ML17303A738
| ML17303A738 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/31/1987 |
| From: | Haynes J, Hull J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 212-00085-JGH-T, 212-85-JGH-T, NUDOCS 8801200133 | |
| Download: ML17303A738 (40) | |
Text
J ACCELERATED DISJ BUTION DEMONSTRATION SYSTEM
~i r
0 REGULATORY INFORMATION DIST QUTION SYSTEM (RIDS)
SPjaz i~
ACCESSION NBR: 8801200133 DOC. DATE: 8+/ 1 /31 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000)28 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 HULL,J.L.
Arizona Nuclear Power Project (formerly Arizona Public Serv HAYNES,J.G.
Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
Monthly operating repts for Dec 1987 W/880113 l r.
-DISTRIBUTION CODE:
IE24D COPIES RECEIVED:LTR EN SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:Standardized plant.
Standardized plant.
Standardized plant.
RECIPIENT ID CODE/NAME PD5 LA LICITRA,E INTERNAL: ACRS AEOD/DSP/TPAB NRR/DLPQ/PEB NRR/DREB PB g~G 01 EXTERNAL: EG&G GROH,M NRC PDR NOTES COPIES LTTR ENCL 1
0 1
0 10 10 1
1 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD5 PD DAVIS,M AEOD/DOA ARM TECH ADV NRR/DOEA/EAB NRR/PMAS/ILRB RGN5 LPDR NSIC COPIES LTTR ENCL 5
5 1
0 1
1 2
2 1
1 1
1 1
1 1
1 1
1 050005288 05000529 05000530 A
D 8j A
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 33 ENCL 30
f P
t
NRC MONTHLY OPERATING REPORT
-DOCKET NO.
UNIT NAME DATE CONPLETED BY TELEPHONE 50 528 PVNGS-1 01/08/88 J.L. Hull 602-393-2679 OPERATING STATUS 2 ~
3.
4 ~
5.6.7.
8.
Unit Name.
Palo Verde Nuclear Generating Station~ Unit 1 Reporting Peripd:
December 1987 Licensed Thermal Power (NMt): 3800 Nameplate Rating (Gross NMe): 1403 Design Electrical Rating (Net MWe):
1270 Maximum Dependable Capacity (Gross MMe): 9.303 Maximum Dependable Capacity (Net NMe):
1221 If Changes Occur In Capacit,y Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
9.
10.
Power Level to Vhich Restricted, Xf Any (Net MMe):
NONE Reasons For Restrictions,.If Any.
This Month Yr.-to-Date Cumulative 11
'2.
13.
14.
15.
16.
17
'8.
19.
20.
21
'2.
23.
24.
Hours in Reporting Period 744 Number of Hours Reactor alas'ritical 0.0 Reactor Reserve Shutdown Hours 0.0 Hours Generator On-Line 0.0 Unit, Reserve Shutdown Hours 0.0 Gross Thermal Energy Generated (MMH) 0.0 Gross Electrical Energy Generated (MMH) 0.0 Net Electrical Energy Generated (MMH) 0.0 Unit Service Factor 0.0%
Unit Availability Factor 0.0r-Unit Capacity Factor (Using MDC Net)
Unit Capacity Factor (Using DER Net,)
- 0. Oii Unit Forced Outage'ate 0.0r
,Shutdowns Scheduled Over Next 6 Months of Each): Currently in refueling shutdo 8760 16872 4 589.1 g
N 0.0 4 505.5 g
r 0.0 9 977.2 g
0.0, 9 717.1 C.
0.0 16 140 694.
C.
J--
5 S16 400.
C.
C 5 268 268.6 C
51.4~
51. 4'4 35~032~837 12~143~300 11~327~924.6 57.6R 57.SR
~
55 ~ 0:~
47.4:c 52-9r 3l.7C 24.4~
a P
~
w
~
(Type, Date, and Duration wn 26.
If Shutdown At End of Report Period Estimated Date of Startup:
Est.imated Node 2 entry~ 01/14/87 Units in Test Status (Prior To Commercial Operation):
880i200133 PDR ADOCK
.R INXTIAL CRXTICALXTY INITIALELECTRXCXTY CONMERCIAL OPERATXON 87i2Zi 5000528
..nen,!
I Forecast 5/85 6/85 11/85 Achieved 5/25/85 6/10/85 1/28/86
l
AVERAGE DAILY UNIT POMER LEVEL DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-528 PVNGS-1 01/08/88
.J.L. Hull 602-393-2679 MONTH:
December 1987 DAY AVERAGE DAILY POMER LEVEL DAY AVERAGE DAILY POSER LEVEL 1
0 3
0
'19 20 0
0 22 0
23 0
9 I
10 0
25 26 27 0
~
~
12 0
28 0
0 29 0
30 15 0
I I
l 7
~
e t,
I II
REFUELING INFORMATION DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE.
50-528 PVNGS-1 01/08/88 J.L. Hull 602-393-2679 0
Scheduled date for next refueling shutdown.
10/02/87 2.
'cheduled date for restart following refueling.
01/14/88 3.
Mill refueling or resumption or operation thereafter require a
Technical Specification change or other license amendment' Yes Required Technical Specifications are as follows:
5.3.1, 3/4.1.1.2i 3/4.1.1.3, 3/4.2.8, 3/4.1.3.1p 3/4 3.1, 3/4 1 '
6p 3/4 ' 'p 2
1'~ 3/4 ' 'p 3/4 2 1p 3/4 '
4~ 3/4 '
7p 3/4.3.2 4o Scheduled date for submitting proposed licensing action and supporting information.
July 1, 1987 5.
Important Licensing considerations associated with refueling, e.g.
nev or different fuel design or supplier, unrevieved design or performance analysis methods, significant changes in fuel
- design, new operating procedures.
t a) Modification of the CPCs under the CPC Improvement Program (CIP) and the Statistical Comgination of Uncertainties (SCU) Program.
b)
Maximum peak pin fuel enrichment vill be 4.05 v 4 U235.
c) The fuel vendor for"the following next 5 reloads vill be Combustion Engineering.
i I
REFUELING INFORMATION DOCKET NO.
50-528 UNIT PVNGS-1 DATE 01/08/88 COMPLETED BY J.L. Hull TELEPHONE
'02-393-2679 (Continued) 6.
The number of fuel,assemblies.
a)
In the core.
241 b)
In the spent fuel storage pool.
80 7.
Licensed spent fuel storage capacity.
1329 Intended change in spent fuel storage capacity.
None 8.
ProJected date of last refueling that, can be discharged to spent fuel storage pool assuming present capacity.
2006 (18 Months reloads and full core discharge capability).
dt I
I II
~
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-528 UNIT PVNGS-1 DATE 01/08/88 COMPLETED BY J.L. Hull TELEPHONE
" 602-393-2679 December 1987 12/01 12/02 12/31 Unit in Refueling Outage
- Mode 6.
0500 Entered Mode 5 Unit in Refueling Outage
- Mode 5.
0 f
b
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
x 50-528 PVNGS-1 Ol/08 88 J.L. Hull 393-2679 Method of Duration 2
Shutting System<
Component>
No.
Date Type
~ Hours Reason Down Reactor LER NO.
Code Code Cause and Corrective Action to Prevent Recurrence 10 Continued S
C N/A N/A N/A Unit shut down due to Refueling Outage.
1 F-Forced S-Scheduled 2 Reason:
A-Equipment Failure (Explain) 6-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training g License Pxamination F-Administrative G-Operational Error (Explain)
.II-Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20X or Greater in the Past 24 lfours tt-Othnr (Rxn1nin) 4 Exhibit F - Instructions for Preparation of Data Entry Sheets for Liccnscc Event Report (LER) File (IIURFS 0161) 5 Exhibit II-Same Source
0 1
l4 f,
NRC MONTHLY OPERATING. REPORT DOCKET NO.
UNXT NAME DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 01/08/88 J.L. Hull 602-393-2679 OPERATING STATUS 1 ~
2 ~
3 ~
5.
6.
7.
8.
Un'it Name.
Palo Verde Nuclear Generating StationL Unit 2 Reporting Period:
December 1987 Licensed Thermal Power (MMt): 3800
~
Nameplate Rating (Gross MNe): 1403 Design Electrical Rating (Net MNe):
1270 Maximum Dependable Capacity (Gross MMe): 1303 Maximum Dependable Capacity (Net M41e):
1221 If Changes Occur Xn Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons'.
9.
10.
Power Level to Which Restricted, If Any (Net MVe):
NONE Reasons For Restrictions, If Any:
This 'Month Yr.-to-Date Cumulative 11
'2
'3
'4
'5.
16.
17.
18.
19.
20.
21.
22
'3
'4.
25.
26
'44 0
24 912 161.
L L
- 78. 3tl:
- 78. 3'<
Units in Test Status (Prior To Commercial Operation):
Hours in Reporting Period 744 87SO Number of Hours Reactor
@as Critical
~
6 985.2 Reactor Reserve Shutdown Hours 0
Hours Generator On-Line 744 6L859.2 Unit Reserve Shutdown Hours 0
0 Gross Thermal Energy Generated (MMH) 2L799L320.
Gross Electrical Energy Generated (MVH) 987LOOO.
8L733L100L Net Electrical Energy Generated
.(MMH) 933L198.
8L190L044; Unit Service Factor 1 OOLOGY Unit Availability Factor 100.0r.
Unit Capacity Factor (Using MDC Net) 102L7r.
7SL6:c Unit Capacity Factor (Usin DER Net) g
- 98. 8r.
- 73. 6tc E
Unit Forced Outage Rate OLOr.
5LS'c Shutdowns Scheduled Over Next S Months (Type, Date, 'and of Each):
Scheduled Date for next Refueling Shutdown Duration of refueling shutdown approximately If Shutdown At End of Report Period, Estimated Date of I
1125S 9 275.1 0
9 12S.2 33L207L1ST L
L 661 270 10L936L882 81L1.c 81.1~
- 79. 6'~
TS. 6:~
Duration 2/21/88 84 days Startup'.
INITIALCRXTICALXTY INITIAL ELECTRICITY COMMERCIAL OPERATION Forecast 3/86 6/86 11/86 Achiev'ed 4/18/86 5/20/86 9/'19/86
'h I
I
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 01/08/88 J.L. Hull 602-393-2679 MONTH:
December 1987 DAY AVERAGE DAILY POMER LEVEL DAY AVERAGE DAILY POSER LEVEL 1
272 1~267 14267 267 1~263 1~263 1~267 1~267 1~263 17 20 22 23 24
" 25 267 1~259 267 1 263 1~267 1 272 1 267 263 1~188 10 1 272 26
>259 1g 272 1 247 28 1 263 272 14 1~267 15 272 30 1~263 267 263 1~267
4 l
I II
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4 REFUELING INFORMATION DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50"529 PVNGS-2 01/08/88 J.L. Hull 602-393-2679 Scheduled date for next refueling shutdovn,.
02/21/88 2.
Scheduled date for restart folloving refueling.
05/15/88 3 ~
Mill refueling or resumption or operation thereafter require a
Technical Specification change or other license amendment.2 YES Shat vill these beV 3/4 1.1.2
, 3/4 1.1..3
, 3/4 2.8 p 3/4 1.3.1
, 3/4 3.1 3/4 1 3 6p 3/4 2 5 p 3/4 2 ~ 1 f 3/4 2 ~ 4 p 3/4 2 3 p 3/4 3 2 2.1.1.1 4 ~
Scheduled date for submitting proposed licensing action and supporting information.
12/15/87 Important Licensing considerations associated vith refueling, e.g.
nev or, different fuel design or supplier, unrevieved design or performance analysis methods, significant changes in fuel
- design, nev operating procedures.
a) Modification of the CPCs under the CPC Improvement Program (CIP) and the Statistical Combination of Uncertainties (SCU) Program.
b)
Maximum peak pin fuel enrichment wi'll be 4.05 v a U235.
c)
The fuel vendor for the folloving next 5 reloads vill be Combustion Engineeri'ng.
I lf 1
Pl
REFUELlNG lNFQRMATiON DOCKET NO.
UNlT DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 01/08/88 J.L. Hull 602-393-2679
-(Continued)
The number of fuel assemblies.
h a)
Xn the core.
243.
b)
In the spent fuel storage pool.
0 7.
8.
Licensed spent fuel storage capacity.
1329 Xntended change in spent fuel storage capacity.
'one Progected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2006 (18 Months reloads and full core discharge.capability)
~
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~
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A L
SUMMARY
OF <<OPERATlNG EXPERXENCE FOR THE MONTH DOCKET NO.
UNlT DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 01/08/88 J.L. Hull 602-393-2679 December 1987 12/01 12/25 0923 Reactor Po~er 100'.
Po~er reduction to 75A for monthly surveillance testing and secondary side maintenance on the moisture separator reheater.
12/26 12/27 12/27 12/31 0030 0515 Reactor Power at 100'.
2400 Reactor Power at 100'.
Completed power reduction to 75'eactor Po~er at 90~
I 0
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UNIT SHUTDOMNS AND POMHR REDUCTIONS N
UNIT NAME:
PVNGS=..2
- ~/8 COMPLETED BY:
J.L. Hull Method of DUIatioll Shutting 3
System<
Component No.
Date Type
-Hours Reason Down Reactor LER NO.
Code Code Cause and Corrective Action to Prevent Recurrence 17 12/25 S
N/A B
I55 N/A N/A N/A Power reduction to 75% for monthly surveillance test'nd secondary maintenance (MSR leak repair) 1 F-Forced S-Scheduled 2 Reason:
A-Equipment Failure (Explain)
II-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training g License Examination F-Administrative G-Operational Error (Explain)
.If-Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20'r Greater in the Past 24 ltours 0-Other (Fxn1nIn) 4 Exhibit F Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (IIUREG 0161)
Exhibit II-Same Source
I' II
NRC MONTHLY OPERATING REPORT DOCKET NO.
UNIT NANE DATE COMPLETED BY TELEPHONE 50-530 PVNGS-3
'01/08/88 J. L. Hull 602-393-2679 OPERATXNG STATUS 1 ~
2 ~
3.
4 ~5.
6.
7 ~8.
9.
10.
Unit Name.
Palo Verde Nuclear Generating Station~ Unit 3 Reporting Period:
December 1987 Licensed Thermal Power (NVt): 3800 Nameplate Rating (Gross NNe):
1403 Design Electrical Rating (Net MNe):
1270 Maximum Dependable Capacity (Gross MMe): 1303 Maximum Dependable Capacit,y (Net NMe):
1221 If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
/
Power Level to Mhich Restricted, If Any (Net MMe):
NONE Reasons For Restrictions, If Any.
This Month Yr. -to-Date Cumulat,ive 11.
12.
13
'4
'5.
17.
18.
19.
20.
21
'2.
23-24.
Hours in Reporting Period Number of Hours Reactor Has Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (NMH)
Gross Electrical Energy Generated (MPH)
Net Electrical Energy Generated (MMH)
Unit Service Factor Unit. Availability Factor Unit Capacity Factor (Using MDC Net)
Unit Capacity Factor (Using DER Net)
Unit, Forced Outage Rate Shutdowns Scheduled Over Ne of Each):
744 6048 6048 677.0 945.9 945.9 eoe.e 0620.7 0
620.7 0
1 192 385.
364 100.
g 319 661.
g
~
0 244 187.0 C.
365 300.
g
~
, 319 661.
~
g
~
0 0
244 187.
365 300.
g W
319 661.
g
~
0 0'
0 0
0 xt 6 Months (Type, Date, and Duration 25.
26.
If Shutdown At End of Report Period, Estimated Date of Startup.
Units in Test Status (Prior To Commercial Operation):
INXTIAL CRITICALITY INITIAL ELECTRICITY CONNERCIAL OPERATION Forecast 07/87
, 07/87 09/87 Achieved 10/25/87 11/28/87
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, I
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-530 PVNGS-3 01/08/88 J.L. Hull 602-393-2679 MONTH:
De+ember 1987 DAY AVERAGE DAILY 'POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 70 2'8 3
120 126 141 20 540 552 22 548 3
23 485 172 24 623 10 551 907 27 970 13 28 1 ~036 361 14 30 197 1~149
1
~
~
~
REFUELXNG INFORMATXON DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-530 PVNGS-8 01/08/88 J.L. Hull 602-393-2679 Scheduled date for next refueling shutdown.
02/25/89 Scheduled date for restart following refueling.
05/05/89 3 ~
Mill refueling or resumption or operation thereafter require a
Technical Specification change or other license amendment2 Not Yet Determined Mhat ~ill these be2 Not Yet Determined
.Scheduled date for submitting proposed licensing action and supporting information.
Not Yet Determined 5.
Important Licensing considerations associated with refueling, e.g.
new or different fuel design or supplier, unrevieved design or performance analysis methods, significant changes in fuel
- design, new operating procedures.
Not Yet Determined
> 6..
The number of fuel assemblies.
a)
Xn the core.
249.
b)
Xn the spent fuel storage pool.
7 ~
Licensed spent fuel storage capacity.
1329 f
Intended change in spent fuel storage capacity.
None 8.
Progected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2007 (18 Months reloads and full core discharge capability).
1 I
I 1
1
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-530 PVNGS-3 01/08/88 J.L. Hull 602-393-2679 December 1987 12/01 12/02 1750 Reactor at 124 Node Tripped turbine due to steam leak between control valve and the high pressure turbine Reactor power at approximately 19.5c.
12/03 0026 Synchronized Main Generator to grid 12/05 1140 Reactor at approximately 19'he reactor was tripped for testing of remote shutdown panel.
Mode 3 12/06 12/06 12/07 1302 1508 1656
- 0201, Reactor critical Node 2
Entered Mode 1
Synchronized Main Generator to grid Reactor power approximately 19'owering power to 2A to allow for turbine work.
12/07 12/07 0315 0429 Tripped Nain Turbine, Node 3 Entered Mode 2, reactor ciitical 12/07 1112 12/07 1615 12/07 2325 Entered Node Synchronized Main Generator to grid Tripped Main Generator for Subsynchronous Resonance Testing@ reactor at approximately 13'.
12/08 0215 12/08 1330 12/09 0137 12/17 0430 Synchronized Nain Generator to grid Reactor power 30'eactor power 504 Reactor trip occurred as a result of Lo DNBR calculated by CPCe.
During insertion of part. length CEAs a subgroup deviation occurred between groups P1 and P2, causing the insertion of a subgroup deviation penalty factor.
I I
~
~
P
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-530 PVNGS-3 01/08/88 J.L. Hull 602-393-2679 December 1987 12/18 12/19 12/19 12/19 12/19 I
12/19 12/19 12/24 12/26 12/29 2207 0412 0625 0838 1535 1610 1439 0827 Reactor Critical Mode 2 Entered Mode 1
Synchronized to grid Tuxbine tripped due to high vibration Synchxonized Main Generator to grid Tuxbine tripped on reverse power.
Synchronized Main Generator to grid Reactor power 60'eactor power 80:4 Turbine trip following a main generator trip on high stator cooling water temperature.
Temperature svitches vere miscalibrated, initiating a generator trip when stator cooling vater temperatures.
wer'e in normal range.
12/29 12/30 12/30 12/31 12/31 1000 0833 1821 2400 Entered Mode 2 Entered Mode 1
Synchronized Main Generator to grid Reactor power 100'.
Reactor power 100%
~
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~
uNiT SHUTDOWNS AND POMER REDUCTIONS DOCKET NO:
UNIT NAtK:
DATE:
COMPLETED BY:
TELEPHONE:
50-530 PUNGS-3 1/8/88 J.L. Hull 602-393-2679 Method of Duration Shutting 3
System<
Component>
No.
Date Type Hours Reason Down Reactor LER NO.
Code Code Cause and Corrective Action to Prevent Recurrence 12/02 F
6.6 N/A N/A N/A N/A Tripped turbine due to steam leak between control valve an(
the High Pressure Turbine.
5 12/05 S
29.8 B
N/A N/A Reactor tripped for testing of Remote Shutdown Panel.
6 12/07 F
13.0 N/A N/A N/A Tripped Turbine due to main-tenance work on Turbine.
7 12/07 S
2.8 N/A N/A N/A N/A Tripped Turbine for subsynchronous resonance testing.
8 12/17 F
49;9 3-87-004 Reactor trip occurred as a result of Lo DNBR calculated by CPCs.
During insertion of part length CEAs a subgroup deviation occurred be-tween groups Pl and P2, causing~~
insertion of a subgroup deviate~~
penalty factor.
9 12/19 F
10 12/19 F
11 12/29 F
7.0 28.2 N/A N/A N/A N/A N/A N/A N/A N/A N/A Turbine trip due to high vibration.
Turbine trip due to reverse power.
Turbine trip due to SBCS Quick Open, recalibrated temperature switches.
1 F'-Forced S-Schcdulcd Reason:
A-Equipment Failure (Explain)
II-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator TraininE II License Fxamination F-Administrative C-Operational Error (Explain)
.II-Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20X or Creator in the Past 24 Ilours e Orhr r fpxnluin) 4 Exhibit F - Instructions for Preparation of Data Entry Sheets for Licensee Event Rcport (LER) File (IIUREC 0161) 5 Exhibit II-Same Source
1(
fi I
l
Arizona Nuclear Power Project P.O. BOX 52034
~
PHOENIX, ARIZONA85072-2034 Docket Nos.
STN 50-528/529/530 January 13, 1988 212-00085-JGH/TJB U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk Gentlemen:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
December Monthly Operating Report File: 88-024-404 88-056-026 Attached is the December Monthly Operating Reports prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A
(Technical Specifications) to the Palo Verde Nuclear Generating
- Station, Units 1,
2 and 3
Operating Licenses.
By copy of this letter, we are also forwarding a copy of the Monthly Operating Reports to the Regional Administrator of the Region V Office.
If you have any questions, please contact Mr. T. J.
Bloom, at (602) 371-4187.
Very truly yours, Py~>~
J.
G. Haynes Vice President Nuclear Production JGH/TJB/rw Attachments cc:
0.
M.
De Michele E. E.
Van Brunt, Jr.
J.
B. Martin E.
A. Licitra A. C. Gehr J.
A. Amenta INPO Records Center (all w/a)
E Wy