ML15215A362
| ML15215A362 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/28/2015 |
| From: | Weber T Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-07090-TNW/CJS | |
| Download: ML15215A362 (10) | |
Text
Saps Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road 102-07090-TN W/CJS Tonopah, AZ 85354 July 28, 2015 ATI-N: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 First Use Report for Startup Test Activity Reduction (STAR) Program
Dear Sirs:
On March 30, 2015, the NRC staff issued License Amendment 195 to Arizona Public Service Company (APS) for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3. The amendments modified the moderator temperature coefficient (MTC) Technical Specification Surveillance Requirements associated with implementation of Westinghouse Electric Company LLC's topical report WCAP-16011-NP-A, Revision 0, Startup Test Activity Reduction Program, dated February 2005. The changes are consistent with NRC-approved Technical Specification Task Force (TSTF)
Standard Technical Specification Change Traveler TSTF-486, Revision 2, Revise MTC Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-1 601 1).
APS committed in letter number 102-06784, dated November 20, 2013, to provide a First Use Report within 90 days of completion of the first application of STAR at PVNGS. This commitment was confirmed as a license condition in License Amendment 195. PVNGS Unit 3, Refueling Outage 18 (3R18) was the first unit to apply the STAR Program. The Unit 3 refueling outage ended on May 3, 2015. The Enclosure to this letter, entitled, Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18), completes the commitment and license condition.
No commitments are being made to the NRC by this letter.
Callaway
- Diablo Canyon
- alo Verde
- Wolf Creek/
102-07090-TN W/CJS ATTlN: Document Control Desk U.S. Nuclear Regulatory Commission First Use Report for Startup Test Activity Reduction (STAR) Program Page 2 Shouid you need further information regarding this submittal, please contact me at (623) 393-5764.
Sincerely, Thomas N. Weber Nuclear Regulatory Affairs Department Leader TNW/CJS
Enclosure:
Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R 18)
CC:
M. L. Dapas M. M. Watford C. A. Peabody NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC Senior Resident Inspector for PVNGS
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18)
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18)
Core Design Method The Palo Verde Nuclear Generating Station (PVNGS), Unit 3 Operating Cycle 19 reload core used CASMO-4/SIMULATE-3 as the design method. This method has been reviewed and approved by the NRC (Reference 1).
Comparison of Measured to Calculated Values Application of the Startup Test Activity Reduction (STAR) Program for Operating Cycle 19 (implemented during startup from Refueling Outage 3R18) allowed the elimination of Control Element Assembly (CEA) worth measurements from the low power physics testing program and allowed for alternate moderator temperature coefficient (MTC) surveillance. The elimination of this measurement and the use of the alternate surveillance are acceptable since the STAR Applicability Requirements have been satisfied and documented.
Tables 1,* 3, and 4 provide the results from the Operating Cycle 19 STAR Program tests. Each of the STAR program test criterion were met. Therefore, the STAR Program was successfully implemented for the PVNGS Unit 3 Operating Cycle 19 reload core.
Where applicable, Table 1 also provides a comparison of the difference between the measured and calculated values. As illustrated, the differences were within the test criteria.
STAR Applicability Requirements Table 5-2, PVNGS STAR Program Applicability Requirements, of WCAP-17787 as contained in Reference 2 and approved by the NRC in Reference 3, lists the applicability requirements for the use of the STAR Program. The STAR applicability requirements provide compensatory measures that ensure the core can be operated as designed when used in conjunction with the STAR Program Tests outlined in Table 5-1 of WCAP-17787 as contained in Reference 2. The STAR applicability requirements involve the following areas:
Core Design Fabrication Refueling Startup Testing CEA Lifetime Conformance with the STAR applicability requirements was documented in accordance with plant processes and procedures. Comparison to an independent qualified core physics method showed acceptable reconciliation results and is 1
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18) summarized in Table 2. Reference 4 specifically documents the conformance of Unit 3 Operating Cycle 19 with the STAR applicability requirements.
Conclusions It was demonstrated that the conditions and limitations listed in Reference 2 and approved in Reference 3 were successfully met for the startup of PVNGS Unit 3 for Operating Cycle 19, following 3R18.
References
- 1.
NRC letter dated March 20, 2001, Jack N. Donohew, Senior Project Manager (NRC) to Gregg R. Overbeck, Senior Vice President (APS), Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3 - Issuance of Amendments on CASMO-4/SIMULATE-3 (ADAMS Accession No. ML010860187)
- 2.
APS letter number 102-06785, dated November 20, 2013, Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Transmittal of Proprietary Documents for Startup Test Activity Reduction (STAR) Program License Amendment Request (LAR) (ADAMS Accession No. ML13329A700)
- 3.
NRC letter dated March 30, 2015, Balwant K. Singal, Senior Project Manager (NRC) to Randall K. Edington, Executive Vice President Nuclear/Chief Nuclear Officer (APS), Palo Verde Nuclear Generating Station, Units 1, 2, and 3 -
Issuance of Amendments RE: Technical Specification Change Regarding Moderator Temperature Coefficient Surveillance for Startup Test Activity Reduction Program (ADAMS Accession No. ML15070A124)
- 4.
Procedure 72PY-9RX06, Low Power Physics Testing Using STAR, Revision 0, as performed in 3R18 on May 3, 2015 under Work Order 4647997 2
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18)
Table 1 PVNGS Unit 3 Operating Cycle 19 STAR Program Test Results
", TEST1 POWER MEASURED CALCULATED DIFFERENCE TEST CRITERIA
- ".:-.....VALUE VALUE
';CEA.Drop Ti me.
Shutdown Individual NA NA Individual
- *,.-2.377 to 3.023
< 3.996 seconds
'--seconds
- CBCY..
HZP 1991 ppm 1978 ppm 13 ppm
+ 50 ppm or the
,,-*.... '(94 pcm)
CBC equivalent of
__500 pcm MTC Alternate HZP
-0.0853E-4Ak/k/OF NA NA
< 0.5 E-4Ak/k/OF Surveillance Incore Flux
"'19%
Maximum NA NA The maximum Symmetry difference between difference between quadrant the measured
.. :.symmetric powers in
,assemblies with rotationally Saverage RPD symmetric greater than 1.
assemblies is 4.3%
within 9.1%/ of the symmetric group
_____________average.
1Table 5-1 of the STAR topical report (Reference 2) provides descriptions of the tests 2 Technical Specification limit 3
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18)
PVNGS Unit 3 Operating Table 1 Cycle 19 STAR (Continued)
Program Test Results TEST1 POWER MEASURED CALCULATED DIFFERENCE TEST CRITERIA
______________________________VALUE VALUE Incore Power 69%
RMS Errors <5%
- .See Table 3 Axial Error <0.1, Fxy FrFz within +-10%/
~ITC HFP
-1.27E-4 Ak/k/OF
-1.33E-4Ak/k/OF 0.06E-4 Ak/k/OF None MTC Surveillance HFP
-1.13E-4 Ak/k/OF NA NA
< 0.0 E-4Ak/k/OF 2 and within COLR limits Incore Power HFP RMS Errors < 5%,
Distribution Radial Error <0.1, See Table 4 Axial Error <0.1,
_____________Fxy, Fr, Fz within +10%
ACBC HZP-HFP HFP 574 ppm 561 ppm 13 ppm 4-50 ppm STable 5-1 of the STAR topical report (Reference 2) provides descriptions of the tests 2 Technical Specification limit 4
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18)
Table 2 Predicted Parameter Reconciliation Results Parameter Units Method Predicted Value SIMU LATE ROCS (Design Method)
.(Alternate Method)
Difference*
Cycle. 19 2.893 2.965 2.5%
Regulating Groups
%/Ap (Proposed Core)
Worth__
Cycle 18 2.953 3.033 2.70/
(Measured Core)___
%Difference**
-2.1
-2.3 Cycle 19 12.438 12.834 3.20/
All Groups Worth
%/Ap (Proposed Core)___________________
Cycle 18 12.322 12.711 3.2%
(Measured Core)
/
Difference**
+ 1.0
+ 1.0 Cycle 19
-0.090
-0.013
+0.077 ARO MTC E-4 Ap / 0F (Proposed Core)
Cycle 18
-0.085
-0.014
+0.071 (MeasuredCore)
Difference**
-0.005
+0.001
- Difference = Alternate - Design for MTC. Difference = 100*(Alternate-Design)/(Design) for CEA worth.
- Difference = Proposed - Measured for MTC. Difference = 100*(Proposed
- Measured)/(Proposed) for CEA worth 5
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18)
Table 3 -
690/ Power Distribution Snapshot 01583272 TEST RESULTS
SUMMARY
0 MEASURED PARAMETER RADIAL PWR DISTRIBUTION ERROR (PRED-CECOR)
RADIAL PN'R DISTRIBUTION RMS5 ERROR
[ PRED-CECOR)
AXIAL PNR DISTRIBUTION ERROR (PRED-CECOR)
AXIAL PNeR DISTRIBUTION RES ERROR (PRED-CECOR)
CECOR MEASURED VALUE
- 1. 4867
- 1. 4105 1.2071 1.7452 MXIM4UM~ DIFFERENCE (PRED--cECOR) 0.0326 0.0152
-0. 0436 0.0219 PREDICTED P3 WALUE
[ (P3 1.4310
- 1. 3320 1.1810
- 1. 6480 ACCEPTANCE CRITERIA S+ OR -
0.1
< +OR -
0.05
< + OR -
0.1 0
.MEASURED PARAMETER FAY FR FZ FQ
< +OR -
0.05
- RCENT DIFFERENCE
- ED-CECOR) /PRED) *i00
-3. 890
-2.062
-2. 207
-5. 898 ACCEPTANCE CRITERIA 1.2879 TO 1.5741 1.2438 TO 1.5202 1.0629 TO 1.2991 1.4832 TO 1.8128 6
Enclosure Summary Report for Implementation of the STAR Program at PVNGS during Unit 3 Refueling Outage 18 (3R18)
Table 4 -
100%M Power Distribution Snapshot C1583639 TEST RESULTS SUMMiARY 0
MEASURED PARAMETER RADIAL PNR DISTRIBUTION ERROR (PRED-CECOR)
RADIAL P.WR DISTRIBUTION PBS ERROR (PRED-CECOR)
AXIAL PWR DISTRIBUTION ERROR (PRED-CECOR)
AXIAL PWR DISTRIBUTION RBS ERROR (PRED-CECOR)
CECOR MEASURED VALUE
- 1. 4676
- 1. 3923 1.1783
- 1. 6779 HPXIXMUX DIFFERENCE (PRED-CECOR)
-0.0305 0.0109
-0.0351 0.0171 PREDICTED P1 VALUE
( (PF
- 1. 4190
- 1. 3680
- 1. 1660 1.6250 ACCEPTANCE CRITERIA
< +OR-0.1
<-÷-OR -
0.05
< + OR -
0.1 U
MEASURED PARAMETER FEY.
FR F2 FQ
< +OR -
0.05 KRCENT DIFFERENCE tED-CECOR) /PRED) *100
-3. 425
-1. 776
-1. 056
-3.255 ACCEPTANCE CRITERIA 1.2771 TO 1.5609 1.2312 TO 1.5048 1.0494 TO 1.2826 1.4625 TO 1.7875 7