ML20235Y198
| ML20235Y198 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/30/1987 |
| From: | Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8710200251 | |
| Download: ML20235Y198 (24) | |
Text
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. sf l. e TENNESSEE VALLEY AUTHORITY
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OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT i
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.j MONTHLY OPERATING REPORT TO NRC SEPTEMBER 1, 1987 - SEPTEMBER 30, 1987 DOCKET NUMBERS 50-259, 50-260 AND 50-296 LICENSE NUMBERS DPR-33. DPR-52, AND DPR l Submitted by:
/
lant Manager 1
0487k B710200251 870930 ADOCKOSOOpP]9-DR J
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CONTENTS v
- Operations. Sununary.
i Refueling Information.
3 Significant Operational Events.
5 Operating Data Report.
6
-Average Daily Unit Power Level...
9 I
Unit Shutdowns and Power Reductions.
12.
- i 15 I
Revision August 16 I
Revision July.
..l.
Revision June' 17 Revision May 18 Revision April.-.
19 Revision March...................
20 Revision February-21
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'P Operations Summary SEPTEMBER'1987-The following. summary. describes theJaignificant operation activities during' the reporting' period. -In support'of this; summary, a chronological los of' significant events is. included in this report..
There were eight reportable occurrences and four revisions to previous
' occurrences reported to NRC during the month.
. Unit'1
<The unit remained'on administrative hold the ent' ire month. The unit is also undergoing its end-of-cycle'6' refueling.',
Unit 2
.The unit remained on' administrative hold the entire month. The unit is also undergning its end-of-cycle 5 refueling.
' Unit 3 The' unit remained on administrative hold.the entire month. The unit is also undergoing environmental qualifications to comply with NRC requirements.
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1 L_._._--________.-__
l Operations Summary (Continued)
SEPTEMBER 1987 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
l Location Usage Factor 1
Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 Closure studs 0.24204 O.17629 0.14360 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.b(3) reporting requirements.
Common System Approximately 5.02E+05 gallons of waste liquids were discharged containing approximately 2.12E-02 curies of activity.
2
i t'
Refueling Information SEPTEMBER 1987 Unit __1 -
. Unit I was placed on administrative hold in March 1985 to resolve TVA and NRC concerns.
The unit also began its sixth refueling on June 1, 1985, with a i
scheduled restart date to be" determined. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 1 items are environmental qualification of electrical equipment (10CFR50.49), torus modification (NUREG 0661), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J), HpCI concerns, modification of PCIS logic (LER 259/85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), RpS modifications (IE Notice 78-45). H O sample 2
line modification (LER 81050), radiation monitors modification (LER 80033), EECW carbon to stainless pipe change out, and all NRC commitment items except i
Anticipated Transients Without Scram (ATWS) modifications which are scheduled for next outage.
I There'are 0 assemblies in the reactor vessel.
The spent fuel storage pool l
presently contains 284 new assemblies, 764 E00-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The prescnt available capacity of the fuel pool is 1355 locations.
Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined.
On September 3, 1985, the unit was placed on administrative hold to resolve TVA and NRC safety concerns. The
.fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 2 items are CRD SDIV piping modification (TEB 80-17),
environmental qualification of electrical equipment (10CFR50.49), torus modifications (NUREG 0661), containment modification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial), MSIV modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J) (partial), D/G speed sensor 3
I Refueling Information SEPTEMBER 1987
- Unit 2 (Continued) installation-(LER 81004), HpCI and RCIC testable check valve change out, modification of PCIS logic (LER 259/85009), HpCI concerns, seismic program review, and EECW carbon to s~tainless pipe change out.
There are 0 assemblies in'the reactor vessel. At month end there were 304 new assemblies, 764 EOC-5, 248 EOC-4, 352 E00-3, 156 EOC-2, and 132 EOC-1
- assemblies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 1481 locations. All HDRs have been installed in the pool with the exception of two.
Unit 3-Unit 3 was shut down on March 9, 1985, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date to be determined. The sixth refueling outage has been scheduled for September 21, 1988, and involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications.
The prior-to-startup unit 3 items are environmental qualifica-tion of electrical equipment (10CFR50.49), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifica-tions, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), addition of redundant drywell control air supply, RpS modification (IE.Rotice 78-45),
H0 Sample line modification (LER 81050), radiation monitor modification 22 (LER 80033), replacement of jet pump holddown beam assemblies (IEB 80-07),
change out of switches in SBGT (LER 83018). EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.
There are 0 assemblien in the reactor vessel.
There are 764 assemblies to finish cycle 6, 248 EOC-5, 280 EOC-4, 124 EOC-3, 144 EOC-2, and 208 EOC-1 l
l assemblien in the spent fuci storage pool.
The present available capacity of l
the fuel pool is 585 locations.
All high density racks (HDR) have been installed in the pool with the exception ot six.
i 4
L___
_.___.___m.m..__._.___m.
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l lD Signifi. cant _0herational Events
' SEPTEMBER 1987:
Unit 1.
09/01/87 0001 Unit remains on administrative' hold to resolve various TVA and NRC' concerns, and end.of cycle'6 refuelins and modifications. continues.
09/30/87 2400
' Unit remains on administrative hold to resolve various-TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
Unit'2 09/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications. continues.
1
-09/30/87 2400
' Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling'and modifications continues.
Unit 3 09/01/87 0001 Unit remains on administrative hold to resolve various
.i TVA and NRC concerns, and environmental qualifications and modifications continues.
09/30/87 2400 Unit remains on administrative hold to resolve various TVA and NRC conwerna, and environmental qualifications and modifications continues.
5 1
i'
v OPERATING DATA REPORT-DOCKET NO. 50-259 DATE 10-01-87 COMPLETED BY J. D. Crawford TELEPHONE (205? 729-2507'
- (FERATING STATUS l Notes l
'.l.
Unit Name:
Browns Ferry Unit One
.l l
2.~
Reprting Period Sootember 1987 l
l 3.
Licensed Thermal Power (Wt): :3293 l
l 4.
Nameplete Rating (Gross MWe): 1152 l
l 5.
Design Electrical Rating (Net MWe) 8065 l
l 6.
Maximum Dependable Capacity (Gross We) 1096.4 l
l-
,7.
Maximum Dependable Capacity (Net MWe) 1065 l-I j
8.
If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Give Reasons:
NIA 5
l
- 9.. Power Lovel To Which Restricted, if Any (Not MWe):
NlA 10.. Reasons For Restrictions, if Any:
NlA 1
This Month Yr-to-Date Cumulative ll. Hours in Roporting Period 720 6551 115,471 l
- 12. Number of Ilours Reactor Was Crltleal 0
0 59.521.38 j
- 13. Reactor Reserve Shutdown Hours.
0 0
6.997.44
- 14. Hours Generator On-Line 0
0 58,767.26
- 15. Unit Roserve Shutdnwn Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
168.066.787 17.' Gross Electrical Energy Generated (MWH) 0 0
55.398.130
- 18. Net Electrical Energy Generated (MW.)
-724
-12068 53.708.567
- 19. Unit Service Factor 0
0 50.5 20.. Unit Availability Factor 0
0 50.5
- 21. Unit capacity Factor (Using MDC Net) 0 0
43.7
- 22. Unit Capacity Factor (Using DER tiet) 0 0
43.7
- 23. Unit Forced Outage Rate 100 100 39.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Fach):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be dotonnined
- 26. Units in Test Status (Prior to C<mnercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCtAL OPERATION (9l77) 6
1
<7 g
-;.1
<3, a.
4
-pf Q OPERATING DATA REPORT:
DOCKET NO.-
50-260 DATE 10-01-87 COMPLETED BY J. D. Crawford
..TELEPHUNE- (205) 729-2507-
'OPERAflNG STATUS' l Notes-l 1.
Unit Names-Browns Ferry Unit Two l-l
- 2. ; Reporting Period ~ September 1987-l l.
3.
Licensed Thermal Power. (MWt): 3293 l
.l-
.4 : Nameplate. Rating (Gross NWe): 1852
.l l
- 5.. Design Electrical' Rating'(Not MWc) 1065 l
l
- 6.'
Maximum Dependable Capacity (Gross MWe) 1098.4
'l l
'7.
Maximum Dependable Capacity.(Not MWe)<
1065
.l l
8,1 f f Changes Occur in Capacity Ratings (items Number 3 Through 7).Since Last Report, Give Reasons:
NlA
.9. ' Power Level To Which Restricted,.If Any (Not MWe):-
NIA 10, Reasons For Restrictions, if Any:
NlA This Month Yr-to-Date Cumulative ll. Hours Iri Reporting Period 720 6551 110.358
- 12. Number'of Hours Reactor Was Critical 0
0 55.860.03
- 13. Reactor Reserve Shutdown Hours 0
0 14.200.44-
- 14. Hours Generator On-Line 0
0 54.338.36
- 15. Unit Reserve Shutdown Hours 0
0 0-
- 16. Gross Thermal Energy Generated (MWH) 0 0
153.245.167
- 17. Gross Electrical Energy Genorated (MWH) 0 0
50.771.798
- 18. Net Electrical Energy Generated (MWH)
-4835
-24290 49,194.013
- 19. Unit Service Factor 0
0 49.2
- 20. Unit Availability Factor 0
0 49.2
- 21. Unit Capacity Factor (Using MDC Net).
0 0
41.9
- 22. Unit capacity factor (Using DER Net) 0 0
41.9
- 23. Unit Forced Outage Rate 100 100 38.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
l
- 25. If Shut Down At End Of Rerort Period, Estimated Date of Startup To be determined
'26. Units in Test Status (Prior to Conrnercial Operation):
Forecast Achloved INITIAL CRITICALITY INITIAL ELECTRICITY COPO4ERCIAL OPERAT10N I
J 7
1 i
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OPERATING DATA REPORT.
DOCKEI NO.
50-296 DATE
~TU~D M 7 COMPLETED BY J. D. Crawford TELEPil0NE (205) 729-2507 OPERATING STATUS-l Notes l
l '. Unit Names-Browns Ferry Unit Three-l l
'2.: Reporting Perlodi. September 1987-l l
1 3.
Licensed Thermal Power (Wt): 3293 l
l 4.
Nameplate Rating (Gross W e): 1152-l l
5.
Design Electrical Rating (Net We).1065 l
l 6.
Maximum Dependable Capacity (Gross We) 1098.4 l
l
'7.
Maxima Dependable Capacity (Net We) ~
1065 l
l q
8.
If Changes Occur in Capacity Ratings (f tems Number 3 Through 7) Since Last Report, Give Reasons:
NIA 9.
Power Level To Whlen Restricted, if Any'(Not We):
NlA 10, Reasons for Restrictions, I( Any:
NlA I
This Month Y,r-to-Date Cumulative
- 11. Hours in Reporting Period 720 6551 92.783
- 12. Number of Hours Reactor Was Critical 0
0 45.306.08
- 13. Reactor Reserve Shutdown Hours 0
0 5.149.55
- 14. Hours Generator On-Line 0
0 44.194.76
- 15. Unit Roserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (WH) 0 0
131.868.267
- 17. Gross Electrical Energy Generated (WH) 0
___ _ 0 43.473.760
- 18. Net Electrical Energy Gonorated (WH)
-4295
-38352 42,053.776
- 19. Unit Service factor 0
0 47.6
- 20. Unit Availability Factor 0
0 47.6
- 21. Unit Capacity Factor (Using MDC Net) 0 0
42.6
- 22. Unit Capacity Factor (Using DER Net) 0 0
42.6 __
- 23. Unit Forced Outage Rate 100 100 41.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
' 26. Units in Test Status (Prior to Coninercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERAT10N (9l7/)
8
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- f;
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AVERAGE DAILY UNIT POWER LEVEL.
DOCKET NO.
50-259 Unit' One DATE 10-01-87 1
COMPLETED BY
.J.D. Crawford
. TELEPHONE
-(205)729-'2507
. MONTH'
' SEPTEMBER 1987 DAY.
AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
'(MWe-Net)
(MWe-Net) 1
-1 17
-1 2
-1 18
-1 3
-1 19
-1 4
-1 20
-1 5
-l' 21
-1 6
-1 22
-1 7
-1 23
-1 8
-1 24
-1 9
-1 25
-1 10
-1 26
-1
~
11
-1 27
-1 12
-1 28
-1 13
-1 29
-1 14
-1 30
-1 15-
-1 31 l
~16
-1 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
I l
(9/77) 9 l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 Unit Two i
DATE 10-01-87 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH SEPTEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DATLY POMER LEVEL (MWe-Net)
(MWe-Net) 1
-5 17
-7 2
-7 18
-7 3
-7 19
-7 4
-7 20
-6 5
-6 21
-7 6
-7 22
-6 7
-6 23
-9 8
-8 24
-6 9
-6 25
-7 10
-7 26
-7 11
-7 27
-8 12
-7 28
-7 13
-7 29
-7 14
-7 30
-7 15
-7 31 16
-7 l
INSTRUCTIONS On this format, list the average daily unit power icvel in MWe-Net for cach day in the reporting month.
Compute to the nearest whoic megawatt.
l (9//7)
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L____ _ _
+
ir
.a -
AVERAGE DATLY UNIT ~ POWER LEVEL DOCKET NO.s 50-296 Unit Three-DATE 10-01-87 COMPLETED BY.
J.D. Crawford TRLEPHONE (205)729-2507 MONTH SEPTEMBER'1987 I
- DAY-AVERAGE. DAILY POWER LEVEL =
. DAY' "AVRRAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) fl
-6 17
-6
-2
-6' 18
-6 3
'- 19
-5 4-20
-6 4-
'5:
-6 21
-6 i
6
-6 22
-6 l
1
! 7 23
-6 1
1 8
-6 24
-6 0
-6 25
-6 i
10.
-6 26
-6 11
-6 27
-6 12
-6 28
-6 l
4 13
-6 29
-6 14
-6 30
-6 15
-6 31 16
-6 l
INSTRUCTIONS On this format, list the average daily unit power icvel in MWe-Net for each day in the. reporting month.
Compute to the nearest whole megawatt.
(9//7) 11
__ _ _ ___ _ _ = _ _ _
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' Operations Summary (Continued)
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.' AUGUST 1987 l
1
{
Fatigue Usage Evaluation The cumulative usage factors ' for the reactor vessel are as follows:
\\
$1 t,ocation Usage Factor
)
i Unit l' Unit 2 Unit 3 Shell at water line 0.00620 0.00492
- 0.00431 I
- Feedwater nozzle' O.29782 0.21319
- 0.16139 8
Closure studs 0.24204 O.17629
- 0.1436,0 NOTE: This accumulated monthly information satisfies Technical i
1 Specification Section 6.6.A.17.b(3) reporting requirements.
J Common System Approximately'9.78E+05 Sailons of waste liquids were discharged containing
{
approximately 2.'64E-02 curies of activity.
- Revision l'
i 9
l 15
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'-iT Operations Summary-(Continued):
JULY.1987.
' l-Fatigue' Usage Evaluation The.cumu'1stive usage-faetors for the reactor vessel-'are as follows:
Location' UsaRe Factor Unit 1 Unit 2-Unit 3
,Shell at water'line 0.00620 0.00492
- 0.00431' Feedwater nozzle ~
-0.29782 0.21319
- 0.16139.
-Closure studs 0.24204 0.17629
- 0.14360
" NOTE: - This accumulated monthly information-satisfies Technical Specification Section 6.6.A.17 b(3) reporting requirements.
Common System Approximately 1.03E+06 gallons of waste liquids were discharged containing approximately 2.65E-02 curies of activity.
- Revision l
4 16
f 1
Operations Summary (Continued)
I l
JUNE 1987 l
1 i
Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
i l
Location Usage Factor i
Unit 1 Unit 2 Unit 3 1
Shell at water line 0.00620 0.00492
- 0.00431 Feedwater nozzle 0.29782 0.21319
- 0.16139 1
Closure studs 0.24204 0.17629
- 0.14360 l
NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.b(3) reporting requirements.
Common System Approximately 8.74E+05 gallons of warte liquids were discharged containing approximately 3.82E-02 curies of activity, i
- Revision l
17
o
. y
'---w-~--
~' ~~~~
--- - - - - ~- -~
~---'
~~ R i
a
.,m
(!!$c, l-y I L 3
-Operations Summary (Continued)
MAY 1987J Fatigue Usage Evaluation The. cumulative usage factors for the reactor. vessel are as follows:
Location Usage Factor 1
l.
tinit 1 tinit:2 Unit 3 Shell at water line 0.00620 10.00492
- 0.00431 i
'Feedwater nozzle 0.29782 0.21319
- 0.16139-
)
Closure studs 0.24204 LO.17629.
- 0.14360 NOTE: This accumulated monthly information satisfies Technical i
Specification Section 6'.6.A.17.b(3) reporting requirements.
Common System
' Approximately 8.13E+05 gallons of waste liquids were discharged containing approximately 1.75E-02 curies of activity.
"Y
- Revision l
l 18
__.__..m_.__.m._.__
m..___..m___
- u v
i 1
.)
. Operations' Summary (Continued)E
]
4 APRIL 1987.
.c j
. Fatigue Usage Evaluation
.The cumulative usage factors for thel reactor vessel are as follows:
l
. Loc ation
Usage Factor Unit 1 Unit 2 Unit 3 i.
~
Shell'at water line 0.00620 0.00492
- 0.00431-Feedwater nozzle 0.29782 0.21319
- 0.16139' 1
Closure studs 0.24204 O.17629
- 0.14360 NOTE: This accumulated monthly information satisfies Technical E
' Specification Section 6.6.A.17.b(3) reporting requirements.
1 Common System'
-}
'Approximately 9.61E+05 gallons-of waste liquids were discharged containing
~
approximately 2.72E-02 curies of activity.
- Revision 1
1 i
I-19
Q >
l.'.
Operations' Summary (Continued)
MARCH 1987' l
I Fatigue' Usage Evaluation The cumulative usage-facters for the reactoe vessel are as follows:
I.ocation Usage Factor Unit I tinit 2 tinit 3 q
'Shell at water line 0.00620 0.00492
- 0.00431 Feedwater nozzle'
'O.29782 0.21319'
- 0.16139
' Closure' studs 0.24204 0.17629
- 0.14360 NOTE:
This. accumulated monthly information satisfies Technical Specification Section 6'.'6.A.17.b(3)Lreporting requirements.
Common System:,
Approximately'*9.5E+05. gallons of waste liquids were discharged containing approximately *1.46E-02 curies of activity.
ARevision l
t 20 l
I au___
V.
h$.)g ei y,.--
"; ',4 7 i\\
J'
..,3 e l't Operations Summary (Continued)~
3 FEBRUARY.1987 r
Fatir.ue Usaxe Evaluation y
6 The cumulative usage' factors for the reactor vessel are as follows:
I,ocation' Usage Factor Unit 1 Unit'2 Unit 3-Shell at water line 0.00620 0.00492
- 0.00431 Feedwater nozzle 0.29782 0.21319
- 0.16139 Closure studs 0.24204 0.17629
- 0.14360 NOTE:.This accumulated' monthly'information satisfles Technical <
Specification Section 6.6.A.17.b(3) reporting' requirements.
Common System Approximately *9.5E+05 gallons of waste liquids were discharged containing approximately *1.46E-02 curies of activity.
- Revislon 21
le.e TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 OCT 131987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Office of Nuclear Reactor Regulation l
Washington, D.C.
20555 l
l Attention: Office of Management Information and Program Control In the Matter of the
)
Docket Nos. 50-259 Tennessee Vallay Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - SEPTEMBER 19'8 Enclosed is the September 1, 1987 Monthly Operating Report to NRC for Brownas c:-
Ferry Nuclear Plant units 1, 2, and 3.
O $
ea %
Very truly yours, 7
> UM TENNES B:E VALLEY UTHORITY h
G. Walker ant Manager Enclosure cc: Mr. G. E. Gears Mr. G. G. Zech, Director Browns Ferry Project Manager TVA Projects U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 101 Marietta St., NW, Suite 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Browns Ferry Resident Inspector Region II Browns Ferry Nuclear Plant Attn:
Dr. J. Nelson Grace, P.O. Box 311 Regional Administratryr Athens, Alabama 35611 101 Marietta Street, N?d, Suite 2900 Atlanta, Georgia 30373 INPO Records Center Institute of Nuclear Power Mr. Ted Marston, Dire: tor Operations Electric Power Research Institute Suite 1500 1100 Circle 75 Parkway P. O. Box 10412 94304 Atlanta, Georgia 30389 Palo Alto, Californi-1
/p q
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