ML070040090
| ML070040090 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/22/2006 |
| From: | Bauer S Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-05618-SAB/TNW/CJJ | |
| Download: ML070040090 (8) | |
Text
10 CFR 50.59, 10 CFR 72.48 Scott A. Bauer Tel. 623-393-5978 Mail Station 7636 Palo Verde Nuclear Department Leader, Fax 623-393-5442 PO Box 52034 Generating Station Regulatory Affairs e-mail: sbauer@apsc.com Phoenix, Arizona 85072-2034 102-05618-SAB/TNW/CJJ December 22, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, & 3 Docket Nos. STN 50-528/5291530 Annual 10 CFR 50.59, 10 CFR 72.48 and Commitment Change Report (January - December 2005)
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 the conclusion of the evaluation required by 10 CFR 50.59(d)(1) for each change. This report contains all evaluations written during 2005, regardless of the implementation status of the evaluated action.
There were no changes per 10 CFR 72.48(d)(1) required to be reported during 2005.
There was one NRC Commitment clarification made during 2005 which is also described in the enclosure.
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/gt Enclosure cc: B. S. Mallett (all w/enclosure)
M. B. Fields G. G. Warnick A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak El Diablo Canyon El Palo Verde El South Texas Project 0 Wolf Creek
ENCLOSURE PALO VERDE NUCLEAR GENERATING STATION ACRONYMIABBREVIATION LIST, 10 CFR 50.59 REPORT JANUARY - DECEMBER 2005, AND COMMITMENT CLARIFICATION - 2005
ACRONYM N/ABBREVIATION LIST ALARA - As Low As Reasonably Achievable ASME - American Society of Mechanical Engineers CaIc. - Calculation COLSS - Core Operating Limit Supervisory System CPC - Core Protection Calculator CRDR - Condition Report/Disposition Request CVCS HUT - Chemical Volume and Control System Hold Up Tank DMWO - Design Modification Work Order EDC - Engineering Document Change EOP - Emergency Operating Procedure IA - Instrument Air IOSGADV - Inadvertent Opening of a Steam Generator Atmospheric Dump Valve LDCR - Licensing Document Change Request LOCA - Loss of Coolant Accident LOF - Loss of Flow MS - Main Steam NC - Nuclear Cooling PVNGS - Palo Verde Nuclear Generating Station RAS - Recirculation Actuation Signal RCS - Reactor Coolant System RMI - Reflective Metal Insulation RSG - Replacement Steam Generator RTD - Resistance Temperature Detector SAFDL - Specified Acceptable Fuel Design Limit SDC - Shutdown Cooling SG - Steam Generator TMOD - Temporary Modification Work Order TS - Technical Specifications UFSAR - Updated Final Safety Analysis Report
10 CFR 50.59 Annual Report (January - December 2005)
Log Doc Type Doc Number Description Summary E-05-0001 Procedure 40OP-9SI02.R49 This procedure revision altered the Safety Injection pump stand-by line-up This change does not require prior NRC approval so that the lines between the containment sump and the Safety Injection in accordance with 10CFR50.59(c)(1).
pump suction, as well as the Containment RAS sumps themselves, remain filled with borated water during normal power operation.
E-05-0002 LDCR 04-FOO5 & 04-FO19 This evaluation addressed the application of a new approved evaluation This change has been previously approved by the method to PVNGS Units 1 & 3 to provide a consistent evaluation method NRC TS Amendment #149.
for all PVNGS units. The methodology separated the IOSGADV event from LOF from SAFDL event, thus established a more appropriate evaluation of IOSGADV event while creating a new safety analysis for a "composite" limiting infrequent event. The method was approved for PVNGS Unit 2 by TS Amendment #149.
E-05-0003 LDCR 05-F008 This modification implements the changes from DMWO 2739742 (Unit 3 This change does not require prior NRC approval only) into Units 1 and 2. The modification installed piping, isolation in accordance with 10CFR50.59(c)(1).
valves and supports to facilitate the filling, draining, venting, and testing of the post-LOCA recirculation piping located upstream of the recirculation check valves, PSIAV205 and PSIAV206. The modification also upgraded various materials on valves JSIAUV0673 and JSIBUVO675 to more corrosion resistant materials.
E-05-0004 Canceled E-05-0005 EDC 2005-00211 This EDC updated vendor calculation A-PV2-FE-0164 (PVNGS Subcritical This change does not require prior NRC approval Main Steam Line Break Return to Power for RSG/Uprate Scenario) to take in accordance with 10CFR50.59(c)(1).
into account errors documented in CRDR 2595572. Specifically, the initial power level and steam generator level used in the vendorcalculation were not the most limiting, however crediting a higher RWT boron concentration resulted in impact to the conclusion.
E-05-0006 Canceled E-05-0007 DFWO 2745267 This modification applied an approved epoxy coating on inside and outside This change does not require prior NRC approval concrete surfaces of D ring and Reactor Cavity walls replaced during Steam in accordance with 10CFR50.59(c)(1).
Generator outage 2R11.
Page 1 of 4
Log Doc Type Doc Number Description Summary E-05-0008 DMWO 2541291 This modification covers activities performed during UIR12 [U3R13], This change does not require prior NRC approval which will facilitate steam generator replacement. These include in accordance with I OCFR50.59(c)(I).
modifications to existing platforms, addition of new platforms, platform beam connection upgrade, removal of polar crane access walkway support brackets, concrete wall cutting/restoration and the addition of a new permanent steel formwork plate.
E-05-0009 DMWO 2513158 The insulation of the reactor vessel upper head was replaced with a This change does not require prior NRC approval new design at Unit 1 under DMWO 2251358. Testing determined in accordance with 10CFR50.59(c)(1).
the insulation did not meet Regulatory Guide 1.36. This evaluation was performed to justify the potentially non-conforming insulation remaining installed for the remainder of the operating cycle.
E-05-0010 PROCEDURE 72ST-9RX03.Rl1 This revision to appendix B of the procedure revised the azimuthal tilt This change does not require prior NRC approval calculation with COLSS out of service. in accordance with 10CFR50.59(c)(1).
E-05-0011 DFWO 2788561 This DFWO is a Use-As-Is disposition for missing parts potentially left in This change does not require prior NRC approval the refueling pool. The proposed activity evaluated the potential impact of in accordance with 10CFR50.59(c)(1).
5 fastening devices found missing from the refueling machine hoisting frame. These devices consist of two 1/4" bolts, one 3/8" bolt, one 3/8" nut, and one 3/8" washer.
E-05-0012 DMWO 2541285 This modification was to the large bore piping systems and associated This change does not require prior NRC approval supports that are necessary to accommodate steam generator replacements in in accordance with 10CFR50.59(c)(1).
Units 1 and 3 during U1R12 and U3R13, respectively. 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. Modifications to the Main Steam (MS) whip restraints will be made to accommodate the taller RSGs. In addition, modifications will be made due to increased loads resulting from steam generator replacement and power uprate.
E-05-0013 PROCEDURE 73TI-9CH04 This procedure will obtain plant data during specified pump suction flow This change does not require prior NRC approval path manipulations in order to determine plant configurations that cannot in accordance with 10CFR50.59(c)(1).
support the CH-536 charging pump suction path to be an operable boron path.
E-05-0014 DFWO 2788561 This DFWO is a Use-As-Is disposition for missing finger from tele- This change does not require prior NRC approval detector. The debris is - 2" long by - 1/4" wide the -1 mm thick and in accordance with 10CFR50.59(c)(1).
made of a copper alloy. The debris could have fallen on top of fuel assemblies in the reactor vessel.
Page 2 of 4
Log Doc Type Doc Number Description Summary E-05-0015 Canceled E-05-0016 LDCR 05-F023 This revision to the UFSAR modified Table 9.3-3 to state that CVCS This change does not require prior NRC approval HUT mode of sampling is now Local Sampling at 2 locations equivalent to in accordance with 10CFR50.59(c)(1).
existing (old) method listed on sheet 10 of 11.
E-05-0017 DMWO 2541022 This DMWO addresses process/performance design requirements and This change does not require prior NRC approval regulatory requirements associated with only the design and fabrication of in accordance with 10CFR50.59(c)(1).
the Units 1 and 3 steam generators, their internals, supports, and cold leg elbows. Sufficient design information is included to assure that design intent, scope and approval are adequate and are in compliance with applicable design requirements and regulatory criteria.
E-05-0018 Canceled E-05-001 9 Canceled E-05-0020 DMWO 2540917 This is the Master DMWO for Power Uprate. This DMWO addresses This change does not require prior NRC approval all engineering documentation and products necessary to support the in accordance with 10CFR50.59(c)(1).
process/performance, safety analyses, radiological analyses and topical issues for design bases for the power uprate.
E-05-0021 DFWO 2809648 This DFWO was an Accept-As-Is disposition of a short-term excursion This change does not require prior NRC approval above the Design Temperature, as described in the UFSAR, of 700 F for the in accordance with 10CFR50.59(c)(1).
pressurizer. It has been determined that all pressure boundary aspects of the pressurizer meet the ASME Section III code stress limits, with the use of stress intensity values as permitted in Relief Request 33.
E-05-0022 TMOD 2785294 This TMOD provided temporary instrument air (IA) compressors during This change does not require prior NRC approval the replacement of the permanent compressors under DMWO 2693912 for in accordance with 10CFR50.59(c)(1).
Unit 3.
E-05-0023 Canceled E-05-0024 DMWO 2358951 This modification permanently removed the Gas Stripper radiation monitor This change does not require prior NRC approval and its support equipment from service. This modification resulted in a in accordance with 10CFR50.59(c)(1).
change to the UFSAR (LDCR 05-F038). The UFSAR was updated to remove the reference to Radiation Monitor DJCHNRYSH0265.
E-05-0025 Canceled Page 3 of 4
IJ Log Doc Type Doc Number Description Summary E-05-0026 Canceled E-05-0027 DMWO 2651111 This modification and associated UFSAR revision (LDCR 04-F03 1) will This change does not require prior NRC approval remove NC low flow switch JNCNFSL0613 and will relocate the associated in accordance with 10CFR50.59(c)(1).
isolation interlock with CH-UV523 to a new temperature switch JCHNTS0224-2.
E-05-0029 TMWO 2826217 This modification was for the temporary installation and use of a portable This change does not require prior NRC approval temporary laundry skid interface to PVNGS Unit 1. in accordance with 10CFR50.59(c)(1).
E-05-0030 Canceled E-05-0031 ABB V-99-060 This activity changed the fuel tube cladding dimensional tolerances and This change does not require prior NRC approval tolerances of form beginning with Palo Verde Batch 3L fuel. in accordance with 10CFR50.59(c)(1).
E-05-0032 CALC FS-03-COO-1996-007 This evaluation revised a Proprietary Unit 3 Nuclear Fuel Basis document. This change does not require prior NRC approval There were alignment issues between the fuel center guide tube and the in accordance with 10CFR50.59(c)(1).
lower end fitting.
E-05-0033 DMWO 2754516 This modification installed a welded attachment in the Unit 1 SDC suction This change does not require prior NRC approval line nozzle to suppress vortex generated acoustic vibration. in accordance with 10CFR50.59(c)(1).
E-05-0035 ABB V-99-017 This evaluation was for ABB V-99-017, Transmittal of Final PV2L This change does not require prior NRC approval Manufacturing Documentation, Enclosure D. Two batch PV2L Urainum in accordance with 10CFR50.59(c)(1).
Erbium oxide fuel pellet lots, C976JK Sublot A and C977JK Sublot B, contained pellets with high sintered density. The estimated upper confidence limits of these lots exceeded the high sintered density specification limit of 97% Theoretical Density (TD) by a small amount.
This excess was 0.2% TD and was accommodated via accepted DCR 5321-98-2082-H- 1.
E-05-0036 Procedure 40AO-9ZZO0 This procedure revision added a New Standard Appendix (103) for RCS This change does not require prior NRC approval Makeup and Emergency Boration for use with the EOP's based on in accordance with IOCFR50.59(c)(1).
Engineering Study for use of CHE-HV-536. This evaluation also applies to various other procedure changes also based on the same Engineering Study.
E-05-0037 TMOD 2849895 This temporary modification will substitute non-class RTD This change does not require prior NRC approval 2JRCNTEO1 I1X for Class 1E RDT 2JRCDTEO1 12HD as the Reactor in accordance with 10CFR50.59(c)(1).
Coolant System (RCS) Loop-1 Hot-Leg temperature input to the Unit 2 Core Protection Calculator (CPC) Channel-D.
Page 4 of 4
Commitment Clarification - 2005 The below commitment clarification was made on November 18, 2005:
In response to GL 89-13 letter 102-02678 dated October 1, 1993 had the following statement:
".... The SP system is also monitored for total system flow and heat exchanger pressure drop on a monthly basis."
The intent of the pressure drop monitoring was only for the EW heat exchanger and not the other heat exchangers cooled by the SP system. The justification for this clarification is that at the time the letter was issued the EW heat exchanger was the only heat exchanger being monitored for pressure drop. Since the letter clearly indicates that monitoring was already in place and since only the EW heat exchanger was being monitored at that time this clarification is justified.