ML20213A355
| ML20213A355 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1986 |
| From: | Jones V, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 87-015, 87-15, NUDOCS 8702030234 | |
| Download: ML20213A355 (24) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _
, e' POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT 8
_ REPORT NO.
86-12 APPROVED:
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STATION MANAGER m.3 b
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1 SECTION PAGE Operating Data Report - Unit No. I 1
Operating Data Report - Unit No. 2 2
Unit Shutdowns and Power Reductions - Unit No.1 3
Unit Shutdowns and Power Reductions - Unit No. 2 4
Average Daily Unit Power Level-Unit No.1 5
Average Daily Unit Power Level-Unit No. 2 6
Summary of Operating Experience - Unit No. I 7
Summary of Operating Experience - Unit No. 2 8
Facility Changes Requiring NRC Approval 9
Facility Changes That Did Not Require NRC Approval 10-13 Tests and Experiences Requiring NRC Approval 14 Tests and Experiments That Did Not Require NRC Approval 15 Other Changes, Test and Experiments 16 Chemistry Report 17 Fuel Handling - Unit No. I 18 Fuel Handling - Unit No. 2 19 Procedure Revisions That Changed the Operating Mode Described in the FSAR 20 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications.
21
PAGE1 OPERATING DATA REPORT DOCKET NO.
50-280 DATE 1/6/87 COMPLETED BY V. H. Jones TELEPHONE 804-357-3184 OPERATING STATUS 1.
Unit Name:
Surry Unit 1 Notes 2.
Reporting Period:
12-01-86 thru 12-31-86 3.
Licensed Thermal Power (MWt):
2441 4.
Nameplate Rating (Cross MWe):
847.5 5.
Design Electrical Rating (Net MWe):
788 6.
Maximus Dependable Capacity (Cross MWe): 820 7.
Maximus Dependable Capacity (Net MWe):
781 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Cive Reasons:
9.
Power Level To Which Restricted, If Any (Net MWe): _
- 10. Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 744.0 8760.0 122952.0 239.0 6015.8 76854.3
- 12. Number of Hours Reactor Was Critical
[
- 13. Reactor Reserve Shutdown Hours 0
0 177d_q l
14 Hours Cenerator On-Line 239.0 6233.2 78545.3 0
M.2
- 15. Unit Reserve Shutdown Hours 578908.8 14190235.8 178072858.5
- 16. Cross Thermal Energy Generated (MWH)
- 17. Cross Electrical Energy Generated (MWH) 194365.0 4725985.0 57497918.0
- 18. Net Electrical Energy Generated (MWH) 185066.0 4488628.0 54521971.0 32.1%
71.2 %
63.9%
- 19. Unit Service Factor 32.1%
71.2 %
66.9%
- 20. Unit Available Factor
- 21. Unit Capacity Factor (Using MDC Net) 31.8%
65.6 %
57.4 %
- 22. Unit Capacity Factor (Using DER Net) 31.6 %
65.0%
56.3%
- 23. Unit Forced Rate 0
3.6 17.4 %
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:
01-26-87
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
OPERATINC DATA REPORT
~
i DOCEET NO.
50-281 DATE 1/6/87 caMPLETED sY V. H. Jones
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TE12 PRONE 804-357-3184 OPERATING STATUS Surry Unit 2 y e.,
1.
Unit Name:
2.
Reporting Period 19-ni-RAthm 1?_11_ng 3.
Licensed Thermal Power (IRft):
?aa1 1
4.
Nameplate Rating (Cross tele):
Ra7 c;
\\.. _,_
N 5.
Design Electrical Rating (Not 198p):
6.
Maximum Dependable Capacity (Cross IGfe):
R?n 7.
Maximus Dependable Capacity (Not MWe):
791 l
8.
If Changes occur in Capacity Ratings (Items Ihamber 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted, If Any (Net IGle):
- 10. Reasons For Restrictions, If Any
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This Month Yr.-to-Date Cumulative,
1
- 11. Hours Ic Reporting Period 744.0 8760.0
' 119832.0
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- 12. Number of Hours Reactor Was Critical 705.3 6168.1 78110.8
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 161.8 6075.0 76840.k%,
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- 15. Unit Reserve Shutdown Hours 0
0 0
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- 16. Cross Themal Energy Generated (MWB) 248562.I 14485443.0 179792473.6'
- 17. Cross Electrical Energy Generated (16f8) 79985.0 4739520.0 58327824.0
^
- 18. Net Electrical Energy Generated (MWR) 74347.0 4498941.0 55285524.0_
- 19. Unit Service Factor 21.8 %
69.3 %
64',1_%
- 20. I'nic Available Factor 21.8 %
69.3 %
' G 4.1 %
- 21. Unit Capacity Factor (Using MDC Net) 12.8 %
65.8%
59.2 %
58.6 %
- 22. Unit Capacity Factor (Using DER Net) 12.7 %
6 5. 2,%. _
- 23. Unit Forced Rate 76.9 %
14.7 %
13.6 %
l
- 24. Shutdowns Scheduled Over Neat 6 Months (Type, Date, and Duration of Each):
y 25.
If Shut Down At End of Report Period Estimated Date of Startup:
2-15-87
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast
' ^
Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C000ERCIAL OPERATION (9/77)
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PAGE3-
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,y IMIT SHUIDOWNS AND P( M R REDUCTIONS DOCKET NO.
50-280 l
UNIT MAME Surry Unit 1
- DATE 1/6/87 COMPLETE BY V. H. Jones 1
REPORT MONIH DECEMBER,1986 TELEPHONE 804-357-3184' f
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- c LICENSEE g,j kj CAUSE & t'nanmer3Vg ACTION TO l
NO.
DATE k
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- J EVENT REPORT #
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$0 PREVENT RECURRENI 4
E jgg 1
The decision was made to perform the 86-09 12-10-86 S
505.0 H
1 scheduled Snubber / Maintenance outage early in order to allow a precautionary Main 1
Feedwater piping inspection as a result of l
pipe rupture in Unit #2.
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F: Forced Reason:
Method Exhibit G - Instructiona S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance or Test 2 - Manual Scram.
Entry Sheets for Licensee C - Refueling 3 - Automatic Scram.
Event Report (LER) File D - Regulatory Restriction 4 - Other (Explain)
E - Operator Training & License Examination 5
Exhibit 1 - Same Source F - Administrative C - Operational Error (Explain)
(9/77)
H - Other (Explain)
PAGE 4 UNIT SHUrDOWNS AND POWER REDUCTIONS DOCKET NO.
50-281 UNIT NAs Surry Unit #2 DATE 1/6/87 COMPLEIG BY V. H. Jones REPORT MorrH DECEMBER,1986 TELEPHONE 804-357-3184 L
, :a LICENSEE.
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EVENr
- j kj CAUSE & CORRECTIVE ACE ON TO MO.
DATE k
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.o gu PREvEwr RECURRErr g5 j gg 8
86-06 12-01-86 S
44.5 C
1 Unit was shutdown for refueling outage which commenced 10-04-86.
86-07 12-09-86 I'
537.7 A
3 LER-86/020 Reactor trip by low-low S/G level in "C" S/G caused by
'C MS trip valve closing.
Shortly after the reactor trip the 18" suction line to "A" Main Feed Pump ruptured due to pipe wall erosion /corro-sion.
"C" MS trip valve will be com-pletely overhauled prior to startup.
Condensate and feed piping will be examined and all piping below acceptance criteria will be replaced.
4 1
2 3
Exhibit C - Instructions Method F: Forced Reason:
S: Scheduled A - Equipment Failure (Emplain) 1 - Manual for Preparation of Data B - Maintenance or Test 2 - Manual Scram.
Entry Sheets for Licensee C - Refueling 3 - Automatic Scram.
Event Report (LER) File D - Regulatory Restriction 4 - Other (Explain)
E - Operator Training & License Examination 5
Exhibit 1 - Same Source F - Administrative C - Operational Error (Explain)
(9/77)
H - Other (Explain)
't PAGES AVERA M DAILY UNIT POWER LEVEL D0cKEr m.
50-280 UNIT Surry Unit 1 DATE 1/7/d/
COMPLETED BY V. H. Tones TELEPHONE 804-357-3184 mNru December,1986 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Ne t)
(MWe-Net) 1 785 17 0
2 782 18 0
3 783 19 0
4 784 20 0
5 783 21 0
6 787 22 0
7 780 23 0
8 786 24 0
9 786 25 0
10 657 26 0
11 0
27 0
L 12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
INSTRUCTIONS l
1 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.
(9/77)
PAGE6 AVERA M DAILY UNIT POWER LEVEL Docxtr no.
50-281 UNIT Surry Unit 2 DAIE I/7/87 COMPLETED BY V. H. Jones 2ELEPHONE 804-357-3184 noNrs December,1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i 1
0 17 0
2 23 18 0
3 187 19 0
4 189 20 0
5 306 21 0
6 521 22 0
7 657 23 0
8 754 24 0
9 460 25 0
10 0
26 0
11 0
27 0
12 0
28 0
0 29 0
13 l
14 0
30 0
15 0
31 0
16 0
INSTRUCTIONS i
I l
l 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.
(9/77) i i
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PAGE 7
SUMMARY
OF OPERATING EXPERIENCE MONTH / YEAR DECEMBER,1986 Listed below in chronological sequence by unit is a summary of
. operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT ONE 12-01-86 0000 This reporting period begins with the unit at 100% power,820MW's.
12-09-86 1430 Station " Notification of Unusual Event" declared, due to unit #2 condensate piping rupture.
1440 Upgraded Emergency classification to " Alert".
1625 Secured from station " Alert".
12-10-86 1730 Commenced unit shutdown at 150MW/hr for secondary pip.ing inspection.
2246 Generator off the Ene.
12-11-86 0050 Reactor shutdown.
1-2123 RCS < 200 F.
12-14-86 0910 RCS at mid-nozzle.
12-31-86 24o0 This reporting period ends with the unit at CSD on RHR for feed and condensate piping replacement.
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SUMMARY
OF OPERATING EXPERIENCE MONTH / YEAR DECEMBER,1986 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT TWO 12-01-86 0000 This reporting period begins with the reactor critical and physics testing in progress.
0646 Manually tripped reactor to reset step counters. Physics testing is complete.
0745 Reactor critical.
12-02-86 2033 Generator on the Une.
2110 Holding power at 30%,220MW's for flux mapping and chemistry.
12-05-86 0345 Commenced power increase at 4%/hr.
0900 Holding power at 50%,370MW's for flux mapping.
2046 Commenced power increase at 4%/hr.
12-06-86 0208 Holding power at 70%,555MW's for flux mapping.
1830 Commenced power increase at 4%/hr.
12-07-86 0007 Holding power at 82%,660MW's, monitoring turbine bearing vibrations.
0410 Commenced power increase at 1-2%/hr. Monitoring "6B" feedwater i
heater level and turbine vibration.
0605 Holding power at 86%,710MW's while working in HPD tank flow.
2118 Commenced power increase at 3%hr.
12-08-86 1120 At 100% power,810MW's.
12-09-86 1420 Reactor trip caused by low-low S/G 1evel in "C" S/G due to the "C" MS trip valve closing.
1430 Station " Notification of Unusual Event" declared, due to main l
condensate piping rupture after reactor trip.
1440 Upgraded Emergency classification to " Alert".
1625 Secured from station " Alert".
12-10-86 0013 RCS < 350 F,450 PSIG.
0703 RCS < 200oF.
12-31-86 2400 This reporting period ends with the unit at CSD on RHR for condensate pipe replacement for feed and condensate pipe replacement.
PAGE 9 FACILITY CHANGES REQUIRING NRC APPROVAL MONTH / YEAR DECEMBER,1986 DC 85-05 Large Bore Snubber Modifications
, Unit 2 This design change replaced four of the pressurizer snubbers with fixed gap restraints; modified the snubber bolts of the steam generator upper restraints; eliminated two of the four-inch bore Bergen-Patterson snubbers on the reactor coolant supports; and modified the remaining steam generator supports and reactor coolan't pump supports.
Summary of Safety Analysis The modifications made to the reactor coolant system equipment supports do not change the design basis, functional requirements, or operation of the reactor coolant system and its associated equipment supports. The modified components have been designed to carry the same loads as required by the original design.
L
PAGE 10 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL 1
MONTH / YEAR DECEMBER 1986 l
UNIT i
DC 81-103 Class IE Solenoid Operated Valve Replacement 2
This design change removed certain solenoid operated valves (SOV's) whose qualifications have not been demonstrated to be adequate. These valves were replaced with equivalent SOV's which have adequately demonstrated environmental qualification.
This design change was previously reported in September 1983. However, additional valves were added to the scope of the design change and is therefore reported a second time.
Summary of Safety Analysis The modification will provide additional assurance that the SOV's will perform their intended safety function during and following any postulated LOCA or HELB accident.
DC 81-119 NUREG-0696 Short Term I & C Project - Remote Multiplexer 1&2 (A & B)
Installation This design change provides a number of remote multiplexers and buffer units, which are the front-end portions of the Data Acquisition System (DAS). The DAS will collect and transmit required data, vital information, and plant status.
Summary of Safety Analysis The modification does not affect normal station operation j
nor the operation of any safety-related equipment. In the event of an accident or on-site emergency, the independent DAS provides a separate source of plant status
(
and information, therefore increasing overall plant safety.
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PAGE 11 FACILITY CHANGES TH AT DO NOT REQUIRE NRC APPROVAL P
MONTH / YEAR DECEMBER 1986 UNIT DC 85-08 Valve Monitoring System PORV and Pressurizer Safety Valves 1
This design change replaces the valve monitoring system fcr the pressurizer power operated relief valves and the safety valves with equipment which is environmentally qualified as required by Reg. Guide 1.97.
Summary of Safety Analysis The PORV's and SV's will provide more reliable indication of valve position during all modes of plant operation because of the redundant channels and the class IE, environmentally and seismically qualified devices. The replacement devices conform to the previous evaluation of the FSAR.
DC 85-09 Valve Monitoring System PORV and Pressurizer Safety Valves 2
This design change replaces the valve monitoring system for the pressurizer power operated relief valves and the safety valves with equipment which is environmentally qualified as required by Reg. Guide 1.97.
Summary of Safety Analysis The PORV's and SV's will provide more reliable indication of valve position during all modes of plant operation because of the redundant channels and the class IE, environmentally and seismically qualified devices. The replacement devices conform to the previous evaluation of the FSAR.
DC 85-17 Service Water Motor Operated Butterfly Valves Replacement 1
The service water motor operated butterfly valves, MOV-SW-103 A, B, C, and D, were replaced with high performance butterfly valves which incorporated enhanced design features to alleviate leakage and bending and were constructed of materials suitable for the service conditions.
Summary of Safety Analysis The changeout of the valves is a one-for-one replacement.
The high performance valves of enhanced design provide improved service in their operating environment. The valves do not alter or affect the system operation or the function of any safety related system. The valves are seismically qualified and seismically installed.
PAGE 12
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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR DECEMBER,1986 UNIT DC 85-18 Service Water Motor Operated Butterfly Valves Replacement 2
TM service water motor operated butterfly valves, MOV-SW-203A, B, C, and D, were replaced with high performance butterfly valves which incorporated enhanced design features to alleviate leakage and bending and were constructed of materials suitable for the service conditions.
Summary of Safety Analysis The changeout of the valves is a one-for-one replacement.
The high performance valves of enhanced design provide improved service in their operating environment. The valves do not alter or affect the system operation or the function of any safety related system. The valves are seismically qualified and seismically installed.
DC 85-33 Black Battery and Building Addition I
This design change installed a pre-engineered, metal" black" Battery Building on concrete foundation, located near the Turbine Building, adjacent to Unit I station transformer area, to house both Units 1 and 2 " black" batteries and associated equipment.
(Unit 2 " black" battery system will be installed under DC-85-35-2). The building will be provided with lighting, fire detection, gaitronics communication, heating, and ventilation systems.
This design change also installed a
" black" (nonsafety-related) 125V DC electrical battery and battery charging system. Large nonsafety-related electrical loads such as the emergency turbine oil pump (60 hp) and the air side seal oil backup pump (25 hp) will be powered from i
this system rather than the class IE,125V DC buses. In addition, part of the electrical heating, ventilation, and lighting loads of the " black" Battery Building will be powered from this system.
Summary of Safety Analysis This modification involves a nonsafety-related system in nonsafety-related areas, and will have no impact on j
any safety-related systems. It will improve the existing l,
class IE,125V DC system by assuming non-class IE loads to the black battery system. The new equipment will be designed, fabricated and installed to meet or exceed the requirements of the applicable sections of the Design l
Basis Document.
PAGE 13 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR DECEMBER,1986 UNIT DC 85-35 Black Battery Addition 2
This design change installed a " black" (nonsafety-related) 125V DC electrical battery and battery charging system.
Large nonsafety-related electrical loads such as the emergency turbine oil pump (60 hp) and the air side seal oil backup pump (25 hp) will be powered from this system rather than the class IE 125V DC buses. In addition, part of the electrical heating, ventilation, and lighting loads of the black Battery Building erected under DC 85-33 will be powered from this system.
Summary of Safety Analysis This modification involves a nonsafety-related system in nonsafety-related areas, and will have no impact on any safety-related systems. It will improve the existing class IE,125V DC system by assuming non-class IE loads to the black battery system. The new equipment will be designed, fabricated and installed to meet or exceed the requirements of the applicable sections of the Design Basis Document.
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PAGEI4 1
TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH / YEAR DECEMBER,1986 i
NONE DURING THIS PERIOD j
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PAGE 15 1
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR DECEMBER,1986 NONE DURING THIS PERIOD 4
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PAGE16 4
i OTHER CHANGES, TEST AND EXPERIMENTS 2
MONTH / YEAR DECEMBER,1986 i
i NONE DURING THIS PERIOD I
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PAGE 17 VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT Ceber 19 26 00N UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX.
MIN.
AVG.
MAX.
MIN.
AVG.
-2
-1
~1
-3
-2 Gross Radioact., uCi/mi 1.96 2.16 6.52 1.85 2.94 3.59 0.2 0.2 0.2 0.0 0.0 0.0 Suspended Solids, ppe
~1
-1
-2
-2
-2 Gross Tritium, uCi/:a1 1.48 1.20 1.34 5.49 4,49 4,gg
~
-3
-4
-3
~4
-5
~4 Iodine
, uCi/a1 5.81 P.73 3.82 6.34 3.51 1.56 I31 0.14 0.08 0.12 0.13 0.09 0.10 I
/I IAI 21.2 ^I 31.7 26.6 2P.F I
37.8 1.9 Hydrogen, cc/ka 1.56 1.37 1.45 2.67 1.87 2.21 Lithium, ppa 403 163 322 291 211 321 Boron-10, ppm
- 50.005 10'.005 10.005 13.005 10.005 10.005-0xygen, (DO), ppe 0.010 10.001 0.003 0.010
$0.001 0.002 Chloride, ppa 6.61 5.72 6.17 6.52 5.71 6.01 pH @ 25 degree Celsius
- Boron-10 = Total Boron X 0.196 REMARKS:
Unit 1:
Unit was shutdown on 12-10-F6 for an instuction/naintenance E total of 226 crans of LiOil was added to Unit One on 12-5-R6.
':te outace.
Ct.T Ded was not niaced in service in reembor.
(t) Str low lNorocon valtrs are due to deaasino after st utdown.
Unit 2: A total of 50 crans of Licil was added to Unit Two on 12-5-96.
':te CAT Cod was placed in service on 12-5-P6 and 12-P-R6.
.- - - =.
PAGE 18 UNIT I
FUEL HANDLING DATE Dec 1986 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC SHIPMENT #
RECEIVED PER SHIPMENT ENRICHMENT CASK ACTIVITY AT ISFSI LEVEL CASTOR V/21 500-11-003 12-4-86 4
A25 NONE 1.87 1
4 A14 NONE 1.87 4
A46 NONE 1.87 4
A33 NONE 1.87 1
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PAGE 19 i
i UNIT 2
FUEL HANDLING DATE Dec,1986 l
NEW OR DATE NUMBER OF NEW OR SPENT I
SPElff FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC I
SHIPMENT #
RECEIVED PER SHIPMENT ENRICHMENT CASK ACTIVITY AT ISFSI LEVEL GASTOR V/21 500-11-003 12-04-86 17 L50 NONE 1.86 i
i 17 LO2 NONE 1.86 17 L44 NONE 1.86 17 L30 NONE 1.86 i
17 L52 NONE 1.86 4
17 L37 NONE 1.86 17 Ll4 NONE 1.86 i
17 L47 NONE 1.86 l
17 L40 NONE 1.86 1
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17 L18 NONE 1.86 i
17 L41 NONE 1.86 I
17 L15 None 1.86 j
17 LO3 NONE 1.86 17 Lil NONE 1.86 17 LOS NONE 1.86 17 L22 NONE 1.86 17 L10 NONE 1.86 i
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PAGE 20 1
i PROCEDURE REVISIONS THAT CHANGED THE i
OPERATING MODE DESCRIBED IN THE FSAR MONTH / YEAR DECEMBER,1986 NONE DURING THIS PERIOD J
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PAGE 21 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH / YEAR DECEMBER,1986 NONE DURING THIS PERIOD l
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o VIMOINIA ELucTurc AND POwna COMPANY llIC11M OND, VI HO IN I A 2312 61 January 19, 1987
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Vaca I*musinant Nortman Ormwarnown U. S. Nuclear Regulatory Commission Serial No.87-015 Attention: Document Control Desk N0/JDH/rh Washington, D. C.
20555 Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 l
MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos. I and 2 for the month of December 1986.
Very truly yours, h
W. L. Stewart Enclosure cc:
Dr. J. Nelson Crace Regional Administrator l
Region II Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station 0
G II