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{{#Wiki_filter:ACCELERATE DISTRIBUTION DEMO STRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)FACIL:STN-50-528 Palo Verde Nuclear Station, STN-50-529 Palo Verde Nuclear Station, STN-50-530 Palo Verde Nuclear Station, AUTH.NAME AUTHOR AFFILIATION ECKLUND,B.S.
{{#Wiki_filter:ACCELERATE               DISTRIBUTION DEMO STRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
Arizona Public Service Co.RECIP.NAME RECIPIENT AFFILIATION NOTARIZED:
NOTARIZED: NO            DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station,             Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station,           Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station,           Unit 3, Arizona Publi 05000530 AUTH. NAME           AUTHOR AFFILIATION ECKLUND,B.S.         Arizona Public Service Co.         (formerly Arizona Nuclear Power RECIP.NAME           RECIPIENT AFFILIATION I
NO DOCKET Unit 1, Arizona Publi 05000528 Unit 2, Arizona Publi 05000529 Unit 3, Arizona Publi 05000530 (formerly Arizona Nuclear Power I
Monthly operating repts for Feb 199 j


==SUBJECT:==
==SUBJECT:==
Monthly operating repts for Feb 199 o Verde Nuclear Generating Station units 1,2,&3./940314 tr.DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR j ENCL g SIZE: (TITLE: Monthly Operating Report (per Tech Specs)D NOTES: STANDARDIZED PLANT Standardized plant.Standardized plant.RECIPIENT ID CODE/NAME PDV PD TRAN,L COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME POLICH, T COPIES LTTR ENCL 1 1 05000528 A 05000529 05000530 D D INTERNAL: ACRS AEOD/DSP/TPAB NRR/DRIL/RPEB RGN5 10 10 AEOD/DOA 1 1 NRR/DORS/OEAB 1 1~EG F 01 1 1 1 1 1 1 1 1 EXTERNAL EGGG BRYCE I J~H NSIC 1 1 1 1 NRC PDR 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
o Verde Nuclear         D Generating Station units 1,2, & 3. /940314               tr.
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22 D D tj C V 1 Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O, BOX 52034~PHOENIX.ARIZONA 85072-2034 41 7-00202-BSE March 14, 1994 U.S.Nuclear Regulatory Commission ATTN: Document'Control Desk Mail Station P1-37 Washington, DC 20555  
DISTRIBUTION CODE: IE24D           COPIES RECEIVED:LTR TITLE: Monthly Operating Report (per Tech Specs)
ENCL  g    SIZE:    (
NOTES: STANDARDIZED PLANT                                                           05000528 A Standardized plant.                                                         05000529 Standardized plant.                                                         05000530 D RECIPIENT              COPIES          RECIPIENT           COPIES            D ID CODE/NAME             LTTR ENCL     ID CODE/NAME       LTTR ENCL PDV PD                      1    1    POLICH, T               1    1 TRAN,L                      1     1 INTERNAL: ACRS                         10    10    AEOD/DOA                1    1 AEOD/DSP/TPAB               1    1    NRR/DORS/OEAB          1   1 NRR/DRIL/RPEB                1     1   ~EG F           01       1     1 RGN5                        1     1 EXTERNAL   EGGG BRYCE I J ~ H           1     1     NRC PDR                1   1 NSIC                        1     1 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR             22   ENCL   22
 
tj C
1 V
 
Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O, BOX 52034 ~ PHOENIX. ARIZONA 85072-2034 41 7-00202-BSE March 14, 1994 U. S. Nuclear Regulatory Commission ATTN: Document'Control Desk Mail Station P1-37 Washington, DC 20555


==Dear Sirs:==
==Dear Sirs:==


==Subject:==
==Subject:==
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos.STN 50-528/529/530 Monthly Operating Reports for February 1994'e-02 0.-6-02 Enclosed are the Monthly Operating Reports for February 1994, prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the PVNGS Units 1, 2, and 3 Operating Licenses.By copy of this letter, Arizona Public Service Company is also forwarding the Monthly Operating Reports to the Regional Administrator, NRC Region V.If you have any questions, please contact me at (602)340-4068.Sincerely, BSE/gez Enclosures CC: (all w/enclosures)
Palo Verde Nuclear Generating Station (PVNGS)
K.E.Perkins A.H.Gutterman NRC Senior Resident Inspector INPO Records Center Utility Data Institute 94033,50320 940228 PDR<.'DQCK,OS000528.R.z'"'"..PDR I~I I l I 1'sw'<<Ew
Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Monthly Operating Reports for February 1994
                      'e     -02   0 .     -   6-02 Enclosed are the Monthly Operating Reports for February 1994, prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the PVNGS Units 1, 2, and 3 Operating Licenses. By copy of this letter, Arizona Public Service Company is also forwarding the Monthly Operating Reports to the Regional Administrator, NRC Region V.
If you have any questions, please contact me at (602) 340-4068.
Sincerely, BSE/gez Enclosures CC:     K. E. Perkins                  (all w/enclosures)
A. H. Gutterman NRC Senior Resident Inspector INPO Records Center Utility Data Institute 94033,50320 940228
.R      .z
            '"
PDR <.'DQCK,OS000528
                  '"   ..PDR


AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.QL529 UNIT NAME~gal~DATE 93LQBLK4 COMPLETED BY~~Qlgrgl MONTH: February 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1070 17 1068 10 12 13 14 15 16 1069 1070 1073 1072 1073 1072 1070 1072 1072 1071 1072 1072 1072 1072 1071 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1071 1072 1072 1072 1072 1073 1072 1072 1071 1070 1076 REFUELING INFORMATION DOCKET NO.QL525 UNIT NAME DATE 93LQBLK COMPLETED BY~~Qlgagl Scheduled date for next refueling shutdown.The 5th refueling outage is tentatively scheduled for 03/13/95.Scheduled date for restart following refueling.
      ~
06/01/95.Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
I I
No.Scheduled date for submitting proposed licensing action and supporting information.
I l
N/A.Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.
I
N/A.The number of fuel assemblies.
        'sw 1
b)In the spent fuel storage pool.Licensed spent fuel storage capacity.Intended change in spent fuel storage capacity.~ng Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.2005 (18 Month reloads and full core discharge capability).  
            ' <<Ew
 
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. QL529 UNIT NAME     ~gal~
DATE         93LQBLK4 COMPLETED BY ~~Qlgrgl MONTH: February 1994 DAY       AVERAGE DAILYPOWER LEVEL           DAY   AVERAGE DAILYPOWER LEVEL 1070                     17               1068 1069                     18              1071 1070                     19              1072 1073                     20              1072 1072                     21              1072 1073                      22              1072 1072                     23              1073 1070                      24              1072 1072                     25               1072 10                  1072                      26               1071 1071                      27               1070 12                  1072                      28               1076 13                  1072                      29 14                  1072                      30 15                  1072                      31 16                  1071
 
REFUELING INFORMATION DOCKET NO.         QL525 UNIT NAME DATE               93LQBLK COMPLETED BY         ~~Qlgagl Scheduled date for next refueling shutdown.
The 5th refueling outage is tentatively scheduled for 03/13/95.
Scheduled date for restart following refueling.
06/01/95.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No.
Scheduled date for submitting proposed licensing action and supporting information.
N/A.
Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.
N/A.
The number of fuel assemblies.
b) In the spent fuel storage pool.
Licensed spent fuel storage capacity.
Intended change in spent fuel storage capacity.   ~ng Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2005 (18 Month reloads and full core discharge capability).


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.QL529 UNIT NAME DATE 938MLRk COMPLETED BY~~klLUzl 02/01 0000 Unit began the month in Mode 1, 85%RX power.02/28 1228 Commenced power increase to 86%at the direction of the Plant Manager.02/28 1305 Stabilized RX power at 86%.02/28 2400 Unit ended the month in Mode 1, 86%RX power.
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. QL529 UNIT NAME DATE         938MLRk COMPLETED BY ~~klLUzl 02/01 0000 Unit began the month in Mode 1, 85% RX power.
SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKET NO~g UNIT NAME~V~~DATE QQJ///Qg COMPLETED BY~BIX&I+.IKRKHSH No.Outage Method of Duration Shutting Down Date Type" Hours Reason2 Reactor3 LER No.System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of February 1994 1F-Forced S-Scheduled Reason: A-Equipment Failure(Explain)
02/28 1228 Commenced power increase to 86% at the direction of the Plant Manager.
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Examination F-Administrative G-Operational Error H-Other (Explain)3Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20%or Greater in the Past 24 Hours 9-Other-(Explain) 4Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER)File (NUREG0161)
02/28 1305 Stabilized RX power at 86%.
Exhibit H-Same Source L~/%
02/28 2400 Unit ended the month in Mode 1, 86% RX power.


AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.SL529 UNIT NAME MEzR2 DATE QZQGLK COMPLETED BY~MGI~MONTH: February 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 17 18 19 20 21 22 23 24 25 10 26 27 12 13 14 15 28 29 30 31 16 l l, REFUELING INFORMATION DOCKET NO.~29 UNIT NAME MbLikR2 DATE 93LQSLR4 COMPLETED BY EMMY~Scheduled date for next refueling shutdown.The 5th refueling outage is tentatively scheduled for 09/17/94, however, it is more likely to take place in the first quarter of 1995.Scheduled date for restart following refueling.
SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKET NO UNIT NAME
12/06/94, or 80 days following the new refueling shutdown date.Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
                                                                                                                                          ~g
A change may.be required to Technical Specification 3.9.6 to raise the overload cutoff limit to accommodate the new fuel assembly modification.
                                                                                                                                          ~V~~
Also, Technical Specification Section 6.9.1.10 will be modified to add the new Inlet Flow Distribution methodology.
DATE                  QQJ///Qg COMPLETED BY          ~BIX&I+.
IKRKHSH Outage                    Method of Duration                Shutting Down                        System Component      Cause and Corrective Action No.          Date        Type"      Hours      Reason2        Reactor3            LER No.        Code4  Code5        to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of February 1994 1F-Forced              Reason:                                    3Method:                                  4Exhibit F - Instructions for Preparation S-Scheduled            A-Equipment Failure(Explain)                1-Manual                                  of the Data Entry Sheets for Licensee B-Maintenance or Test                      2-Manual Scram                            Event Report (LER) File (NUREG0161)
C-Refueling                                3-Automatic Scram D-Regulatory Restriction                    4-Continuation from Previous Month E-Operator Training 8 License              5-Reduction of 20% or Greater in the    Exhibit H-Same Source Examination                                Past 24 Hours F-Administrative                            9-Other-(Explain)
G-Operational Error H-Other (Explain)
 
L
~
/%
 
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. SL529 UNIT NAME     MEzR2 DATE         QZQGLK COMPLETED BY ~MGI~
MONTH: February 1994 DAY       AVERAGE DAILYPOWER LEVEL         DAY     AVERAGE DAILYPOWER LEVEL 17 18 19 20 21 22 23 24 25 10                                         26 27 12                                         28 13                                         29 14                                         30 15                                         31 16
 
l l,
 
REFUELING INFORMATION DOCKET NO.           ~29 UNIT NAME           MbLikR2 DATE                 93LQSLR4 COMPLETED BY         EMMY~
Scheduled date for next refueling shutdown.
The 5th refueling outage is tentatively scheduled for 09/17/94, however, it is more likely to take place in the first quarter of 1995.
Scheduled date for restart following refueling.
12/06/94, or 80 days following the new refueling shutdown date.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
A change may. be required to Technical Specification 3.9.6 to raise the overload cutoff limit to accommodate the new fuel assembly modification. Also, Technical Specification Section 6.9.1.10 will be modified to add the new Inlet Flow Distribution methodology.
Scheduled date for submitting proposed licensing action and supporting information.
Scheduled date for submitting proposed licensing action and supporting information.
10/13/94.Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.
10/13/94.
The fuel assembly will consist of a denser fuel pellet, Erbium burnable absorber and guardian grid.A primary temperature drop of 10'is currently planned.The number of fuel assemblies.
Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.
e)to the core.~b)In the spent fuel storage pool.~~Licensed spent fuel storage capacity.~99 Intended change in spent fuel storage capacity.~~Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.2005 (18 Month reloads and full core discharge capability).
The fuel assembly will consist of a denser fuel pellet, Erbium burnable absorber and guardian grid. A primary temperature drop of 10' is currently planned.
0  
e) to the core. ~
The number of fuel assemblies.
b) In the spent fuel storage pool. ~~
Licensed spent fuel storage capacity.     ~99 Intended change in spent fuel storage capacity. ~~
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2005 (18 Month reloads and full core discharge capability).
 
0


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.54529 UNIT NAME~59.~DATE QBLQBM COMPLETED BY 02/01 0000 Unit began the month in Mode 5, mid-cycle outage in progress.02/28 2400 Unit ended the month in Mode 5, mid-cycle outage in progress.
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 54529 UNIT NAME   ~59.~
f 0 0 SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKET NO SLURB UNIT NAME LVHGR2 DATE QZ99LRk COMPLETED BY~B~RLVEKI tuRISLIM Date Outage Method of Duration Shutting Down Type" Hours Reason2 Reactor3 LER No.System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence 94-01 01/08/94 S 672.0 N/A N/A N/A Continuation of planned mid-cycle from previous month.1F Forced S-Scheduled 2R A-Equipment Failure(Explain)
DATE         QBLQBM COMPLETED BY 02/01 0000 Unit began the month in Mode 5, mid-cycle outage in progress.
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Examination F-Administrative G-Operational Error H-Other (Explain)3Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20%or Greater in the Past 24 Hours 9-Other-(Explain) 4Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER)File (NUREG0161)
02/28 2400 Unit ended the month in Mode 5, mid-cycle outage in progress.
Exhibit H-Same Source r


AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.59-'539 UNIT NAME DATE Q3LGGLR4 COMPLETED BY~MB!~MONTH: February 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1071 17 1062 10 12 13 14 15 16 1069 1067 1068 1067 1071 1069 1069 1067 1069 1066 1064 1067 1069 1069 1067 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1067 1067 1070 1069 1072 1073 1072 1071 1069 1070 1078 REFUELING INFORMATION DOCKET NO.59-'QQ UNIT NAME LVHGR2 DATE QZQSLK COMPLETED BY Q~QR!led Scheduled date for next refueling shutdown.03/19/94, 4th refueling.
0 0 f
 
SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKET NO            SLURB UNIT NAME            LVHGR2 DATE                  QZ99LRk COMPLETED BY          ~B~RLVEKI tuRISLIM Outage                Method of Duration              Shutting Down                        System Component      Cause and Corrective Action Date        Type"      Hours    Reason2    Reactor3            LER No.        Code4    Code5        to Prevent Occurrence 94-01      01/08/94        S        672.0                                        N/A            N/A    N/A          Continuation of planned mid-cycle from previous month.
1F Forced            2R                                      3Method:                                  4Exhibit F - Instructions for Preparation S-Scheduled            A-Equipment Failure(Explain)            1-Manual                                  of the Data Entry Sheets for Licensee B-Maintenance or Test                    2-Manual Scram                            Event Report (LER) File (NUREG0161)
C-Refueling                              3-Automatic Scram D-Regulatory Restriction                4-Continuation from Previous Month E-Operator Training 8 License          5-Reduction of 20% or Greater in the    Exhibit H-Same Source Examination                              Past 24 Hours F-Administrative                        9-Other-(Explain)
G-Operational Error H-Other (Explain)
 
r
 
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. 59-'539 UNIT NAME DATE         Q3LGGLR4 COMPLETED BY ~MB!~
MONTH: February 1994 DAY       AVERAGE DAILYPOWER LEVEL         DAY     AVERAGE DAILYPOWER LEVEL 1071                     17               1062 1069                     18              1067 1067                     19              1067 1068                    20              1070 1067                     21              1069 1071                    22              1072 1069                     23               1073 1069                    24               1072 1067                    25               1071 10                1069                    26               1069 1066                    27               1070 12                1064                    28               1078 13                1067                    29 14                1069                    30 15                1069                    31 16                1067
 
REFUELING INFORMATION DOCKET NO.           59-'QQ UNIT NAME           LVHGR2 DATE                 QZQSLK COMPLETED BY         Q~QR!led Scheduled date for next refueling shutdown.
03/19/94, 4th refueling.
Scheduled date for restart following refueling.
Scheduled date for restart following refueling.
06/07/94.Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
06/07/94.
At present, four Tech.Spec.changes are in process.One for increasing the radially averaged weight percent of U235 in fuel rods to 4.30w/o.The other is to change the DNBR setpoint limit from 1.24 to 1.30.These are generic Tech.Spec.changes, and will be implemented on a Unit by Unit basis, beginning with U3C5.Also, there are two other Tech.Spec.changes that will allow U3C5 to operate at 100%power due to the steam generator issues.Scheduled date for submitting proposed licensing action and supporting information.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
The fuel enrichment change was submitted in October 1993 and the DNBR setpoint change was submitted in January 1994.Important Licensing considerations associated with refueling, e.gnew or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.
At present, four Tech. Spec. changes are in process. One for increasing the radially averaged weight percent of U235 in fuel rods to 4.30w/o. The other is to change the DNBR setpoint limit from 1.24 to 1.30. These are generic Tech. Spec. changes, and will be implemented on a Unit by Unit basis, beginning with U3C5.
U3C5 will incorporate a new higher maximum enrichment level of 4.30w/o U235 and will also utilize a new integral burnable absorber, Erbium.The NRC granted a license amendment (No.35)which allows the use of 80 fuel rods clad with advanced zirconium based alloys (other than Zircaioy<)
Also, there are two other Tech. Spec. changes that will allow U3C5 to operate at 100% power due to the steam generator issues.
in two fuel assemblies during Unit 3 Cycles 4, 5, and 6 for in-reactor performance evaluation.
Scheduled date for submitting proposed licensing action and supporting information.
Date of issuance was July 20, 1992.The number of fuel assemblies.
The fuel enrichment change was submitted in October 1993 and the DNBR setpoint change was submitted in January 1994.
e)tn the core.~b)In the spent fuel storage pool.Licensed spent fuel storage capacity.Intended change in spent fuel storage capacity.Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.2005 (18 Month reloads and full core discharge capability).  
Important Licensing considerations associated with refueling, e.gnew or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.
U3C5 will incorporate a new higher maximum enrichment level of 4.30w/o U235 and will also utilize a new integral burnable absorber, Erbium.
The NRC granted a license amendment (No. 35) which allows the use of 80 fuel rods clad with advanced zirconium based alloys (other than Zircaioy<) in two fuel assemblies during Unit 3 Cycles 4, 5, and 6 for in-reactor performance evaluation. Date of issuance was July 20, 1992.
e) tn the core. ~
The number of fuel assemblies.
b) In the spent fuel storage pool.
Licensed spent fuel storage capacity.
Intended change in spent fuel storage capacity.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2005 (18 Month reloads and full core discharge capability).


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.K=HO UNIT NAME ElblGR2 DATE QBNBLK4 02/01 0000 Unit began the month in Mode 1, 85%RX power.02/28 1002 Commenced power increase to 86%at the direction of the Plant Manager.02/28 1136 Stabilized RX power at 86%.02/28 0000 Unit ended the month in Mode 1, 86%RX power.
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. K=HO UNIT NAME ElblGR2 DATE       QBNBLK4 02/01 0000 Unit began the month in Mode 1, 85% RX power.
SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKETNO UNIT NAME f~~V(~DATE Q3LK194 COMPLETED BY IKaKBau Outage Method of Duration Shutting Down Date Type" Hours Reason2 Reactor3 LER No.System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of February 1994"F-Forced S-Scheduled 2Reaso A-Equipment Failure(Explain)
02/28 1002 Commenced power increase to 86% at the direction of the Plant Manager.
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Examination F-Administrative G-Operational Error H-Other (Explain)3Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20%or Greater in the Past 24 Hours 9-Other-(Explain) "Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee-Event Report (LER)File (NUREG0161)
02/28 1136 Stabilized RX power at 86%.
Exhibit H-Same Source
02/28 0000 Unit ended the month in Mode 1, 86% RX power.
~1}}
 
SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKETNO UNIT NAME             f~~V(~
DATE                 Q3LK194 COMPLETED BY IKaKBau Outage                   Method of Duration                 Shutting Down                         System Component      Cause and Corrective Action Date       Type"     Hours       Reason2       Reactor3           LER No.       Code4   Code5       to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of February 1994 "F-Forced             2Reaso                                      3Method:                                  "Exhibit F - Instructions for Preparation S-Scheduled             A-Equipment Failure(Explain)               1-Manual                                  of the Data Entry Sheets for Licensee B-Maintenance or Test                       2-Manual Scram                            -Event Report (LER) File (NUREG0161)
C-Refueling                                3-Automatic Scram D-Regulatory Restriction                    4-Continuation from Previous Month E-Operator Training 8 License              5-Reduction of 20% or Greater in the     Exhibit H-Same Source Examination                                Past 24 Hours F-Administrative                            9-Other-(Explain)
G-Operational Error H-Other (Explain)
 
~ 1}}

Revision as of 08:26, 29 October 2019

Monthly Operating Repts for Feb 1994 for Palo Verde Nuclear Generating Station Units 1,2 & 3.W/940314 Ltr
ML17310B100
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 02/28/1994
From: Ecklund B
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
471-00202-BSE, 471-202-BSE, NUDOCS 9403150320
Download: ML17310B100 (25)


Text

ACCELERATE DISTRIBUTION DEMO STRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION ECKLUND,B.S. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION I

Monthly operating repts for Feb 199 j

SUBJECT:

o Verde Nuclear D Generating Station units 1,2, & 3. /940314 tr.

DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR TITLE: Monthly Operating Report (per Tech Specs)

ENCL g SIZE: (

NOTES: STANDARDIZED PLANT 05000528 A Standardized plant. 05000529 Standardized plant. 05000530 D RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDV PD 1 1 POLICH, T 1 1 TRAN,L 1 1 INTERNAL: ACRS 10 10 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 NRR/DORS/OEAB 1 1 NRR/DRIL/RPEB 1 1 ~EG F 01 1 1 RGN5 1 1 EXTERNAL EGGG BRYCE I J ~ H 1 1 NRC PDR 1 1 NSIC 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22

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Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O, BOX 52034 ~ PHOENIX. ARIZONA 85072-2034 41 7-00202-BSE March 14, 1994 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, and 3 Docket Nos. STN 50-528/529/530 Monthly Operating Reports for February 1994

'e -02 0 . - 6-02 Enclosed are the Monthly Operating Reports for February 1994, prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the PVNGS Units 1, 2, and 3 Operating Licenses. By copy of this letter, Arizona Public Service Company is also forwarding the Monthly Operating Reports to the Regional Administrator, NRC Region V.

If you have any questions, please contact me at (602) 340-4068.

Sincerely, BSE/gez Enclosures CC: K. E. Perkins (all w/enclosures)

A. H. Gutterman NRC Senior Resident Inspector INPO Records Center Utility Data Institute 94033,50320 940228

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. QL529 UNIT NAME ~gal~

DATE 93LQBLK4 COMPLETED BY ~~Qlgrgl MONTH: February 1994 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 1070 17 1068 1069 18 1071 1070 19 1072 1073 20 1072 1072 21 1072 1073 22 1072 1072 23 1073 1070 24 1072 1072 25 1072 10 1072 26 1071 1071 27 1070 12 1072 28 1076 13 1072 29 14 1072 30 15 1072 31 16 1071

REFUELING INFORMATION DOCKET NO. QL525 UNIT NAME DATE 93LQBLK COMPLETED BY ~~Qlgagl Scheduled date for next refueling shutdown.

The 5th refueling outage is tentatively scheduled for 03/13/95.

Scheduled date for restart following refueling.

06/01/95.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

No.

Scheduled date for submitting proposed licensing action and supporting information.

N/A.

Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.

N/A.

The number of fuel assemblies.

b) In the spent fuel storage pool.

Licensed spent fuel storage capacity.

Intended change in spent fuel storage capacity. ~ng Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

2005 (18 Month reloads and full core discharge capability).

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. QL529 UNIT NAME DATE 938MLRk COMPLETED BY ~~klLUzl 02/01 0000 Unit began the month in Mode 1, 85% RX power.

02/28 1228 Commenced power increase to 86% at the direction of the Plant Manager.

02/28 1305 Stabilized RX power at 86%.

02/28 2400 Unit ended the month in Mode 1, 86% RX power.

SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKET NO UNIT NAME

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DATE QQJ///Qg COMPLETED BY ~BIX&I+.

IKRKHSH Outage Method of Duration Shutting Down System Component Cause and Corrective Action No. Date Type" Hours Reason2 Reactor3 LER No. Code4 Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of February 1994 1F-Forced Reason: 3Method: 4Exhibit F - Instructions for Preparation S-Scheduled A-Equipment Failure(Explain) 1-Manual of the Data Entry Sheets for Licensee B-Maintenance or Test 2-Manual Scram Event Report (LER) File (NUREG0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from Previous Month E-Operator Training 8 License 5-Reduction of 20% or Greater in the Exhibit H-Same Source Examination Past 24 Hours F-Administrative 9-Other-(Explain)

G-Operational Error H-Other (Explain)

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. SL529 UNIT NAME MEzR2 DATE QZQGLK COMPLETED BY ~MGI~

MONTH: February 1994 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 17 18 19 20 21 22 23 24 25 10 26 27 12 28 13 29 14 30 15 31 16

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REFUELING INFORMATION DOCKET NO. ~29 UNIT NAME MbLikR2 DATE 93LQSLR4 COMPLETED BY EMMY~

Scheduled date for next refueling shutdown.

The 5th refueling outage is tentatively scheduled for 09/17/94, however, it is more likely to take place in the first quarter of 1995.

Scheduled date for restart following refueling.

12/06/94, or 80 days following the new refueling shutdown date.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

A change may. be required to Technical Specification 3.9.6 to raise the overload cutoff limit to accommodate the new fuel assembly modification. Also, Technical Specification Section 6.9.1.10 will be modified to add the new Inlet Flow Distribution methodology.

Scheduled date for submitting proposed licensing action and supporting information.

10/13/94.

Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.

The fuel assembly will consist of a denser fuel pellet, Erbium burnable absorber and guardian grid. A primary temperature drop of 10' is currently planned.

e) to the core. ~

The number of fuel assemblies.

b) In the spent fuel storage pool. ~~

Licensed spent fuel storage capacity. ~99 Intended change in spent fuel storage capacity. ~~

Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

2005 (18 Month reloads and full core discharge capability).

0

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 54529 UNIT NAME ~59.~

DATE QBLQBM COMPLETED BY 02/01 0000 Unit began the month in Mode 5, mid-cycle outage in progress.

02/28 2400 Unit ended the month in Mode 5, mid-cycle outage in progress.

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SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKET NO SLURB UNIT NAME LVHGR2 DATE QZ99LRk COMPLETED BY ~B~RLVEKI tuRISLIM Outage Method of Duration Shutting Down System Component Cause and Corrective Action Date Type" Hours Reason2 Reactor3 LER No. Code4 Code5 to Prevent Occurrence 94-01 01/08/94 S 672.0 N/A N/A N/A Continuation of planned mid-cycle from previous month.

1F Forced 2R 3Method: 4Exhibit F - Instructions for Preparation S-Scheduled A-Equipment Failure(Explain) 1-Manual of the Data Entry Sheets for Licensee B-Maintenance or Test 2-Manual Scram Event Report (LER) File (NUREG0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from Previous Month E-Operator Training 8 License 5-Reduction of 20% or Greater in the Exhibit H-Same Source Examination Past 24 Hours F-Administrative 9-Other-(Explain)

G-Operational Error H-Other (Explain)

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. 59-'539 UNIT NAME DATE Q3LGGLR4 COMPLETED BY ~MB!~

MONTH: February 1994 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 1071 17 1062 1069 18 1067 1067 19 1067 1068 20 1070 1067 21 1069 1071 22 1072 1069 23 1073 1069 24 1072 1067 25 1071 10 1069 26 1069 1066 27 1070 12 1064 28 1078 13 1067 29 14 1069 30 15 1069 31 16 1067

REFUELING INFORMATION DOCKET NO. 59-'QQ UNIT NAME LVHGR2 DATE QZQSLK COMPLETED BY Q~QR!led Scheduled date for next refueling shutdown.

03/19/94, 4th refueling.

Scheduled date for restart following refueling.

06/07/94.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

At present, four Tech. Spec. changes are in process. One for increasing the radially averaged weight percent of U235 in fuel rods to 4.30w/o. The other is to change the DNBR setpoint limit from 1.24 to 1.30. These are generic Tech. Spec. changes, and will be implemented on a Unit by Unit basis, beginning with U3C5.

Also, there are two other Tech. Spec. changes that will allow U3C5 to operate at 100% power due to the steam generator issues.

Scheduled date for submitting proposed licensing action and supporting information.

The fuel enrichment change was submitted in October 1993 and the DNBR setpoint change was submitted in January 1994.

Important Licensing considerations associated with refueling, e.gnew or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, and new operating procedures.

U3C5 will incorporate a new higher maximum enrichment level of 4.30w/o U235 and will also utilize a new integral burnable absorber, Erbium.

The NRC granted a license amendment (No. 35) which allows the use of 80 fuel rods clad with advanced zirconium based alloys (other than Zircaioy<) in two fuel assemblies during Unit 3 Cycles 4, 5, and 6 for in-reactor performance evaluation. Date of issuance was July 20, 1992.

e) tn the core. ~

The number of fuel assemblies.

b) In the spent fuel storage pool.

Licensed spent fuel storage capacity.

Intended change in spent fuel storage capacity.

Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

2005 (18 Month reloads and full core discharge capability).

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. K=HO UNIT NAME ElblGR2 DATE QBNBLK4 02/01 0000 Unit began the month in Mode 1, 85% RX power.

02/28 1002 Commenced power increase to 86% at the direction of the Plant Manager.

02/28 1136 Stabilized RX power at 86%.

02/28 0000 Unit ended the month in Mode 1, 86% RX power.

SHUTDOWNS AND POWER REDUCTIONS February 1994 DOCKETNO UNIT NAME f~~V(~

DATE Q3LK194 COMPLETED BY IKaKBau Outage Method of Duration Shutting Down System Component Cause and Corrective Action Date Type" Hours Reason2 Reactor3 LER No. Code4 Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of February 1994 "F-Forced 2Reaso 3Method: "Exhibit F - Instructions for Preparation S-Scheduled A-Equipment Failure(Explain) 1-Manual of the Data Entry Sheets for Licensee B-Maintenance or Test 2-Manual Scram -Event Report (LER) File (NUREG0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from Previous Month E-Operator Training 8 License 5-Reduction of 20% or Greater in the Exhibit H-Same Source Examination Past 24 Hours F-Administrative 9-Other-(Explain)

G-Operational Error H-Other (Explain)

~ 1