CENTS code. Use of the CENTS code has been approved for PVNGS in accordance with License Amendment 137 and Generic Letter 83-11, Supplement 1 guidelines.
E-02-00016 LDCR 01-F057 This revision to the UFSAR revised Section 15.2.3, Loss of This change does not require prior Condenser Vacuum and Section 15.2.8, Feedwater Line Break NRC approval in accordance with Events. This 50.59 provides justification for the new LOCV 10CFR50.59(c)(1).
and FWLB analyses using the CENTS computer code. Use of the CENTS code has been approved for PVNGS in accordance with License Amendment 137 and Generic Letter 83-11, Supplement 1 guidelines.
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Log Number Doc Type Doc Number Description Summary E-02-00017 WO 2459122, 2497620, This modification dealt with temporary installation of thermal This change does not require prior 2497616, 2501516 loggers to obtain equipment and ambient temperature data for NRC approval in accordance with Equipment Qualification purposes. 10CFR50.59(c)(1).
E-02-00018 LDCR 02-F061 This revision to the UFSAR revised the SGTR and SGTRLOP This change does not require prior safety analyses using the CENTS code. Use of the CENTS NRC approval in accordance with code has been approved for PVNGS in accordance with 10CFR50.59(c)(1).
License Amendment 137 and Generic Letter 83-11, Supplement 1guidelines.
E-02-00020 LDCR 02-F031 This revision to the UFSAR updated Sections 3.1.16 and Prior NRC approval was granted 15.4.1 to correctly list the peak fuel centerline temperature in association with LDCR 02-limit. T003, which changed the peak linear heat rate safety limit to a peak fuel centerline temperature safety limit. (License Amendment
- 145)
E-02-00021 TMOD 2549067 This Temporary Modification supported operations procedure This change does not require prior changes that are required to locally control one of the letdown NRC approval in accordance with backpressure control valves on-line with normal letdown in 10CFR50.59(c)(1).
service.
E-02-00023 LDCR 02-T004, -R007, - These LDCRs are the result of Site Chemistry/Radiological This change does not require prior F040 Monitoring organizational changes. Organizational changes NRC approval in accordance with are in process that will re-align the Radiological Monitoring 10CFR50.59(c)(1).
programs and personnel, and make other organizational changes within the Site Chemistry Department.
E-02-00024 LDCR 02-F033 This revision to the UFSAR addressed changes to Section The revised FWLB with LOP and 15E.2. A new Analysis of Record was performed for the Single Failure Event was Feedwater Line Break (FWLB) with Loss of Offsite Power submitted for NRC review and (LOP) and Single Failure event described in UFSAR 15E.2 as approval as part of the Unit 2 a result of CRDRs 2469198 and 2529756, utilizing the CENTS Power Uprate License computer code. Amendment Request (APS Letter 102-04866 to NRC dated 11/21/2002). License Amendment 149 was issued on September 29, 2003.
E-02-00025 PROC 420P-2EC02 R34 This procedure revision provides instructions to "feed and This change does not require prior bleed' the EC system to improve system chemistry while NRC approval in accordance with maintaining the EC system operable. 10CFR50.59(c)(1).
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Log Number Doc Type Doc Number Description Summary E-02-00026 This 50.59 evaluates CENTS Code Version 02020. CENTS This change does not require prior code was generically approved for all Westinghouse-CE plants NRC approval in accordance with in 1994. Since then, Westinghouse-CE has made a number of 10CFR50.59(c)(1).
changes to the code. These can be categorized as: code cleanup, correction of errors, addition of new, optional features etc. This 50.59 addresses the changes made since initial NRC approval of the Code.
E-02-00027 LDCR 02-F025 This UFSAR revision changes Table 6.4.6-1 as a result of This change does not require prior corrections to input data that were used to determine the NRC approval in accordance with volumetric flow rate from the steam generator steam space to 10CFR50.59(c)(1).
the environment during hypothetical accidents.
E-02-00028 LDCR 02-F047 This proposed change would allow a deviation from the A License Amendment Request guidance provided in Regulatory Guide 1.25 regarding fuel rod for this change was submitted to pressurization. Reg. Guide 1.25 states that the wmaximum fuel the NRC on August 22, 2003.
rod pressurization is 1200 psig*. This proposed change would Refer to APS letter 102-04990 to change this requirement to "maximum assembly average peak the NRC, dated August 22, 2003.
fuel rod pressurization is 1200 psig".
E-02-00029 CALC 13-NC-ZY-263 R7 This licensing evaluation is to determine if the new geometry This change does not require prior created by the use of this cask (NAC-UMS CoC, Docket 72- NRC approval in accordance with 1015) is within the original reviewed methodology for fuel 10CFR50.59(c)(1).
handling accident as described in Chapter 15.7.4.1 of the UFSAR.
E-02-00030 LDCR 02-FO50 This 50.59 involves updating the UFSAR to incorporate This change does not require prior changes due to implementation of dry fuel storage and NRC approval in accordance with associated plant modifications, as well as implementing 10CFR50.59(c)(1).
procedures for Dry Fuel Storage System operation.
E-02-00031 DMWO 221244 This modification deals with containment structural This change does not require prior modifications. Plant modifications will be made during Unit 2 NRC approval in accordance with a11hrefueling outage, which will facilitate steam generator 10CFR50.59(c)(1).
replacement.
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Log Number Doc Type Doc Number Description Summary E-02-00032 DMWO 219978 This DMWO for PUR/RSG addresses process/performance This evaluation is predicated on design requirements, safety analyses, radiological analyses, NRC approval of the APS License topical issues, and regulatory requirements associated with Amendment request to support the overall PUR/RSG project. replacement of steam generators and uprated power operations for Unit 2. Refer to APS Letter 102-04641 to NRC, dated December 21, 2001. All other aspects addressed by this evaluation do not require prior NRC approval in accordance with 10 CFR 50.59(c).(1).
E-02-00033 DMWO 234952 This DMWO supports design and fabrication activities for the License Amendment Number 149 Replacement Steam Generators for Unit 2. was issued on September 29, 2003.
E-02-00034 DMWO 221242 This modification is for Steam Generator Large Bore Piping. This change does not require prior Replacement of the Unit 2 steam generators during Unit 2 11 th NRC approval in accordance with refueling outage will require modification to the large bore 10CFR50.59(c)(1).
secondary piping systems that are connected to them: Main Steam, Main Feedwater, Downcomer Feedwater and Blowdown. A new large bore secondary piping system, recirculation, and associated valves will also be installed to facilitate use of the new recirculation feature of the replacement steam generator (RSG) design.
E-02-00035 DMWO 221935 This modification includes the addition of new power, control This change does not require prior and instrumentation cables inside containment for future SG NRC approval in accordance with downcomer blowdown motor-operated valves. 10CFR50.59(c)(1).
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