ML20237K155
| ML20237K155 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/31/1987 |
| From: | Colville J, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 192-00259-JGH-T, 192-259-JGH-T, NUDOCS 8708190110 | |
| Download: ML20237K155 (16) | |
Text
l NRC MONTHLY OPERATING REPORT DOCKET NO.
50-528 i
[9 @5__((~~((
j 5
UNIT NAME 4
DATE 0_8/09/87---------_--
j COMPLETED BY J.M._Cglv111e TELEPHONE 602-393
_26_79---
O_ P E R A T I N _G S_ T _A T_ U S i
1.
Unit Name: Pgig_Verdg_Nuciggr_Ggggrgting_gtgtignt_Ugit_1 2.
Reporting Period: _ July _19@Z 3.
Licensed Thermal Power (MWt): 3@gg 4.
Nameplate Rating (Gross MWe): 149@
5.
Design Electrical Rating (Net MWe):
1@Zg 6.
Maximum Dependable Capacity (Gross MWe): 1@g@
7.
Maximum Dependable Capacity (Net MWe):
12@l 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
9.
Power Level to Which Restricted, If Any (Net MWe):
_NgNE_________
10.
Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
___Z44____
___596@____
__1@299___
12.
Number of Hours Reactor Was Critical
____@S Z__
__@tiggt4__
_8 578.5 t
t 13.
Reactor Reserve Shutdown j
Hours
_____Q.g__
______Q.Q__
_____g.g__
)
14.
Hours Generator On-Line
____19.1__
__@t111.4__
_qt@2@____
15.
Unit Reserve Shutdown Hours
_____g.Q__
______g.g__
_____g.g__
16.
Gross Thermal Energy Generated (MWH)
___29 941.
11 tg@2 5g7.
29 954 739 t
3 1
3 17.
Gross Electrical Energy l
Generated (MWH)
____@tggg.
_@tg44t5gg.
19t@Z1 1gg 7
18.
Net Electrical Energy Generated (MWH)
_______g.g
@t@g4 9@5.@
9 @@4 S91.@
3 t
t 19.
Unit Service Factor
____@.@3__
____gi 23__
_____@@t13_
t 20.
Unit Availability Factor
____2.@3__
____@i.23__
_____@3.13_
21.
Unit Capacity Factor (Using MDC Net)
____g.93__
____5@.g3__
____@g.93_
22.
Unit Capacity Factor (Using DER Net)
____Q.93__
____55.g3__
____52.Z3, 23.
Unit Forced Outage Rate
___9Z.43__
____gg.g3__
____2@.@y_
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Scheduled date for next refuelino shutdown-9/12/87 -
l Dyggtigg_gf_rg{ygligg_abytdgwg_gggggximgtgly_@p_dgyg___
25.
If Shutdown At End of Report Period, Estimated Date of Startup:
l 26.
Unite ~In~ Teat SE$tuA~IPrI~o~r~To 5cEm~er~cI;I 5p rstionTI-~~~~~-~~-~~
~
~
~~
e Forecast Achieved' INITIAL CRITICALITY 5/85 5/25/85 l
INITIAL ELECTRICITY
[~@2g5~[
~ 2_552g5[
COMMERCIAL OPERATION 11/85 1/28/86 t
8708190110 870731 1g2,q PDR ADOCK 05000528 R
'I j
1 l,
AVERAGE DAILY UNZT POWER LEVEL 1
DOCKET NO.
50-528
~~ PV G52 ~~~~~~~~
I UNIT --------
1 COMPLETED BY J.M.
Colville j
-_-_0_2__25_5_5_25_575~~~
5 TELEPHONE 1
+
---_lJu Y__198_7-- -
I MONT_H:
h i
l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
0 17 O
l 2
0 18 O
3 O
19 O
0 4
0 20 ----_-----------_---------
i l
5
-_--________0_____________
21 __-_-______ 0_____________
U 6
0 22 0
7 O
23 0
8 0
24 0
9 0
25 0
l 10 0
26 _---_-__---_0__._------_----
11 0
27 O
12 0
28 O
13 0
29 O
I 14 0
30 0
15 0
31 279 16 0
l l
J I
REFUELING INFORMATION 4
i i
DOCKET NO.
50-528 l
UNIT PVNGS-1______
j DATE 08/09/87 1
l COMPLETED BY
(([M[~[Ch[E(([~e TELEPHONE 602-393-2679 i
t l
1.
Scheduled date for next refueling shutdown.
I 09/12/87 2.
Scheduled date for restart following refueling.
11/20/87 l
l 3.
Will refueling or resunption or operstion thereafter require a Technical Specification change or other license amendment?
1 Yes J
l Required Technical Specifications are as follows:
5.3.1, 3/4.1.1.2, 3/4.1.1.3, 3/4.2.8, 3/4.1.3.1, 3/4.3.1.
3/4.1.3.6, 3/4.3.1, 2.1.1, 3/4.2.5, 3/4.2.1, 3/4.2.4, 3/4.2.7, 3/4.3.2 1
I 4.
Scheduled date for submitting proposed licensing action and supporting information.
July 1, 1987 5.
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, new operating procedures.
I I
a) Modification of the CPCs under the CPC Improvement Program l
(CIP) and the Statistical Combination of Uncertainties l
(SCU) Program.
i b) Maximum peak pin fuel enrichment will be 4.05 w % U235.
1 c) The fuel vendor for the following next 5 reloads will be i
Combustion Engineering.
l l
i l
i i
1 l
J
(
l REFUELING INFORMATION j
i i
DOCKET NO.
50-528 ------
4 UNIT F0s55 1 i
DATE 6526[925![_~[~_[
l COMPLETED BY J.M._Colville l
l l
TELEPHONE 602-393-2679 l
l l
(Continued) 6.
The number of fuel assemblies.
j a)
In the core. _ _ _ _ _2 4 _1 _ _ _ _
i b)
In the spent fuel storage pool.
______O______
7.
Licensed spent fuel storage capacity.
___1329___
Intended change in spent fuel storage capacity.
___Noge___
8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
l 2006 (18 Months reloads and full core discharge capability).
i l
1 i
1 l
1 1
4 l
[
j
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
99-92p_______
UNIT PVNGg-1______
DATE 98/92/@7_____
COMPLETED BY J.M._Colville TELEPHONE
@g2-323-2g7p_
guly_1982 3
07/01 0000 Unit in Mode 4.
r 07/04 2202 While in Mode 4, both LPSI pumps experienced catastrophic seal failures.
In order to maintain shutdown cooling, the plant was forced to go to Mode 5 to use the Containment Spray pumps for shutdown cooling, where the Containment Spray pumps have a 2OOF upper temperature limit - Entered Mode 5.
07/28 0234 Entered Mode 4.
7/28 1621 Entered Mode 3.
7/30 1216 Reactor la critical - Entered Mode 2.
7/30 2145 Entered Mode 1.
7/31 0455 Synchronized Main Generator to Grid.
f l
l 7/31 2100 Reactor power at 50%.
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NRC MONTHLY' OPERATING REPORT DOCKET NO.
@g-@29_______
UNIT NAME PVNG@-g______
DATE g@/99/@Z_____
COMPLETED BY J.M.
Colville TELEPHONE 56223[9[3225 h[
Z OPERATING STATUS 1.
Unit Name: Pglg_Vgrdg_Nuglggg_Ggngrgting_@tgtignt_Ugit_2 2.
Reporting Period: July _19@Z 3.
Licensed Thermal Power (MWt): @@gg l
4.
Nameplate Rating (Gross MWe): 149@
5.
Design Electrical Rating (Net MWe):
12Z9 6.
Maximum Dependable Capacity (Gross MWe): 1@g@
[
7.
Maximum Dependable Capacity (Net MWe):
1221 l
l 8.
If Changes Occur In Capacity Ratings (Items Nu.Ser 3 Through 7)
Since Last Report, Give Reasons:
9.
Power Level to Which Restricted, If Any (Net MWe):
_NgNE_________
10.
Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 11.
Houls in Reporting Period
___Z$3____
___QQ88____
___Z@@4___
12.
Number of Hours Reactor Was Critical
___Zi@.1__
___3@Z@.4__
___Q@@@.@_
13.
Reactor Reserve Shutdown Hours
_____g____
_____Q_____
_____g____
14.
Hours Generator On-Line
___Z11.2__
___@2@@.1__
___@@@g.1_
15.
Unit Reserve Shutdown Hours
_____g____
_____g_____
_____g____
16.
Gross Thermal Energy Generated (MWH) 2 G@Zt944.
11 439 42@.
19 ?@4t429 t
t 1
t 17.
Gross Electrical Energy Generated (MWH)
__9@@t999
_4399@t999
_@t9@@t1Zg 18.
Net Electrical Energy l
Generated (MWH)
__@ZZt@g1_
_@tZ@4t@@@.
_@t4@11224 19.
Unit Service Factor
___9@.@$__
___@4.1N___
___Z2.93__
20.
Unit Availability Factor
___9Q.@$__
___@4.13___
___Z2.93,_
21.
Unit Capacity Factor (Using MDC Net)
___9@.@3__
___@g.13___
___Zg.93__
22.
Unit Capacity Factor (Using DER Net) 92.9%
57.8%
67.3x 23.
Unit Forced Outage Rate
____4.43__
___19.@3___
___19.g3__
j 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration l
of Each):
I 25.
If Shutdown At End of Report Period, Estimated Date of Startup:
UnitA~I~n~Te$t 5tstuA~iPrio~~To CoAme~rcIAI~6~erStI~nII~~~~~~~~~~~~
~
~
~
~- ~
26.
r p
o Forecast Achieved INITIAL CRITICALITY 3/86 4/18/86 INITIAL ELECTRICITY
~~5755~~
~5726755~
COMMENCIAL OPERATION
(([2@@_~_~
~h2_Ih2@@~
5 s
AVERAGE DAILY UNIT POWER LEVEL 1
DOCKET NO.
50-529 ~~~~~~
UNIT PV G5-2
~~~~~
DATE 55759257 COMPLETED BY J.M.
Co - -
- - - - - - - _l v _i l _l e_
TELEPHONE 602-393-2679 MONTH:
Ju.l.X-1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
1 63 17 1 254 1 2 z--
2
x259 18 1 254 1
x----.-------------
t i
3
x259 19 ------- 1 54 1
1 2 r26.3.---------------
20 ------
1 46----------------
1 -.
1 2 4
5
z254 21 - - - - - - -.1. 1 5 0.- - - - - - - - - - - - - -
2--
1 6
r25.9 22 974 1 -- ---------------
7
---_1z254_-----------___---
23 --------_--_---_----------
0 8
1 50------
24 574 1 2 9
.1x254 25 -- ---- 1 50----------------
1 2 10 ------
z254------------------
26 -------
1-46--------------
1 1 2 11 L25.4.---------------
27 ------- z250 1
1 12 ------ 1 54 28 -----.-- 1 46 1 2 1 2 13 ------ x250 29 1 246 1
x-----------------
14 ------ 1250 30 1
z242.-----
1 ---
15 ----- - 12.4. 6------
31 ------- 1 46---------------
1 1 2 16 ------ L254------------
1
REFUELING INFORMATION 1
l l
i DOCKET NO.
50-529
~~ ~~
UNIT hh h53h~__[__
l DATE g@/99/@7_____
{
L COMPLETED BY J.M.
Colville 1
l TELEPHONE
-hgh35h5[hh}h[
l 4
1.
Scheduled date for next refueling shutdown.
j i
t 02/21/88 2.
Scheduled date for restart following refueling.
04/30/88 l
l 3.
Will refueling or resumption or operation thereafter require a l
Technical Specification change or other license amendment?
Not Yet Determined f
What will these be?
Not Yet Determined 4.
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, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Not Yet Determined 6.
The number of fuel assemblies, a)
In the core. ____241____
b)
In the spent fuel storage pool.
______g______
j 7.
Licensed spent fuel storage capacity. ___1329___
Intended change in spent fuel storage capacity.
___Noge___
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).
'e
)
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH l
DOCKET NO.
gg-Q2p_______
UNIT pVNG@-g______
DATE g@/99/@7_____
j COMPLETED BY J.M._ Coly 111e TELEPHONE ggg-@23-g@72_
July _1ggz 07/01 0000 Reactor Power 100%
07/22 1850 Unit 2 reactor tripped while a rapid plant shutdown was being performed due to a suspected steam generator tube 1
leak.
The condensate demineralizers were taken out of service incorrectly which resulted in a perturbation of l
condensate flow to the Main Feedwater pumps. The
{
perturbation was significant enough to cause low suction i
pressure trips on both Main Feedwater pumps.
The Control l
Room operator manually tripped the reactor due to the loss of the Main Feedwater pumps - Entered Mode 3.
)
I 7/23 2242 Reactor is critical - Entered Mode 2.
)
l l
7/24 0335 Synchronized Main Generator to Grid.
7/25 22O2 Reactor power at 100%.
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NRC MONTHLY OPERATINC REPORT
[
DOCKET'NC.
59-539_______
UNIT NAME PVNGS-@______
DATE 08/09_/87----- _------
COMPLETED BY J.M._Colville TELEPHONE
@gg-@9@-g@79_
OPERATING STATU_S 1.
Unit Name: Pglo_Vgrdg_Nuciggr_Gengrgting_Stgtiont_ Unit _@
2.
Reporting Period: July _19@Z 3.
Licensed Thermal Power (MWt): @@gg 4.
Nameplate Rating (Gross MWe): 149@
5.
Design Electrical Rating (Net MWe):
12Z9 6.
Maximum Dependable Capacity (Gross MWe): 1@g@
7.
Maximum Dependable Capacity (Net MWe):
aggi 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
9.
Power Level to Which-Restricted, If Any (Net MWe):
_NgNE_________
10.
Reasons For Restrictions, If Any:
l 1
This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
___Z44____
___@g2@____
___@g@@___
12.
Number of Hours Reactor Was Critical
_____Q____
_____Q_____
_____g____
13.
Reactor Reserve Shutdown Hours O
O
___-_o_____
14.
Hours Generator On-Line
_____g____
_____g_____
_____g____
15.
Unit Reserve Shutdown Hours O
o
_o____
16.
Gross Thermal Energy Generated (MWH)
_____g____
_____g_____
_____Q____
17.
Gross Electrical Energy Generated (MWH)
_____g____
_____g_____
_____g____
18.
Net Electrical Energy Generated (MWH)
_____g____
_____g_____
_____g__,_
19.
Unit Service Factor
_____g____
_____g_____
_____g____
20.
Unit Availability Factor
_____g____
_,.___g_____
_____g____
21.
Unit Capacity Factor (Using MDC Net)
O O
O 22.
Unit Capacity Factor (Using DER Net)
_____g____
_____g_____
_____g____
23.
Unit Forced Outage Rate
_____g____
_____g_____
_____g____
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shutdown At End of Report Period, Estimated Date of Startup:
Un1EA~I~~ Test 5tatuA~I5Eio$~To CES$~efbiAl 5p ritionii----~~~~~~~-
~
~
26.
n e
Forecast Achieved INITIAL CRITICALITY 07/8
_7_--
INITIAL ELECTRICITY 07/87 COMMERCIAL OPERATION
~55/89-~
--~~~~~~~
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-530 UNIT PVUG5__~3_-----
~~~~~~
DATE 08/09/87 COMPLETED BY J.M.
Colville
_3-2679------
TELEPHONE 602-39 MONT_H:
Jul
-- Y-1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
_0 17 0
2
--_-______0____-___-------
18 O
3 0
19 0
l 4
0 20 0
t 1
5 O
21 _--__----------- ---__---_
0 t
6 0
22 0
l 7
0 23 0
8 0
24 O
9 0
25 0
10 0
26 O
11 0
27..--_------ 0 12 ___------ 0 28 __--_----__O 13 0
29 0
14 0
30 0
15 0
31 0
16 -_---_--__O________________
I J
l 4
i l
-1 REFUELING INFORMATION j
DOCKET NO.
59-539_______
UNIT-pVNG@-3______
- DATE,
_g@/99/@Z_____
COMPLETED BY J M._Colv111e 3
TELEPHONE
@gg-393-2@Z9_
1.
Scheduled date for next refueling shutdown.
l' 02/25/89 2.
Scheduled date for restart following refueling.
05/05/89 3.
Will refueling or resumption or operation thereafter require a l
Technical Specification change or other license amendment?
Not Yet Determined l
What will these be?
Not Yet Determined 4.
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, unreviewed design or performance analyala methods, significant changes in fuel design, new operating procedures.
Not Yet Determined 6.
The number of fuel assemblies.
a)
In the core.
____241____
b)
In the spent fuel storage pool. ______g______
7.
Licensed spent fuel storago capacity.
___1339___
Intended change in spent fuel storage capacity.
___Ngge___
8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
J 2007 (18 Months reloads and full core discharge capability).
l
~
3UMMARY OF OPERATING' EXPERIENCE FOR THE~ MONTH l
j *.
.1 I
l I
DOCKET NO.
59 -539___ ____
UNIT EyNgg;g______
DATE gggggggZ_____
COMPLETED BY J.M._golville TELEPHONE gg2;@@g-2g22_
Jyly_1ggZ 07/01 0000 Unit in Mode S.
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{
- Arizona Nuclear Power Project P.O. BOX 52034.
- PHOENIX. ARIZONA 85072-2004
'192-00259-JGH/TRB August. 13, 1987 NRC Document Control Desk U.S. Nuclear Regulatory Commission.
. ashington, D.C.-
20555 l
W
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Docket Nos. STN 50-528 License Nos..NPF-41 STN 50-529 NPF-51 STN-50-530 NPF-65 July Monthly Operating Report File: 87-024-404
Dear Sirs:
Attached please find the July 1987, Monthly Operating iseports 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.
l If you have any questions, please contact me.
Very truly yours, r
Klh l i
J. G. Hay s i
Vice President Jj Nuclear Production JGH/TRB/cid i
.j cc:
- 0. M. DeMichele (all-w/a).
E. E. Van Brunt, Jr.
i J. B. Martin E. A. Licitra A. C. Gehr J. A. Amenta INFO Records Center
[l k\\-
i
-