ML20204B646
| ML20204B646 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 02/28/1987 |
| From: | Reavis J, Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8703250120 | |
| Download: ML20204B646 (16) | |
Text
.
Of(RAllNSDATA$[ FORT 00CEET 50 413 DATE 31387 (FIRAllNG$f4ILS COMfLtl[081 J.A.Reavit IEllFHON[
704/3737567
- 1. Cell Nmt CAIAWM i
- 2. Reporttag f orlod: FEM) arf l t917 fEMUA4f 26,1987 i
- 3. Licenied Ihere11 toeer Wt11 34ll 4.NattplateFatlng(6tellMWell 1303 l Notet #NaotplateRolleg I
5.teingn(lettitalfating(hetPWeli l145 I (Grott MWel calculated at i
6.PetitetDepenfableCaratity(6fontPWeli l 1450.000MVA
.90peser 1
- 7. Maileat Ctpf ahble Capacity (Ntt PWell l143 I fatter per Fa p lit, 1
8.IfCht*get0 Cur in Capacity Altir'p (ltest Nveter 3 lbreagh 71 lir:0last I h0R[6 0020.
I O f f ? f I
- O I ' t R e a t o ti t i,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
l.,,,,,,,,,,,,,,,,,,,,,,,,,,,,,l
- 9. Footr Level to Which Restricted, if Any INet MWell,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
- 10. Ac a i n f o r R e s t r i c t i e i t, i f s q l,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
ThisFonth fr..toCate Cueulative 11.H)ertlaReptrtingFtried 67F 0 1,416.0 14,641.0 ff. N,oter Of We,eactcr Was Critical 6R.)
1.El.0 10,339.4 r
it lentar ten n e livitern Hotre 0~
-0~
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- 14. Heir 1 Ge t at:r On-LL,e 659.9 1,297.3 9.950.0 '
1), tPit f everst $wthen Nvrt
~0.
0-
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- 16. Brett hertal (norgr Ot*erated 'FWHI f.fli.f81 4t04,957 N,777,17f'
- 17. Casi tiettrical (rtegy Crotra'ed Wo 711,4?S l.411.033 10,761,767 li, %t (tectrical (nergy Stetra'tJ I%il 7D,9t!
I,316,8 0 10.019,866
- 11. Utit fe'it:t futu 18.f 10.9 68.0 t ). #il A all,5tl6tr facter 9F.2 10.7 68.0 '
II, init Capull, F#ctor (Uttrg 10C Net) 96.2 06.2 St.8 f t. L' nit h;nity f a: tor Illing Ctl Nell 4.2 16.2 59.8
!). Urlt firces Datage itt 1.8 9.1 11.6 s
T4. INtfrait fthstuted Over Ntil 6 Pont>t (t pe. Oste, anJ Ourallen of f athu i
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f 3. I f 5%t C o nn A t I'd C f Rtrar t Fer iod, t it is at ed C a t e o f ll u t op s.,,,,,,,,,,,,,,,,,......................................
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(6. Unitt to felt Status irrier to Coesercial Ortrallenh forecast Achieved INIi!4L 01IlCAtIff IN!!!AL[llCIRlClff (Orl8CIAL UU4flM
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(7 AVERAGE CAILY UNil PcWER LEVEL i
t t
00Citi NO.
50-413 4
UNil Catambai i
OAft March 13,1987 COMPLitt0 J.A.Reavis ILLEPHONE 704 373 7567 i
r 4
l J
j RONTH filRUARY,1997 1
i OAV AVERAGEDAILYPOWERL(vil CAT AvtRAGE DAILY POWER Livil (MWE Net)
(MWE-Net)
- i I
106 17 1839 I
933 il 1843 l
3 1137 19 1145 4
lint 20 l144 4
i 5
litt il 1144 1
i
.I 6
1845 22 1145 1
7
!!44 23 1142 1
t 8
1145 24 114) t 4
,1 9
1844 25 1841 g
10 1844 26 1842 3
I 18 1147 27 lino 1
L It 1844 28 lint
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13 1145 14 1846 I
l$
!!46 I
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16 1145 i
j J
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-413__
UNIT NAME _CAIAWBA_1________
DATE _( 3 /13[B7_______
REPORT MONTH ___Fet2ruary_1982_
COMPLETED BY _GER% D_REAVIS____
TELEPHONE _(704)-373-7567__
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TINGl EVENT SYS-l CAUSE AND CORRECTIVE
- 0 0
l lP l DURATION O
DCHNI REPORT TEM ICOMPONENT ACTION TO 0
l DATE IE l HOURS lN IR/X l NO.
l CODE l CODE PREVENT RECURRENCE e
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i H
I 1
h3 I B7-2-01 lF l 12.07 lA l4 I IE l INSTRU l REACTOR TRIP DUE TO HIGH FLUX LOW 9
l l
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l POWER RANGE SETPOINT B
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I 9 9-p 87 1 iF l lF l HG XXXXXX POWER INCREASE DELAY DUE TO HOTWELL l
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IE INSTRU l POWER INCREASE DELAY DUE TO NUCLEAR I
9 l
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l l INSTRUMENTATION CALIBRATION (CHANNEL I I
l l
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l MISMATCH) l l
l l
1 1
I I
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- II-p l 87 2 1S I lB l-l HA l TURBIN l TURBINE TRIP TEST l
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I 3 I2-p l 87 2 lF I
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l lB l-l IE l INSTRU NUCLEAR INSTRUMEMTATION RECALIBRATION 1
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TO CORRECT POWER MISMATCH
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3 4
F Fcrced Reason:
Method:
Exhibit G - Instructions i S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l
B-Maintenance or test 2-Manual Scram Entry Sheets For License C-Refueling 3-Automatic Scram Event Report (LER) i l
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-Ol61) l E-Operator Training & License Examination i
F-Administrative 5
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain) l l
DOCKET NO:
50-413 UNIT:
Catawba 1 DATE:
03/13/87 NARRATIVE
SUMMARY
Month: February, 1987 Catawba Unit 1 began the month returning to service after an outage to correct a design deficiency on the Containment Air Return Fans, when the unit tripped due to a setpoint not being blocked. The unit was back on line that day. lo11owing several holds during the power escalation due to chemistry, testing, and instrument problems, the unit operated at 100% for the remainder of the month.
MONTHLY REFUELING INFORMATION REQUEST 1.
Facility name: Catawba, Unit 1 2.
Scheduled next refueling shutdown: October, 1987 3.
Scheduled restart following refueling: December, 1987 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, what will these be? Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.
Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7.
Number of fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 64 8.
Present licensed fuel pool capacity: 1418 Size of requested or planned increase: -
9.
Projected date of last refueling which can be accomanodated by present licensed capacity: August, 2008 i
DUKE POWER COMPANY DATE: March 13, 1987 Name of
Contact:
J. A. Reavis Phone:
704-373-7567
OFERATINS DATA FEFORT DOCKET 50-414 DATE 3-13-87 0FERATIN3 STATUS COMPLETED BY J. A. Reavis TELEPHONE 704/373-7567
- 1. Unit Nate: CATAWBA 2
- 2. Feporting Periods.FEBK'JARY 1,1987-FEERUARY 28,1987
- 2. Licensed Thereal Power (MWt):
3411
' 4. Nieeplate Rating (Gross MWe):
1305 i Note's
- Nameplate Rating I
- 5. Design Electrical Rating (Net MWe):. 1145 i (6rcss MWel calculated as 1
6; Maxinus Dependable Capacity (6ross MWe):
l 1450.000 MVA x.90 power I
- 7. Marieus Dependable Capacity (Net MWe):
!!45 I factor per Page 111, l
E. If Changes Occur in Capacity Ratings (Itess Number 3 Throagh 7) Since Last I NURE6-0020.
I Report. Give Reasons:
l l
90 Focer Level To L!hich Restricted, if Any (Net MWe):
_10. leascn for Eestrictions, If any..........
....= _
This Month Yr.-to-Date Cusulative
'11. Heurs la Esporting Feriod 672.0 1,416.0 4,657.0-
-12. Nusber Of Hocrs Reactor Was Critical 608.4 1,291.6 2,684.4 '
- 13. Kesctor Reserve Shetdown Hours
--0--
--0--
--0--
- 14. Hours Generater On-Line 574.9 1,241.3 2,567.0 -
- 15. Unit Reserve Shutdewn Hcurs
--0--
--0--
--0--
- 16. Eress Trercal Erergy Generated (MWH) 1,746,995 3,924,863 7,969,477
~17. Scoss Electrical Energy Generated (MWH) 602,950 1,365,550 2,788,692-
.18. Het Electrical Erargy 6ererated (MWH) 564,021 1,282,913 2,590,115
- 19. Unit Service Factor 85.6 87.7 55.1
- 20. Unit Availability Fa: tor 65.6 87.7 55.1 El. Urit Capacity Factor (Using MDC Net) 73.4 79.1 48.4
- 22. Unit C uacity Factor (Using DER Net) 73.4 79.1 48.4
- 23. Unit Forcrd Outage Rate 10.4 7.8 44.0
- 24. Shutjowns Scheduled 0<er Next 6 Months (Type, Date, ar.d Duration of Each):
......Np.o_e.............
- 25. If Shut Dan At End Of Report Period. Estisalid Date of Startup:....................._
- 26. Units in Test Status (Prior to Consercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C0ttHERCIAL OFERATION t'
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-414 UNIT Catawba 2 DATE March 13,1987 COMPLETED J. A. Reavis TELEPHONE 704-373-7567 MONTH FEBRUARY,1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)
(MWE-Net) 1 0
17 1118 2
164 18
!!25 3
697 19 1137 4
1115 20 823 5
1118 21 697 6
1116 22 1105 7
1113 23 1100 8
1096 24 649 9
1116 25 0
10
!!!9 26 0
11 1120 27 56 12 1102 28 494 13 1115 14 1124 15 1122 16
!!23 e
- - +
y e
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-414 UNIT NAME _CATAW@A_2________
PAGE 1 of 4 DATE _ggflgfg2______;__
REPORT MONTH ____ February _1
@2_
COMPLETED BY _ GERALD _REAVIS____
TELEPHONE _12941-@23-2562___
MET-R HOD E
OF T
A SHU-LICENSE N
Y S
TING EVENT SYS-CAUSE AND CORRECTIVE l
0 P
DURATION O
DOWN REPORT TEM COMPONENT ACTION TO DATE E
HOURS N
R/X NO.
CODE CODE PREVENT RECURRENCE 3
G7-2-01 S
30.20 A
4 CB HTEXCH REACTOR COOLANT DRAIN TANK HEAT EXCHANGER LEAK REPAIR 11-p 87 2 F
A HA INSTRU POWER INCREASE DELAY DUE TO TURBINE GENERATOR CONTROL PROBLEMS 12-p 87 3 S
B HA TURBIN POWER INCREASE DELAY DUE TO TURBINE TRIP TEST 13-p 87 3 F
HA INSTRU POWER INCREASE DELAY DUE TO POWER B
LOAD UNBALANCE CIRCUIT CALIBRATION 14-p 87 4 F
A HJ PUMPXX HEATER DRAIN PUMP '2C1' SEAL REPAIR (RX POWER AT 100%)
15-p 87 8 S
F 22 222222 POWER REDUCTION PER DISPATCHER REQUEST 1
2 3
4 F Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For License C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-Ol61)
E-Operator Training & License Examination F-Administrative 5
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-414 UNIT NAME _CATAWHA_?________
DATE ~03/13/87 PAGE 2 of 4 REPORT MONTH ____E @ tuaEy_12@2_
COMPLETED BY _hk5h(D[hhh55h(('_,[
TELEPHONE _12041-373-2567___
MET-R HOD E
OF T
A SHU-LICENSE N
Y S
TING EVENT SYS-CAUSE AND CORRRECTIVE i
O P
DURATION O
DOWN REPORT TEM COMPONENT ACTION TO DATE E
HOURS N
R/X.
NO.
CODE CODE PREVENT RECURRENCE 16-p 87 8 F
A HJ PUMPXX HEATER DRAIN PUMP '2C1' SEAL REPAIR (RX AT 100% POWER) 17-P 87-2-12 S
B HB VALVEX POWER REDUCTION DUE TO CONTROL VALVE MOVEMENT TEST 18-P 87-2-12 F
A HJ PUMPXX HEATER DRAIN PUMP '2C2' SEAL REPAIR (RX POWER AT 100%)
19-P 87-2-20 F
A HH VALVEX POWER REDUCTION DUE TO STEAM GENER-ATOR
'2D' FEEDWATER CONTROL VALVE REPAIR 20-P 87-2-21 F
F HG HTEXCH POWER INCREASE DELAY DUE TO STEAM GENERATOR SULFATE CHEMISTRY VERIFI-CATION I
21-P 87-2-21 F
H RC FUELXX POWER INCREASE DELAY DUE TO QUADRANT POWER TILT RATIO OUT OF SPEC 1
1 2
3 4
F Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For License C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-Ol61)
E-Operator Training & License Examination F-Administrative 5
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain)
- 'm UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-414 UNIT NAME _ CATAWBA _2________
DATE 03/13/87' l
PAGE 3 of 4 REPORT MONTH ____ February _1282_
COMPLETED BY [hhhhhh_hh55[h~_(([
TELEPHONE _12041-323-2562___
L.
MET-R HOD E
OF l
T A
SHU-LICENSE N
Y S
TING EVENT SYS-CAUSE AND CORRECTIVE O
P DURATION O
DOWN REPORT TEM COMPONENT ACTION TO DATE E
HOURS N
R/X NO.
CODE CODE PREVENT RECURRENCE 22-P 87-2-21 F
H RC FUELXX POWER INCREASE DELAY DUE TO QUADRANT POWER TILT RATIO OUT OF SPEC l
- l 23-p 87-2-22 F
H RC FUELXX POWER INCREASE DELAY DUE TO QUADRANT POWER TILT RATIO OUT OF SPEC.
24-P 87-2-23 S
B HA TURBIN POWER REDUCTION DUE TO TURBINE ACCEPTANCE TESTING 25-P 87-2-23 S
B HA TURBIN POWER INCREASE DELAY DUE TO TURBINE ACCEPTANCE TESTING 4
87-2-24 F
66.92 A
3 EC CKTBKR TURBINE AND REACTOR TRIP DUE TO LOSS OF 125 VOLT DC VITAL FEEDER BREAKER I
26-P 87-2-27 F
F CG HTEXCH POWER INCREASE DELAY DUE TO STEAM l
GENERATOR CAT CON LEVELS OUT OF SPEC a
1 2
3 4
F Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry. Sheets For License i
C-Refueling 3-Automatic Scram Event Report (LER) i D-Regulatory Restriction 4-Other (Explain)
File (NUREG-0161)
E-Operator Training & License Examination F-Administrative 5
G-Operator Error (Explain)
Exhibit-I - Same Source j
H-Other (Explain) i
ir i
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 414-
~
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U N I T ' N A M E _ C_ 5_ _T d W 5 5_ _' 5_ _
PAGE 4 of 4 DATE 03/13/Ta7 REPORT MONTH ____Egbruary_1282_
COMPLETED BY [hkhd(h_~hh5hih"~_~~_ __
. TELEPHONE _12041-323-2562___
4 MET-i
~~ n,* s y
999 ll E
OF T
A SHU-LICENSE 2
N Y'
S TING EVENT SYS-CAUSE AND CORRECTIVE i
O P
DURATION O
DOWN REPORT TEM COMPONENT ACTION TO DATE E
HOURS N
R/X NO.
CODE CODE PREVENT RECURRENCE 27-p 87-2-27 F
F CG HTEXCH POWER INCREASE DELAY DUE TO STEAM GENERATOR SULFITE-OUT OF SPEC l
28-p 87-2-28 F
A HA CKTBKR GENERATOR BREAKER
'B' TRIP, MOISTURE j
IN MOTOR OPERATED DISCONNECT CABINET 2S-p 87-2-28 F
A HA CKTBKR GENERATOR BREAKER
'B' TRIP i
i MOTOR OPERATED DISCONNECT ly 30-p 87-2-28 F
A HA CKTBKR GENERATOR BREAKER
'B' REPAIR it i
i i
i j
i
.i i 1 2
3 4
i F Forced Reason:
Method:
Exhibit G - Instructions l
S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For License C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-0161) l E-Operator Training & License Examination F-Administrative 5
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain) 1 1
i
DOCKET NO:
50-414 UNIT:
Catawba 2 DATE:
03/13/87 NARRATIVE SUMMAR" Month: February, 1987 Catawba Unit 2 began the month returning to service from an outage to repair its Reactor Coolant Drain Tank. The power increase was delayed by turbine control circuitry problems and testing. On 2/04 the unit's efficiency was reduced after its "2C1" Heater Drain Pump was removed from service for repairs. On 2/20 a power reduction to 25% was made so that the "D" Steam Generator Feedwater Regulating valve could be repaired. During the power increase following repairs, several holds were encountered due to chemistry and core power distribution limits. Power was reduced from 100% on 2/23 for Turbine Acceptance testing. The unit tripped off line on 2/24 after a breaker was inadvertently-The unit was back in opened that interrupted vital instrumentation power.
service on 2/27 but had several holds in its power increase due to chemistry restrictions. On 2/28 a runback occurred while the unit was increasing power towards 100%. Micro switches in the "B" generator breaker Motor Operated Disconnect had malfunctioned and the unit remained at approximately 50% power through the end of the month.
i l
i.
i lt
~
CORRECTED COPY DOCKET NO: 50-414 UNIT: Catawba 2 DATE: 02-16-87 NARRATIVE
SUMMARY
Month: January, 1987 Catawba Unit 2 began the month at 100% power, but on January 6 power was reduced to 88% to remove a Heater Drain pump from service. Plux mapping was also performed which required the unit to maintain 88% power until January 9.
On January 10, the unit reduced power from 100% to 17% to repair a Steam Generator Feedwater regulating valve.
The valve repairs were completed the same day and the unit began to increase power. A hold was necessary at 82% power due to Power Tilt limits in the core. The unit was back at 100% on January 12.
The unit reduced power to 85%
on January 15 to remove a Heater Drain pump from service, but was able to return to 100% on January 16 at reduced megawatt output (1066 MWe) due to the loss of the Heater Drain pump. On January 28, the unit tripped after a Steam Generator Feedwater regulating valve failed closed. The unit returned to service on January 29, but the turbine tripped on January 30 due to high Moisture Separator Reheater levels. The unit remained off line for the remainder of the month.
4 4
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--.-_,.m-,...,n.-,,,,--
,-w,,w,-e r,-mm--mm p.
--,e-,
--v-,-
MONTHLY REFUELING INFORMATION REQUEST 1.
Facility name: Catawba, Unit 2 2.
Scheduled next refueling shutdown: December, 1987 3.
Scheduled restart following refueling: March, 1988 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, what will these be?
Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.
Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
t 7.
Number of fuel assemblies (a) in the core:
193 i
(b) in the spent fuel pool: 8.
Present licensed fuel pool capacity:
1418 Size of requested or planned increase:
9.
Projected date of last refueling which can be accommodated by present licensed capacity: August, 2008 J
DUKE POWER COMPANY DATE: March 13, 1987 Name of
Contact:
J. A. Reavis Phone:
704-373-7567 i
~ -,
r..
-e.,
,-,-..-e-,..-..n._-
-r----
s m
CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT 1.
Personnel Exposure For the month of January, no individual exceeded 10 percent of their allowable annual radiation dose limit.
2.
The total station liquid release for January has been compared with the Technical Specifications maximum annual dose conunitment and was less than 10 percent of this limit.
The total station gaseous release for January has been compared with the Technical Specifications maximum annual dose conunitment and was less than 10 percent of this limit.
l
-o DUKE POWER GOMPANY P.O. DOX 33180 CHAML0frTE, N.C. 28942
' HAL H. TUCKER Tzt.mpssows vue enseman (704) 373-4531 m aman emos m ion March 13, 1987 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
20555 Re: Catawba Nuclear Station
~
Docket No. 50-413 and 50-414
Dear Sir:
Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the month of February, 1987. Also attached is a corrected copy of the Catawba Unit 2 Narrative Summary.
Very truly yours, Q 44 f
Hal B. Tucker JAR /03/sbn l
Attachment xc:
Dr. J. Nelson Grace, Regional Administrator INPO Records Center U. S. Nuclear Regulatory Commission Suite 1500 Region II 1100 Circle 75 Parkway 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Atlanta, Georgia 30323 Mr. Richard G. Oehl, NE-44 Mr. Phil Ross U. S. Department of Energy U. S. Nuclear Regulatory Commission 19901 Germantown Road MNBB-5715 Germantown, Maryland 20874 Washington, D. C.
20555 American Nuclear Insurers Dr. K. Jabbour, Project Manager c/o Dottie Sherman, ANI Library Office of Nuclear Reactor Regulation The Exchange, Suite 245 U. S. Nuclear Regulatory Commission 270 Farmington Avenue Washington, D. C.
20555 Farmington, CT 06032 i
NRC Resident Inspector hj, l
Catawba Nuclear Station i
L