ML20212K969
| ML20212K969 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/31/1986 |
| From: | Jones V, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 86-764, NUDOCS 8701290256 | |
| Download: ML20212K969 (22) | |
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e VIRGINIA ELECTRIC & POWER COMPANY,
SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 86-10 APPROVED:
s#e STATION MANAGER fDy f61031 DR R
05000280 R PDR 4
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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 7
Facility Changes Requiring NRC Approval 9
Facility Changes That Did Not require NRC Approyal 10 Tests and Experiments Requiring NRC Approval 13 Tests and Experiments That Did Not Require NRC Approval 13 Other Changes, Test and Experiments 14 Chemistry Report 15 Fuel Handling 16 Procedure Revisions That Changed the Operating Mode 18 Described in the FSAR Description of Periodic Test Which Were Not Completed Within 19 the Time Limits Specified in Technica1 Specifications
Pag?I OPERATING DATA REPORT DOCKET No. Surry Unit 1-50-281 Daft Novernber 6,1986 COMPLETED BY V. H. Jones TELEPHONE (804) 357-3184 OPERATINC STATUS 1.
Unit Name Surry Unit 1 Notes 2.
Reporting Feriod:
10-01-86 to 10-31-R6 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 (Itema Number 3 Through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level To Which Restricted, If Any (Net NWe):
- 10. Reasons For Restrictions, If Any This Month Yr.-to-Date Cumulative 745.0 7296.0 121488.0
- 11. Hours In Reporting Period
- 12. Number of Hours Reactor Was Critical 745.0 5274.2 77586.3 0
0 3774.5
- 13. Reactor Reserve Shutdown Hours 745.0 _
5056.8 75895.3
- 14. Hours Cenerator On Line 0
0 3736.2
- 15. Unit Reserve Shutdown Hours
- 16. Cross Thermal Energy Generated (MWH) 1810509.0 11855029.0 175737651.7 608415.0 3938410.0 56710343.0
- 17. Cross Electrical Energy Generated (16fH) 579023.0 3738338.0 53771681.0
- 18. Het Electrical Energy Generated (MWH) 100.0 %
69.3%
63.0%
- 19. Unit Service Factor 100.0 %
69.3%
66.0 %
- 20. Unit Available Factor
- 21. Unit Capacity Factor (Using HDC Net) 99.5% -
65.6 %
57.1%
2.
Unit Capacity Factor (Using DER Net) 98.6 %
65.0%
56.2 %
0 4.4%
17.8 %
- 23. Unit Forced Rate Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):
24
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Comunercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY Coa 9ERCIAL OPERATION (9/77)
P g3 2 OPERATING DATA REPORT DOCERT No.Surry Unit 2-50-281 DATE November 6,1986 COMPUTED BY V. H. Iones TEuruous(804) 357-3184 OPERATING STATUS 1.
Unit Name:
Surry Unit 2 notes 2.
Reporting Period:
10-01-86 to 10-31-86 3.
Licensed Thermal Power (Mut):
2441 4
Nameplate Rating (Croes MWe):
847.5 S.
Design Electrical Rating (Net MWe):
788 6.
Maatsum Dependable Capacity (Cross lede):
820 7.
Maaimus Dependable Capacity (Net MWe):
781 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last N/A Report, Give Reascos:
9.
Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any This Month Yr.-to Date Cumulative
- 11. Rours In Reporting Period 745.0 7296_0 118368.0
- 12. Number of Hours Reactor Was Criticai 74.7 5946.8 77889.5
- 13. Reactor Reserve Shutdown Hours 0
0 328.1
- 14. Hours Generator On-Line 74.4 5913.2 76678.6 0
0 0
- 13. Unit Reserve Shutdown Houre
- 16. Cross Thermal Energy Generated (NWR) 174126.5 14236880.9 179543911.5
- 17. Cross Electrical Energy Generated (less) 55600.0 4659535.0 58247839.0
- 18. Het Electrical Energy Generated (MWE) 52675.0 4424594.0 55211177.0
- 19. Unit Service Factor 10.0 %
81.0 64.8%
- 20. Unit Available Factor 10.0%
81.0 64.8%
- 21. Unit Capacity Factor (Using MDC Net) 9.1 %
77.7 %
59.9%
2.
Unit Capacity Factor (Using DER Net) 9.0%
77.0 %
59.7%
- 23. Unit Forced Rate 0
7.9%
13.1%
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 November 26, 1986
- 26. Unite In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECIRICITT CottERCIAL OPERATION (9/77)
Darurt so, 50-280 toIT Suurnabs Ano routR REnocrious Unir Mass Surry Unit 1 DATE November 5,1986 conPLETS BT V. H. Tnnan REPO C MONIH October 1986 TELEPNOME (804) 357-3184 e,
'oo LICENSEE g,
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j Unit was reduced to 64% power,500mw for 1
86-08 10-5-86 F
0.0 A
1 repair of oil leak on 1-FW-P-1B. Leak repaired j
and unit returned to full power.
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Method:
Exhibit C - Instructione F: Forced Reason:
1 - Manual for Freparation of Data i
S: Scheduled A - Equipment Failure (Explain)
B - Maintenance or Test 2 - Manual Scram.
Entry Sheets for Licensee 3 - Automatic Scran.
Event Report (LER) File I
C - Refueling D - Regulatory Restriction 4 - Other (Explain)
(NUREC 0161)
E - Operator Training & License Emaninetton 5
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I AVERACE DAILY IMIT F0WER LEVEL DOCIET NO. 50-280 UNIT Surry Unit I DATE November 5,1986 COMPLETED SY V. H. Jones TIta nant (804) 357-3184 nowra October 1986 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 767 17 769 2
765 18 776 3
764 19 776 4
767 20 7ga 5
736 21 790 6
775 22 790 7
777 23 787 8
768 24 783 9
771 25 785 10 777 26 788 11 782 27 788 12 782 28 787 13 782 29 781 14 783 30 781 15 769 31 791 16 783 INSTRUCTIONS On this format, list the average dai.; unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
(9/77)
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Pcga 6 AVERAM DAILY UNIT POWER LEVEL DOCKET NO.
50-281 UNIT Surry Unit 2 DATE November 6,1986
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COMPLETED BY V. H. Jones RLEPH0em (804) 357-3184 nowru October 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 741 17 0
2 739 18 0
3 704 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
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
31 n
15 n
4 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) cen,-
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SUMMARY
OF OPERATING EXPERIENCE MONTH / YEAR OCTOBER 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 incident.
UNIT ONE 10-1-86 0000 This reporting period begins with
.the unit at 100% power,815 mw.
10-5-86 0625 Commenced unit rampdown at 150 mw/hr. for removal of 1-FW-P-1B from service.
0751 Holding power at 64%,500 mw, 0852 1-FW-P-1B RTS, commenced power increase at 150 mw/hr.
1115 Unit at 100% power,815 mw.
10-31-86 2400 This reporting period ends with the unit at 100% power,820 mw.
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SUMMARY
OF OPERATING EXPERIENCE MONTH / YEAR OCTOBER 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 10-1-86 0000 This reporting period begins with the unit at 100% power,790 mw.
10-3-86 2035 Commenced unit rampdown for refueling outage at 150 mw/hr.
10-4-86 0221 Ger.erator off the line.
10-4-86 0239 Reactor shutdown.
10-5-86 0557 RCS < 3500F/450 psig.
10-5-86 1245 RCS < 200oF 10-8-86 0637 RCS at mid-nozzle.
10-19-86 1842 Rx head removed.
10-23-86 1712 Rx core is defueled.
10-31-86 1631 Commenced fuel on-load.
10-31-86 2400 This reporting period ends with the unit at RSD, core on-load in
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Pcg29 FACIUTY CHANGES REQUIRING NRC APPROVAL MONTH / YEAR OCTOBER 1986 NONE DURING THIS PERIOD 4
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Page 10 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR OCTOBER 1986 UNIT DC 80-31 Post Accident Sampling System - Long Term 1&2 This design change installed a permanent system to provide the capability of obtaining post-accident samples of reactor coolant, reactor containment atmosphere and reactor containment sumps.
Summary of Safety Analysis The system was designed to maintain radiation doses ALARA.
All sample lines were minimized to reduce radiation sources and provisions for flushing and purging back to containment were provided. Piping modifications were made outside of the containment isolation valves thereby preserving the safety-related piping.
DC 82-09 E.Q. Limit Switch Replacement 1
This design change replaced existing limit switches with equivalent switches which have environmental qualifications as set forth in IEEE Std. 323-1974, IEEE Std. 344-1975 and NUREG-0588. The limit switches are associated with the engineered safeguards including containment isolation.
Summary of Safety Analysis This modification did not change the operating parameters of the limit switches or the design basis of the systems or the values for any postulated accident. The modification will provide additional assurance that the limit switches will perform their intended safety function.
DC 84-52 Dry Cask Independent Spent Fuel Storage Installation Safeguards This design change involved the security safeguards systems for the spent fuel storage facility.
Summary of Safety Analysis This system does not involve the operating plant or any of the engineered safeguards.
Page 11 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR OCTOBER 1986 UNIT DC 84-53 Dry Cask Independent Spent Fuel Storage Installation Non-Safeguards This design change was for the construction of the ISFSI including the storage slabs, roads, perimeter fence, emergency diesel electric generating set, lighting and associated duct banks.
Summary of Safety Analysis This modification will not affect the operation of any equipment or system required to mitigate a Design Basis Accident. The construction'is away from the power station and has no effect on the operation of any safety related equipment, system or structure.
DC 84-66 Appendix 'R' Emergency Switchgear Room Ventilation Equipment Isolation I&2 This design change, for a fire that could cause the loss of all three chillers and their associated pumps, will provide a chilled water tie-in to the central air conditioning system, which normally serves the office building. Either of the two chillers of the central A/C system has adequate capacity and was tied mechanically to the Control Room and ESR air handlers.
Summary of Safety Analysis The modification does not modify or alter existing installed equipment. It ensures a means of ventilating the Control Room and ESR for post-fire shutdown conditions.
DC 85-36 Alternate Power Supply for Semi-Vital Buses 1&2 To ensure the availability of each Unit's semi-vital bus, reliable alternate power sources will be provided. This entails provision of separate 480V sources, transformers, manual transfer switches, and associated cable and conduit. It also removes the l
Gai-Tronics System from the vital bus and adds it to the semi-vital bus.
The alternate sources for the semi-vital buses will be powered from the respective Units' H-train Motor Control Center in the Emergency Switchgear Room (lH1-1 and 2H1-1).
Summary of Safety Analysis The operation of safety-related equipment under normal or accident conditions is not affected by this modification. This design change is non-safety related and non-seismic. However, specific components were seismically mounted to prevent damage to safety related equipment.
Pags 12 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR OCTOBER 1986 UNIT DC 85-37 Hydrogen Storage Bottles Replacement 1&2 The existing hydrogen bulk storage facilities are being replaced with nine H2 bottles with a capacity of 8,350 standard cubic feet per bottle. Six of the bottles will be normally filled for H2 supply to the turbine generator and three bottles will be used as reserve make-up H2 supply.
Summary of Safety Analysis The hydrogen storage system is non-safety related, non-seismic. It is located a minimum distance of 50 ft. from existing building structures. The modification will not affect the safety function of any existing equipment and is consistent with the system design basis.
DC-86-02 Emergency Bus U.V. Relay Replacement 2
This design change replaces existing undervoltage and degraded voltage relays in the undervoltage relay panel and adds overvoltage relays to the emergency switchgear.
Summary of Safety Analysis The availability of safety-related equipment fed from the bus being worked on will be impacted during the construction phase of this DCP. Only one bus was worked on at a time. The post-construction phase of this modification does not modify the operation of existing safety-related equipment or systems.
It does, however, ensure the availability of safety-related power systems as designed and currently analyzed in the PSAR.
Page 13 TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH / YEAR OCTOBER 1986 NONE DURING THIS PERIOD TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR OCTOBER 1986 l
NONE DURING THIS PERIOD l
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Page 14
.+
OTHER CHANGES, TEST AND EXPERIMENTS MONTH / YEAR OCTOBER 1986 NONE DURING THIS PERIOD l
l 6
Paga 15 h
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CHEMISTRY REPORT october 19 86 l
UNIT NO. 1 UNIT NO. 2 y
MAX.
MIN.
AVG.
MAX.
MIN.
AVG.
Gross Radioact., uCi/al 1.26E+0 5.32E-1 9.14E-1 2.31E-1 9.47r-a 5.29E-2 Suspended Solids, ppa 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritius, uC1/al 4.41E-1 1.72E-1 3.06E-1 (A)
(A)
(A)
IodinsI3I, uCi/mi 5.38E-3 2.52E-3 3.84E-3 1.54E-4 6.67E-5 1.14E-4 131 I
/1 0.15 0.07 0.11 0.09 0.08 0.08 Hydrogen, cc/kg 32.0 26.1 29.3 26.0 3.l(B) 12.0 (B)
Lithius, ppa 1.78 1.53 1.66 0.45 0.41 0.42 Boron-10, ppa
- 198 182 le7 428 19.6 290 0xygen, (DO), ppe 60.005 40'.005 60.005 8.2(B) 60.005 2.29(B)
Chloride, ppa 0.011 0.002 0.007 0.013 dr0.001 0.005 pH @ 25 degree Celsius 6.49 6.37 6.43 7.03 5.05 5.57
- Boron-10 = Total Boron X 0.196 REMARKS:
Unit One: CAT Bed placed in service on 10-20-26' for Idthiin reeval.
Ib Lithiun additions were nade to Unit One in October.
Unit M :
(A) Eo Trititm nirbers because of shutdown condition.
(B) Unit two cerraenced rartping down for refueling shutdown on 10-03-86 at 2035.
Paga 16 UNIT 1
FUEL HANDLING DATE October 1986 NEW OR DATE NUMBER 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 DURINC THIS PERIOD i
i L-
Paga 17 UNIT 2 FUEL HANDLING DATE October 1986 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC SHIPMENT i RECEIVED PER SHIPMENT I
i ENRICHMENT CASK ACTIVITT LEVEL NONE DURING THIS PERIOD l
Page 18 9
PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR MONTH / YEAR OCTOBER 1986 NONE DURING THIS PERIOD
e 's Pag 319 9
e DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH / YEAR OCTOBER 1986 NONE DURING THIS PERIOD l
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- VIRGINIA ELucTmIC AND Powr.m COMPANY Ricuwoxn, VIRGINIA 202G1 N vember 14, 1986 w.L.sr=waar Vses Pasesosur Nuctuan OramATsons Mr. Ronald M. Scroggins, Director Serial No.
.86-764 Office of Resource Management N0/JDH:dmk U.S. Nuclear Regulatory Commission Docket Nos.
50-280 Washington, D.C. 20555 50-281 License Nos. DPR-32
Dear Mr. Scroggins:
DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT N05. 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos. 1 and 2 for the month of October 1986.
Very truly yours, fhsn4 k
L. Stewart Ynclosure (3 copies) cc: Mr. James M. Taylor, Director (12 copies)
Office of Inspection and Enforcement Dr. J. Nelson Grace (1 copy)
Regional Administrator Region II Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station l
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