ML20207S968
| ML20207S968 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/28/1987 |
| From: | Jones V, Saunders R, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 87-144, NUDOCS 8703230004 | |
| Download: ML20207S968 (24) | |
Text
.
- - i POW 34-04 b
VIRGINIA ELECTRIC AND POWER COMPANY -
SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 87-02' APPROVED:
/> * -
eM STATION MANAGER 8
DO h
a fly I/
g SECTION -
PAGE-Operating Data Report - Unit No.1 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 Experier.ce - Unit No. I 7
Summary of Operating Experience - Unit No. 2 7
Facility Changes Requiring NRC Approval 8
Facility Changes That Did Not Require NRC Approval 9-13 Tests and Experiments 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 Handung - 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 Specification's 21
F PAGE 1 OPERATING DATA RIPORT DOCKET NO.
50-280 DATE Mar 4.1987 COMP!2TED BY V. H. Ienes TE12 PHONE 804-357-3184 OPERATINC STATUS 1.
Unit Name:
Surry Unit 1 Netes 2.
Reporting Period:
02-01-87 to 02-28-87 3.
Licensed Thermal Power (MWe):
2441 4 Nameplate Rating (Cross NWe):
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 Cuautative
- 11. Hours In Reporting Period 672.0 1416.0 124368.0
- 12. Number of Hours Reactor Was Critical 129.0 124.0 78674.3
- 13. Reactor Reserve Shutdown Hours 0
0 3774.5 14 Hours Generator On-Line 123.6 123.6 76477.9
- 15. Unit Reserve Shutdown Ecurs 0
0 3736.2
- 16. Cross Thermal Energy Generated (MWR) 194111.5 194111.5 178266970.0
- 17. Cross Electrical Energy Generated (WH) 65620.0 65620.0 57563538.0 1s. Net Electrical Energy Generated (MWM) 61106.0 61106.0 54583077.0
- 19. Unit Service Factor 18.4 %
8.7%
61.9 %
- 20. Unit Available Factor 18.4 %
8.7%
64.9 %
- 21. Unit Capacity Factor (Using MDC Net) 11.6%
5.5%
56.8*o
- 22. Unit Capacity Factor (Using DER Net) 11.5 %
5.5%
55.7 %
- 23. Unit Forced Rate 0
0 17.7%
24 Shutdowns Scheduled Over Nest 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIA1.CRITICAI.ITY INITIAL Et2CIRICITY COMERCIAL OPERATION l
(9/77)
PAGE 2 OPERATING DATA REPORT DOCKET NO.
50-281 DATE Mar.4,1987 COMPLETED BY V. H. Tones TEI.EPHONE 804-357-3I84 OPERATING STATUS 1.
Unit Names Surry Unit ?
Notes 2.
Reporting Period:
02-01-87 to 02-?g-97 3.
Licensed Thermal Power (MWt):
2ddl 4 Nameplate Rating (Cross. e):
R d7_ ci W
5.
Design Electrical Rating (Net MWe):
788 6.
Maximus Dependable Capacity (Cross MWe):
A70 7 Maximum Dependable Capacity (Net MWe):
7R1 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power 1.evel To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr.ato-Date Cumulative
- 11. Hours In Reporting Period 672.0 1416.0 121248.0
- 12. Number of Hours Reactor Was criticai 0
0 78110.8
- 13. Reactor Reserve Shutdown Hours 0
0 12g,1 14 Hours Generator On Line 0
0 76840.4
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Cross Thermal Energy Generated (MWH) 0 0
179792473.6
- 17. Cross Electrical Energy Generated (MWH) 0 0
58327824.0
- 18. Net Electrical Energy Generated (MWH) 0 0
55285524.0 0
0 63.4*6
- 19. Unit Service Factor 0
0 63.4 5
- 20. Unit Available Factor
- 21. Unit Capacity Factor (Using MDC Net) 0 0
58.5 5
- 22. Unit Capacity Factor (Using DER Net) 0 0
57.9 6 100.0%
100.0%
13.6 6
- 23. Unit Forced Rate 24 Shutdowns Scheduled Over Neat 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period Estimated Date of Startup 03-12-A7
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved 1NITIAL CRITICALITY INITIAL ELECTRICITY C0lM RCIAL OPERATION (9/77)
PAGE 3
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uMIT SwrnahneS Ase Fonsa mmritoMS DOCKET po.
50-280 tm1T suas Surry I DATE March 4,1987 Cos@LETED BY V.II. Jones REroRI NOIFIH February 1987 TEttemonE 804-357-3184 c
- c LICENSEE e
c h,j kj cAUSE & CoRISCTIVE ACTION TO No.
DATE k
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548.4 H
I The decision was made to perform the scheduled Snubber / Maintenance outage early in order to allow a precautionary Main Feedwater piping inspection as a restrit of pipe rupture in Unit #2.
F: Forced Reason:
Method:
Exhibit C - Instructions S: Scheduled A - Equipment Failure (Emplain) 1 - Manual for Preparatico of Data B - Maintenance or Test 2 - Manual Scram.
Entry Sheets for Licensee C - Refueling 3 - Automatic Scram.
Event Report (lea) File D - Regulatory Restriction 4 - Other (Explain)
(NUREC 6161)
E - Operator Training & License Examinatica F - Administrative Exhibit 1 - Same Source C - Operational Error (Emplain)
(9/77)
H - Other (Explain)
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PAGE 5 AVERAG DAILY UNIT POIER LEVEL DOCKET NO.
K0 7R0 ll NIT h erv 1 DATE W r 4_14R7 COMPLETED BY V. M_ Tnnon TELEPIIDIE I An di 197-11 R 4 MDemi Pohruary 1987 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
1 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 14 8
0 24 177 9
0 25 313 10 0
26 497 11 0
27 753 12 0
28 793 11 0
14 0
15 0
16 0
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.
(9/77)
PAGE 6 AVERAG DAILY UNIT Polder LEVEL DOCKET Mo.
50-281 LHIT Surry II
.DATE Mar 4,1987 COMPLETED BY V. H. Tones TELEPHONE (804) 357-3184
.M Fnbruary 1987 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (We-Net)
(We-Net) 1 0
17 0
2 0
18 0
1 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
0 11 0
27 12 0
0 28 11 0
0 14 0
15
- 6 0
INSTRI'CTIONS On this format, list the average daily unit power level in We-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
7 f J! i PAGE 7s
SUMMARY
OF OPERATING EXPERIENCE MONTH / YEAR FEBRUARY 1987 Listed below in chronological sequence by. unit is a summary of operefing experiences for this month which required load reductions or resulted in -
significant non-load related incidents.
UNIT ONE 02-01-87 0000 This reporting period begins with the unit at CSD on RHR.
with "C" RCP running.
02-13-87 0434 RCS > 2000F.
1505 Commenced RCS cooldown, due to U-2 charging pump t'
service water supply line 00S.
1940 RCS < 2000F.
02-21-87 1515 RCS > 2000F.
4 02-22-87 0220 RCS > 3500F,450 psig.
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02-23-87 1457 Reactor is critical.
/-
2025 Generator on line.
r-l 2135 Unit at 30% power,205 MW's, holding for chemistry.
02-25-87 1107 Commenced power increase at 100 MW/hr.
I 1500 Holding power at 60%,480 MW's for chemistry.
h' 02-26-87 2147 Commenced power increase.
(x 2310 Holding power at 87%,740 MW's to allow cleaning of CP
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strainers.
02-27-87 0830 Commenced power increase at 50 MW/hr.
1120 Holding power at 97%,800 MW's for CP straintrs.
1930 Slowly increasing power to 100 %.
2020 Unit at 100%,835 MW's.
t 02-28-87 2400 This reporting period ends with the Unit at 100%, 835 M W's.
i UNIT TWO 02-01-87 0000 This reporting period begins with the unit at CSD on RiiR.
i 02-28-87 2400 This reporting period ends with the unit at CSD on RHR.
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PAGE 8 4%,
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.f FACILITY CIIANGES REQUIRING NRC APPROVAL MONTH / YEAR FEBRUARY 1987 NONE DURING THIS PERIOD t
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PAGE 9 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR FEBRUARY 1987 UNIT DC 81-103 Class IE Solenoid Operated Valve Replacement 1
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. Howeter, 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 83-39A Appendix 'R' Emergency Diesel Generator Mods 1
This design change relocated existing relays and added a transfer switch, metering and control and indication for circuit breakers and diesel engines in the EDG room. This will permit operation of the EDG from the EDG room in the event of a control room evacuation.
Summary of Safety Analysis This design change increases the availability of the EDG control circuits following-a fire., The transfer switch is key locked and alarmed to prevent unauthorized actuation.
The modification will not reduce the capacity, method of operation, or design basis of safety related equipment for any postulated accident.
PAGE 10.
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR FEBRUARY 1987 UNIT DC 85-02
_ Containment Gas and Particulate Monitor System 1
The containment gas and particulate monitors have a history of malfunctioning which results in erroneous readings, tripping the containment purge system. Also, the pump is located inside the containment which causes a maintenance problem if there is a pump failure during power operation. The existing monitor will be replaced with a new monitor installed in approximately the same location. The new monitor has an integral sample pump, thereby making it accessible for any required maintenance.
The existing pump will be removed.
The new monitor employs a state-of-the-art moving particulate filter. This filter will eliminate the inleakage problems, filter failures and will also minimize filter changes in comparsion to a fixed filter.
Summary of Safety Analysis The function of the containment gas and particulate monitor system is not beir.g altered by this design change.
In fact, the replacement of the monitor will increase the reliability of the readings provided by this system. The relocation of the pump from inside containment to the auxiliary building will make this portion of the system more accessible for maintenance in addition to further reducing the exposure to personnel conducting routine maintenance activities to this equipment.
This design modification will neither replace or modify any safety system. The pump will not create a hazard to any safety related equipment in its new location during a seismic event. The containment gas and particulate monitor system will remain operational during refueling operations as specified in Technical Specification 3.10.
Therefore, this design modification will not impact the function of the containment purge isolation system or any other systems during construction or post-construction phases.
PAGE 11 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR FEBRUARY 1987 UNIT DC 85-03 Containment Gas and Particulate Monitor System 2
- The containment gas and particulate monitors have-a history of malfunctioning which results in erroneous readings, tripping the containment purge system. Also, the pump is located inside the containment which causes a mainten nce problem if there is a' pump failure during power operation. The existing monitor will be replaced with a new monitor installed in approximately the same location. The new monitor has an integral sample pump, thereby making it accessible for any required maintenance.
The existing pump will be removed.
The new monitor employs a state-of-the-art moving particulate filter. This filter will eliminate the inleakage problems, filter failures and will also minimize filter changes in comparsion to a fixed filter.
Summary of Safety Analysis The function of the containment gas and particulate k
monitor system is not being altered by this design change.
U In fact, the replacement of the monitor will increase the reliability of the readings provided by this system. The relocation of the pump from inside containment to the auxiliary building will make this portion of the system more accessible for maintenance in addition to further reducing the exposure to personnel conducting routine maintenance activities to this equipment.
This design modification will neither replace or modify any safety system. The pump will not create a hazard to any safety related equipment in its new location during a seismic event. The containment gas. and particulate monitor system will remain operational during refueling operations as specified in Technical Smcification 3.10.
Therefore, this design modification will not impact the function of the containment purge isolation system or any other systems during construction or post-construction phases.
PAGE 12 FACILITY CHANGES THAT DID NOT REQUIRE NRC' APPROVAL MONTH / YEAR FEBRUARY 1987 UNIT DC 84-38 HPSI Flow Transmitter and VCT Level Transmitters 1
Modification This design change added two transmitters for redundant measurements of total cold leg SI flow and total hot leg SI flow. The two VCT transmitters were replaced with EQ qualified transmitters and relocated to outside the VCT cubicle for ALARA purposes.
Summary of Safety Analysis The new transmitters are environmentally and seismically qualified.
Installation does not affect any safety equipment or the operation of safety systems.
DC 84-39 HPSI Flow Transmitter and VCT Level Transmitters 2
Modification This design change added two transmitters for redundant measurements of total cold leg S1 flow and total hot leg SI flow. The two VCT transmitters were replaced with EQ qualified transmitters and relocated to outside the VCT cubicle for ALARA purposes.
Summary of Safety Analysis The new transmitters are environmentally and seismically qualified.
Installation does not affect any safety equipment or the operation of safety systems.
DC 84-54 Snubber Replacement and Elimination 1
This design change removed some snubbers, replaced snubbers with a different type, replaced snubbers with rigid struts and reworked same snubbers. This was to eliminate potential problems, high costs for snubber maintenance and testing, and significant ALARA problems associated with maintenance and testing.
Summary of. Safety Analysis These modifications do not affect any aspect of the systems other than seismic support of the piping. The modifications do not result in pipe stress or support or nozzle loads in excess of the Designs Basis seismic allowables for the affected lines.
PAGE 13 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR FEBRUARY 1987 UNIT
- DC 85-15 Boron Evaporator Feedwater Demineralizer Modification I&2 This design change involved the installation of valves and piping to permit processing the boron evaporator-feedwater through demineralizers prior to the evaporators to lower radiation levels. The existing boron clean Ion exchangers, I-BR-I-2A and 1-BR-I-2B are utilized as the new boron evaporator feedwater demineralizers.
Summary of Safety Analysis The system is not safety-related and is not a part of the Technical Specifications. The piping cross-connects do not _ modify or alter existing safety-related equipment or systems.
4 r
PAGE 14 3
O TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL f
MONTH / YEAR FEBRUARY 1987 NONE DURING THIS PERIOD k
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d' PAGE 15 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR FEBRUARY 1987 NONE DURING THIS PERIOD k
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P OTHER CHINGES, TEST AND EXPERIMENTS MONTH / YEAR FEBRUARY 1987' NONE DURING THIS PERIOD i-i l
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PAGE ' 17 -
VIRGINIA POWER S1RRY POWER STATION
$1EMISTRY REPORT Fi'BRUARY 19 87
~
UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX.
MIN.
AVG.
MAX.
MIN.
AVG.
-1
-3
-2
-2
-3
-2 Gross Radioact., uCi/ml 8.15 2.94 7.46 3.43 3.56 1.11 0.0 0.0 0.0 0.0 0.0 0.0 Suspended Solids, ppa
-1
-1
~I 4.56 4.56 4.56 (B)
(B)
(E,3 Gross Tritium, uCi/mi
-3
-5
-3 I3I 3.53 39,74 1.42 (B)
(B)
(B)
, uCi/mi 131 131 (A)
(A)
(A)
(B)
(B)
(B) 7 j7 (B)
(B)
(B)
Hydrogen, cc/kg 44.3 33.3 38.2 F
Lithium, ppm 2.24 0.56 1.38 (C)
(C)
(C)
Boron-10, ppm
- 496 156 332 414 396 405 0xygen, (DO), ppa 10.005 s 0.005 s 0.005 0.700 50.005 50.085 Chloride, ppm 0.010 s 0.001 0.008 10.010 50.001 0.007 pH @ 25 degree Celsius 6.53 5.63 5.89 5.82 5.69 5.55
- Boron-10 = Total Baron X 0.196 RD4 ARKS:
Unit 1 - 3745 grams of LiOH added in Februarv.
(A) Test mt reiirM, unit not at stable power for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Unit 2 - No LiOH aMM in February.
(B) Test not recuired when reactor not critical.
(C) Lithium not required, unit terperature is less than 180'F for February.
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PAGE 18
' t' NIT I
FUEL HANDLING DATE February 1987 i
NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT #
RECEIVED PER SHIPMENT ENRICHMENT CASK ACTIVITT LEVEL NONE DUR[NG THIS PERIOD L
t
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1 I
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PAGE 19 UNIT
?
FUEL HANDLING DATE February 1987 NEW OR.
DATE NLHBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT #
RECEIVED PER SHIPMENT f
f ENRICHMENT CASK ACTIVITY LEVEL NONE DURIl4G THIS PEI.IOD
\\
PAGE 20 e
PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR MONTH / YEAR FEBRUARY 1987 NONE DURING THIS PERIOD s
E PAGE 21 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN> TECHNICAL SPECIFICATIONS MONTH / YEAR FEBRUARY 1987 NONE DURING THIS PERIOD f
l l
VINGINIA ELECTuIC AND Powsu COMPANY RIc IMoND,VIHOINIA 20261 March 16, 1987 w.L.srswaar Vsen Fansannut
. Nucs. man oramanone U.'S. Nuclear Regulatory Commission Serial No.87-144 Attn: Document Control Desk N0/FML:vlh 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 UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units I and 2 for the month of February 1987.
Very}rulyyours,
,% h.M W. L.
tewart Enclosure l
cc:
.U. S. Nuclear Regulatory Commission 101 Marietta Street, N. W.
i Suite 2900 Atlanta, GA 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station l
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