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NRC MONTHLY OPERATING REPORT DOCKET NO. 5_Q_5_29_ | |||
UNIT NAME PyN93-g DATE 06/05/#5 COMPLETED BY L b _Elull TELEPHONE b@g-2]E-D)99 Ey t . 6393 9P_EROJJ119_S_TRLU) 1.- Unit Name s P_gl o _V_e_t d .e _N_u_cl e_at_Qgnenat_i ng _S_t_at i_onu_U_ni t__2 | |||
: 2. Report ing Period: M_a_y__,1_9_q6_ | |||
: 3. Licensed Thermal Power (MWt): JD99 | |||
: 4. Nameplate Rating (Gross MWe): J393 | |||
: 5. Design Electrical Rating (Net MWe): _ | |||
Jggj | |||
: 6. Maximum Dependable Capacity (Gross MWe): Tg_D3_Agigrsfrg# | |||
: 7. Maximum Dependable Capacity (Net MWe): Tp_pe_dytgrmfrgd | |||
: 8. If Changes Occur In Capacity Rat ings (It ems Number 3 Through 7) | |||
Since Last Re port, Give Reasons _ _ _ _ ___ _ | |||
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - ___._____ __ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - | |||
: 9. Power Level to Which Restricted, If Any (Net MWe): _N_QN_E_ _ | |||
: 10. Reasons For Rest ri ct ions, If Any _ _ _ , _ _ _ , _ _ _ _ _ _ _ | |||
This Month Yr.-to-Date Cumulative | |||
: 11. Hours-in Reporting Period _ _ 733____, _, __Jg3Jzg5__ _3JD92 35__ | |||
: 12. Number of Hours Reactor Was Critical __321._8_ _ _ _, _ __42 6 ._Z ___ __ig6 _7 ,_ | |||
: 13. Reactor Reservu Shutdown Hours _____0____ _ _, _ _ _q - __ __ Q____ | |||
: 14. Hours Generat or On-Line 193.1 193.1 193.1 | |||
: 15. Unit Reserve Shutdown Hours _____Q____, _, _ _ _ _0 _ , _ | |||
_____0__,,_ | |||
: 16. Gross Thermal Energy Generated (MWH) _L7_8 u45_8__ _ L18_u_5_8_ 4 _ __ _178_u(58_,_ | |||
: 17. Gross Electrical Energy Geneeated (MWH) __30._800__ __30 t_00___ 8 _ _ 3 0 ,_8 0 0_ ,_ | |||
: 16. Net Electrical Energy Generated (MWH) _ _ _Quq5_Z_ _ _ _,_,i,_Q5_7_ _,_ __,_tuS5_Z__ | |||
: 19. Unit Service Factor __ __tf(@ __,_ _ _ __N_(@ __, __ __ __N_L@ __ _ | |||
: 20. Unit Availability Factor ____N_(@___ N/A N/A | |||
: 21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A | |||
: 22. Unit Capacity Factor (Using DER Net) ____N(@___ _ _ _ _N (@ _ ___ __ __N_L@ __, _ | |||
: 23. Unit Forced Outage Rate __ _ _N_(@ __ _ _ _ _ _N_(@ _ _ _ _ N (@___, | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): _Ng_ s1.goj.tjgyph_gy$g.gg_gl arDgp_yp%jj_3 fhgr wStrgDh.y_ryr_ | |||
: 25. If Shutdown At End of Report Period, Estimat ed Date of Startups | |||
____t!L9_____________________________ - ___ _ _ _ _ _ _ _ __ -------- = | |||
: 26. Units in Test St at us (Prior To Commercial Operat ion) : | |||
Forecast Achieved INITIAL CRITICALITY __3/85__ _3/jg/js_ | |||
INITIAL ELECTRICITY __&f85__ _5fggf_86_ | |||
COMMERCIAL OPERATION _jjfpb__ _ _ _ _ , _ _ _ _ , _ | |||
8608100179 860531 PDR ADOCK 05000529 MM R PDR lh | |||
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __QQ-52%_ _ _ _ _ | |||
UNIT _ _ _ __P_V_N_GS_ _2_ -- | |||
DATE ___ _06LO_6_L86 _ _ _ _ _ | |||
COMPLETED BY J_._k _idull,______ | |||
* TELEPHONE ___6_0g_9_32_ .q3qe _ | |||
__ Ku.t.__65_%__ . _ | |||
O ttONTil May 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 _ __ | |||
0 = _____-__ 17 _-- .- 0 _ | |||
2 ___________0____--- = | |||
18 -0 - -- | |||
3 ___________g_- _ 19 _ __ __ _ - e_ __ | |||
4 ____ --- 9 -- - - - - - = 2 0 _ _ _ __ - - - - - - O_----- | |||
5 ___________0 - _ - - - _____ 21 ___ -122 6 ___ - 0_ = = = - --- 22 13e 7 ___________0- - - --=____ 2 3 _ _ _ __ __ _ _ _ _1_2_8_ __ =___ | |||
B _ _ _ _ _ _ _ - _ 0- -- | |||
24 -- 122-- __ | |||
9 _ _ _ _ _ _ _ _ _ 0______ - 25 - - | |||
0 10 _ =_____g______ ______ | |||
26 _____________g____-_ - | |||
=_- | |||
11___. - _ _ _ _0 ==__- --___ | |||
27 --_________0 - | |||
12 ___________0__ _. 28 _ - - - - - - _ 0 ______ | |||
13 =- - - _ - _8 _.____ 29 __--- -- __ __1_8. _ - __ | |||
14 _ _ _ _ _ _ _ g______ =_ 3 0 _ __ _ _ - | |||
. 183_= __ | |||
15 ______0___________ 31 _= --_ 9_4_ _ _ _ _ _ _ _ | |||
16 ___________e- ---- | |||
1 REFUELING INFORMATION DOCKET NO. Q0_ _q29 _ _ _ _ | |||
UNIT. Pyt199-g______ | |||
DATE _06/_05/35 COMPLETED BY- Jzl.2_11uj_1 TELEPHONE #0g-932--jg_00_ | |||
EE.tz bD23 | |||
: 1. Sched ul ed date for next refueling shutdown. | |||
01/02/88 | |||
: 2. Scheduled date for restart following refueling. | |||
02/20/89 | |||
: 3. Wi ll refueling or resumpt ion or operation thereaf ter require a . | |||
Technical Specification change or other li cense amendment ? . | |||
Not Yet Det errained Wh at will these be? | |||
Not Yet Determined | |||
: 4. Scheduled date for submitting proposed licensing action and supporting information. | |||
Not Yet Deterrained | |||
: 5. Important Licensing considerat ions associated with refueling, | |||
: e. g. new or di fferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures. | |||
Not (et betermined | |||
: 6. The number of fuel assemblies, a) In the core. ____241____ | |||
s b) In the spent fuel st orage pool. _= _0 __ ._ | |||
: 7. Licensed spent fuel storage capacity. ___J329___ | |||
Intend ed change in spent fuel storage capacity. __ _ blorst_ _ | |||
: 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity. | |||
2003 (w/ annual reloads and full core discharge capability). | |||
__ .~ | |||
-r' tok t))N 'SUM MARY OF OPERATING EXPERIENCE FOR THE MONTH Tl2.0 - d, 3 /24:[ S/ N ' l ~l' 5 J,L 4,p Tj% / - 24t - | |||
/298 DOCKET NO. 50-529_______ | |||
,g - f[' A 7 ~~ M' f p, ) UNIT pVNGS-2 f,/;.(f- AY/ | |||
^- ' ,%# | |||
* J[.1 L ' ~ DATE Osf_0_6[86 f/ . 6 - Ab 2 | |||
~ | |||
,,1 Y . / g _ pff j COMPLETED BY TELEPHONE | |||
.J2b2_itul 1 502-932-}3.00_ | |||
ff a ./ w E_!@2_by93 | |||
((3Q " Z f | |||
: g. y . ,2 4-3 j'h4 - 3, 2., Tl 3 l ~ | |||
05/01 0000 Plant in Mode 5 due to BOP /ESFAS d iscrepancies 05/14 0333 Unit entered Mode 4 05/14 1326 Unit ent ered Moce 3 05/16 1825 Unit 2 reactor declared critical - entered Mode 2 _,_ | |||
f' 'j o 05/18 2157 Ent ered Mode 1 - reactor power at 10% [jg-- d; M 05/20 1742 Synchronized Main Turbine with Grid [l20 ~ ll ' f2-05/26 0313 React or trip on low level in #1 Steam Generator N' # | |||
Entered Mode 3 g j,ey 05/26 0630 Reactor critical - Mode 2 hf 05/26 1303 Entered Mode 1 I[3 / -I J N 1 05/26 1706 Synchronized Main Turbine with Grid, reactor power at 13% | |||
05/27 0123 Stabilized reactor power at 1.0% after entering Mode 2 d ue to a leak on the condenser hotwell level drawoff | |||
; bypass valve. | |||
05/29 0250 Entered Mode 1 05/29 0520 Synchronized Main Generator to Grid 05/31 1332 Reactor trip on high pressurizer pressure | |||
_ [j_ :,,"l Qll"b!/'i f$ ' | |||
f.i2c ) - | |||
$1E .T!] ' ' -),2,h l Sh- l ~ - : J 57 u - 14. | |||
i yl'>::-:-l 9 34 - z.1, fly p -75 glso r; ;n - ; ' ' | |||
gj 3 I - t .qif | |||
~ ~~ | |||
jy[-;- | |||
f 7/ P S ~ 13 ~ )' f;y ; g.< | |||
w c. , - - _ . | |||
'''' UNIT SHUTDOWHS AND POWER ACDUCil0NS . | |||
COCKET N?. Jn-97 '*: | |||
' UNIT NANC PWM*S 2 . | |||
4 i DATE 6-10-E6 . | |||
* COMPLETED DY _ . . . | |||
TELErit0NC ~ 9 D-5 W | |||
* P. (A 01 Hethod or | |||
* Shutting | |||
* Down System Component Cause & Cerrective 1 Du ra t ion 2 | |||
* 3 1.ER r4 5 Actinn to No. Date Type (stours) Reason Roactor fio . Codo Code Prevent Becurrence 5-1-86 3f8.5 A . 4 N/A , | |||
Plant in dode 5 due to BOP /ESFAS | |||
* discrepancies.. | |||
.27.2 2-86-025- DJ N/A* Reactor. trip slue to low SG level. | |||
1 5-25-86 F G 3 2 5-31-86 F 10.5 A 3 2-86-G27 EL ' 51' High pressurizec press,ure'. | |||
Negativo sequence trip on the | |||
- main generator csused a turbine | |||
* trip. Turbine bypass valves did,not quick open resulting in reactor trip on high pressurizer pressure. | |||
k | |||
_e 1 2 3 h T-forced Rensnn: Hethod: Exhibit F = Instructions S-Schodufed A-Eauipment ralluro (Explain) 1-Hanual for rrnparation or oatn 0-tra intenance or Test 2-Hanunt Sernm. Ent ry Sheet s for Licensoo - | |||
C-Itc ruc t i ng 3-Automa tic Scram, tvent Report (LER) File . | |||
D-negulatory Restriction 14-Continua t ion f rom- (HUREc 0161) | |||
E-onnrator Tra ininD & l.icense Examination rrnvious Honth | |||
* T- Admi n i s t ra t ivo | |||
* 5-neduction or 20% 5 c-oporational Error (Explain) . , * | |||
* or creator in tno Exhibit H-Some Source II-Other (Explain) ' | |||
Past 2fs flours o n e, n.. * , | |||
: i. 9-Othe r ( Expla in) | |||
k* | |||
f Arizona Nuclear Power Project | |||
* f) | |||
P.o. Box 52034 e PHOENIX, ARIZONA 85072-2014 June 13, 1986 ANPP-36931-EEVB/PGN/98.05 Mr. Ronald M. Scro8 gins, Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 | |||
==Subject:== | |||
Palo Verde Nuclear Generating Station (PVNGS) | |||
Unit 2 Docket No. STN 50-529 (License NPF-51) | |||
May Monthly Operating Report File: 86-024-404 | |||
==Dear Mr. Scroggins:== | |||
Attached please find the May, 1986, Monthly Operating Report prepared and sub-mitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the Palo Verde Nuclear Generating Station, Unit 2 Operating License. By copy of this letter we are also forwarding a copy of the Monthly Operating Report to the Regional Administrator of the Region V office. | |||
If you have any questions, please contact me. | |||
Very truly yours, bA A i E. E. Van Brunt, Jr. | |||
Executive Vice President Project Director EEVB/PGN/rw Attachment cc: J. B. Martin (all w/a) | |||
R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center v | |||
h i i( | |||
- >}} |
Latest revision as of 00:52, 30 December 2020
ML20205D804 | |
Person / Time | |
---|---|
Site: | Palo Verde |
Issue date: | 05/31/1986 |
From: | Hull J, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
References | |
ANPP-36931-EEVB, NUDOCS 8608180179 | |
Download: ML20205D804 (6) | |
Text
_
NRC MONTHLY OPERATING REPORT DOCKET NO. 5_Q_5_29_
UNIT NAME PyN93-g DATE 06/05/#5 COMPLETED BY L b _Elull TELEPHONE b@g-2]E-D)99 Ey t . 6393 9P_EROJJ119_S_TRLU) 1.- Unit Name s P_gl o _V_e_t d .e _N_u_cl e_at_Qgnenat_i ng _S_t_at i_onu_U_ni t__2
- 2. Report ing Period: M_a_y__,1_9_q6_
- 3. Licensed Thermal Power (MWt): JD99
- 4. Nameplate Rating (Gross MWe): J393
- 5. Design Electrical Rating (Net MWe): _
Jggj
- 6. Maximum Dependable Capacity (Gross MWe): Tg_D3_Agigrsfrg#
- 7. Maximum Dependable Capacity (Net MWe): Tp_pe_dytgrmfrgd
- 8. If Changes Occur In Capacity Rat ings (It ems Number 3 Through 7)
Since Last Re port, Give Reasons _ _ _ _ ___ _
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - ___._____ __ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -
- 9. Power Level to Which Restricted, If Any (Net MWe): _N_QN_E_ _
- 10. Reasons For Rest ri ct ions, If Any _ _ _ , _ _ _ , _ _ _ _ _ _ _
This Month Yr.-to-Date Cumulative
- 11. Hours-in Reporting Period _ _ 733____, _, __Jg3Jzg5__ _3JD92 35__
- 12. Number of Hours Reactor Was Critical __321._8_ _ _ _, _ __42 6 ._Z ___ __ig6 _7 ,_
- 13. Reactor Reservu Shutdown Hours _____0____ _ _, _ _ _q - __ __ Q____
- 14. Hours Generat or On-Line 193.1 193.1 193.1
- 15. Unit Reserve Shutdown Hours _____Q____, _, _ _ _ _0 _ , _
_____0__,,_
- 16. Gross Thermal Energy Generated (MWH) _L7_8 u45_8__ _ L18_u_5_8_ 4 _ __ _178_u(58_,_
- 17. Gross Electrical Energy Geneeated (MWH) __30._800__ __30 t_00___ 8 _ _ 3 0 ,_8 0 0_ ,_
- 16. Net Electrical Energy Generated (MWH) _ _ _Quq5_Z_ _ _ _,_,i,_Q5_7_ _,_ __,_tuS5_Z__
- 19. Unit Service Factor __ __tf(@ __,_ _ _ __N_(@ __, __ __ __N_L@ __ _
- 20. Unit Availability Factor ____N_(@___ N/A N/A
- 21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A
- 22. Unit Capacity Factor (Using DER Net) ____N(@___ _ _ _ _N (@ _ ___ __ __N_L@ __, _
- 23. Unit Forced Outage Rate __ _ _N_(@ __ _ _ _ _ _N_(@ _ _ _ _ N (@___,
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): _Ng_ s1.goj.tjgyph_gy$g.gg_gl arDgp_yp%jj_3 fhgr wStrgDh.y_ryr_
- 25. If Shutdown At End of Report Period, Estimat ed Date of Startups
____t!L9_____________________________ - ___ _ _ _ _ _ _ _ __ -------- =
- 26. Units in Test St at us (Prior To Commercial Operat ion) :
Forecast Achieved INITIAL CRITICALITY __3/85__ _3/jg/js_
INITIAL ELECTRICITY __&f85__ _5fggf_86_
COMMERCIAL OPERATION _jjfpb__ _ _ _ _ , _ _ _ _ , _
8608100179 860531 PDR ADOCK 05000529 MM R PDR lh
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __QQ-52%_ _ _ _ _
UNIT _ _ _ __P_V_N_GS_ _2_ --
DATE ___ _06LO_6_L86 _ _ _ _ _
COMPLETED BY J_._k _idull,______
- TELEPHONE ___6_0g_9_32_ .q3qe _
__ Ku.t.__65_%__ . _
O ttONTil May 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 _ __
0 = _____-__ 17 _-- .- 0 _
2 ___________0____--- =
18 -0 - --
3 ___________g_- _ 19 _ __ __ _ - e_ __
4 ____ --- 9 -- - - - - - = 2 0 _ _ _ __ - - - - - - O_-----
5 ___________0 - _ - - - _____ 21 ___ -122 6 ___ - 0_ = = = - --- 22 13e 7 ___________0- - - --=____ 2 3 _ _ _ __ __ _ _ _ _1_2_8_ __ =___
B _ _ _ _ _ _ _ - _ 0- --
24 -- 122-- __
9 _ _ _ _ _ _ _ _ _ 0______ - 25 - -
0 10 _ =_____g______ ______
26 _____________g____-_ -
=_-
11___. - _ _ _ _0 ==__- --___
27 --_________0 -
12 ___________0__ _. 28 _ - - - - - - _ 0 ______
13 =- - - _ - _8 _.____ 29 __--- -- __ __1_8. _ - __
14 _ _ _ _ _ _ _ g______ =_ 3 0 _ __ _ _ -
. 183_= __
15 ______0___________ 31 _= --_ 9_4_ _ _ _ _ _ _ _
16 ___________e- ----
1 REFUELING INFORMATION DOCKET NO. Q0_ _q29 _ _ _ _
UNIT. Pyt199-g______
DATE _06/_05/35 COMPLETED BY- Jzl.2_11uj_1 TELEPHONE #0g-932--jg_00_
EE.tz bD23
- 1. Sched ul ed date for next refueling shutdown.
01/02/88
- 2. Scheduled date for restart following refueling.
02/20/89
- 3. Wi ll refueling or resumpt ion or operation thereaf ter require a .
Technical Specification change or other li cense amendment ? .
Not Yet Det errained Wh at will these be?
Not Yet Determined
- 4. Scheduled date for submitting proposed licensing action and supporting information.
Not Yet Deterrained
- 5. Important Licensing considerat ions associated with refueling,
- e. g. new or di fferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Not (et betermined
- 6. The number of fuel assemblies, a) In the core. ____241____
s b) In the spent fuel st orage pool. _= _0 __ ._
- 7. Licensed spent fuel storage capacity. ___J329___
Intend ed change in spent fuel storage capacity. __ _ blorst_ _
- 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2003 (w/ annual reloads and full core discharge capability).
__ .~
-r' tok t))N 'SUM MARY OF OPERATING EXPERIENCE FOR THE MONTH Tl2.0 - d, 3 /24:[ S/ N ' l ~l' 5 J,L 4,p Tj% / - 24t -
/298 DOCKET NO. 50-529_______
,g - f[' A 7 ~~ M' f p, ) UNIT pVNGS-2 f,/;.(f- AY/
^- ' ,%#
- J[.1 L ' ~ DATE Osf_0_6[86 f/ . 6 - Ab 2
~
,,1 Y . / g _ pff j COMPLETED BY TELEPHONE
.J2b2_itul 1 502-932-}3.00_
ff a ./ w E_!@2_by93
((3Q " Z f
- g. y . ,2 4-3 j'h4 - 3, 2., Tl 3 l ~
05/01 0000 Plant in Mode 5 due to BOP /ESFAS d iscrepancies 05/14 0333 Unit entered Mode 4 05/14 1326 Unit ent ered Moce 3 05/16 1825 Unit 2 reactor declared critical - entered Mode 2 _,_
f' 'j o 05/18 2157 Ent ered Mode 1 - reactor power at 10% [jg-- d; M 05/20 1742 Synchronized Main Turbine with Grid [l20 ~ ll ' f2-05/26 0313 React or trip on low level in #1 Steam Generator N' #
Entered Mode 3 g j,ey 05/26 0630 Reactor critical - Mode 2 hf 05/26 1303 Entered Mode 1 I[3 / -I J N 1 05/26 1706 Synchronized Main Turbine with Grid, reactor power at 13%
05/27 0123 Stabilized reactor power at 1.0% after entering Mode 2 d ue to a leak on the condenser hotwell level drawoff
- bypass valve.
05/29 0250 Entered Mode 1 05/29 0520 Synchronized Main Generator to Grid 05/31 1332 Reactor trip on high pressurizer pressure
_ [j_ :,,"l Qll"b!/'i f$ '
f.i2c ) -
$1E .T!] ' ' -),2,h l Sh- l ~ - : J 57 u - 14.
i yl'>::-:-l 9 34 - z.1, fly p -75 glso r; ;n - ; ' '
gj 3 I - t .qif
~ ~~
jy[-;-
f 7/ P S ~ 13 ~ )' f;y ; g.<
w c. , - - _ .
' UNIT SHUTDOWHS AND POWER ACDUCil0NS .
COCKET N?. Jn-97 '*:
' UNIT NANC PWM*S 2 .
4 i DATE 6-10-E6 .
- COMPLETED DY _ . . .
TELErit0NC ~ 9 D-5 W
- P. (A 01 Hethod or
- Shutting
- Down System Component Cause & Cerrective 1 Du ra t ion 2
- 3 1.ER r4 5 Actinn to No. Date Type (stours) Reason Roactor fio . Codo Code Prevent Becurrence 5-1-86 3f8.5 A . 4 N/A ,
Plant in dode 5 due to BOP /ESFAS
- discrepancies..
.27.2 2-86-025- DJ N/A* Reactor. trip slue to low SG level.
1 5-25-86 F G 3 2 5-31-86 F 10.5 A 3 2-86-G27 EL ' 51' High pressurizec press,ure'.
Negativo sequence trip on the
- main generator csused a turbine
- trip. Turbine bypass valves did,not quick open resulting in reactor trip on high pressurizer pressure.
k
_e 1 2 3 h T-forced Rensnn: Hethod: Exhibit F = Instructions S-Schodufed A-Eauipment ralluro (Explain) 1-Hanual for rrnparation or oatn 0-tra intenance or Test 2-Hanunt Sernm. Ent ry Sheet s for Licensoo -
C-Itc ruc t i ng 3-Automa tic Scram, tvent Report (LER) File .
D-negulatory Restriction 14-Continua t ion f rom- (HUREc 0161)
E-onnrator Tra ininD & l.icense Examination rrnvious Honth
- T- Admi n i s t ra t ivo
- 5-neduction or 20% 5 c-oporational Error (Explain) . , *
- or creator in tno Exhibit H-Some Source II-Other (Explain) '
Past 2fs flours o n e, n.. * ,
- i. 9-Othe r ( Expla in)
k*
f Arizona Nuclear Power Project
- f)
P.o. Box 52034 e PHOENIX, ARIZONA 85072-2014 June 13, 1986 ANPP-36931-EEVB/PGN/98.05 Mr. Ronald M. Scro8 gins, Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No. STN 50-529 (License NPF-51)
May Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the May, 1986, Monthly Operating Report prepared and sub-mitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the Palo Verde Nuclear Generating Station, Unit 2 Operating License. By copy of this letter we are also forwarding a copy of the Monthly Operating Report to the Regional Administrator of the Region V office.
If you have any questions, please contact me.
Very truly yours, bA A i E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/PGN/rw Attachment cc: J. B. Martin (all w/a)
R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center v
h i i(
- >