ML20211Q329

Monthly Operating Repts for Nov 1986

ML20211Q329
Person / Time
Site:	Surry
Issue date:	11/30/1986
From:	Jones V, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
86-823, NUDOCS 8703030066
Download: ML20211Q329 (25)

Text

. ,. POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 86-11 APPROVED: h _-

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[ 8703030066 861130 1 PDR ADOCK 05000280 R PDH

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,', .- g 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 10-14 Tests and Experiences Requiring NRC Approval 15 Tests and Experiments That Did Not Require NRC Approval 16 Other Changes, Test and Experiments 17 Chemistry Report 18 Fuel Handling - Unit No. I 19 Fuel Handling - Unit No. 2 20 Procedure Revisions That Changed the Operating Mode Described in the FSAR 21 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications. 22

PAGE1 OPERATING DATA REPOTT ,

DocKa NO. Surry # l-50-280 -

DAIR Dec.04,1986 COMP 121ED BY V. H. Jones TE12Pu0nr 804-357-3184 OPERATINC STATUS Unit Name: Surry Unit 1 Notes  :

1.

2. Reporting Period: 11-01-86 to 11-30-86

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3. Licensed Thermal Power (MWt): R

4. Nameplate Rating (Cross MWe): ,,

_ _ 847.5

5. Design Electrical Rating (Net MWe): 788

6. Maximum Dependable Capacity (Cross MWe): 820

7. Maximus Dependable Capacity (Net We): 781 ,

8. If Changes Occur in Capacity Ratings (Items Nasher 3 Through 7) 31nce Last Report, Cive Reasons: N/A , , _ _ _

9. Power Level To Which Restricted, If Any (Net IGle): _.

10. Reasons For Restrictions, If Any:

This Month Tr.-to-Date Cumulative

11. Bours In Reporting Period 720.0 8016.0 122208.0 720.0 5994.2 78306.3

12. Number of Bours Reactor Was Critical 0 / 0 3774.5

13. Reactor Resarve Shutdown Hours ,

720.0 ,. 5776.8 7FA13.3

14. Bours Generator On-Line 0 0 3536.2

15. Unit Reserve Shutdown Bours ,

16. Cross Thermal Ene/sy Generated (MWE) 1756298.0 13511327.0 177493949.7

17. Cross Electrical 2nergy Generated Oers) 593190.0 4531600.0 57303533.0

18. Net Electrical Energy Generated (MWE) 565224.0 ' 4303562.0 54336905.0 100.0 % 72.1% 62.7%

19. Unit Service Factor 100.0 % 72.1% 65.8%

20. Unit Available Factor 100.5 % 68.7 % 57.5%

21. Unit Capacity Factor (Using MDC Met) 99.6% 68.1% 56.4%

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Rate 0 L9% 17_ gg 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duratice of Esch):

04/03/87 - Snubber / Maintenance - 10 davs P

l 25. If Shut Down At End Of Report Period Estinsted Date of Startup l

26. Units In Test Status (Prior to Ccruserciel Operation): Forecast. Achieved l

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i Im m AL CR M CALU T INITIAL IIACIRICITY l c0MERCIAL OFLtATION

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' (9/77)

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PAGE 2 OPERATING DATA REPORT DOCKET No. Surry #2-50-281 DATE Doc 04.1986 l

COMPLETED BY V. H.Tnnes TELEPHONE R0d-357-3184

_ OPERATING STATUS, I. Unit Name:

Surry Unit 2 not,,

2. Reporting Period: 11-01-86 to 11-30-86

3. Licensed Thermal Power (NWt): 2441

4. Nameplate Rating (Cross MWe): 847.5

5. Design Electrical Rating (Net MWe): 788

6. Maximum Dependable Capacity (Cross MWe): 820

7. Maximum Dependable Capacity (Net MWe): 781

8. If Changes Occur in capacity Ratings (Items Number 3 Through 7) Since Last Reput, Cive Reasons

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative 720.0 8016.0 119088.0

11. Bours In Reportir.g Period

12. Number of Hours Reactor Was Critical 16.0 5962.8 77905.5

13. Raaet r Reserve Shutdown Hours 0 0 328.1 0 5913.2 76678.6 l 14. Hours Generator On-Line 0 0 0

15. Unit Reserve Shutdown Bours

16. Cross Thermal Energy Cenerated (NWB) 0 14236880.9 179543911.5

17. Cross Electrical Energy Generated (PsiH) 0 4659535.0 58247839.0

18. Net Electrical Energy Canerated (NWB) 0 4424594.0 55211177.0 0 73.8 % 64.4%

19. Unit Service Factor 0 73.8 % 64.4%

20. Unit Available Factor

21. Unit Capacity Factor (Using MDC Net) 0 70.7 % 59.5%

0 70.0 % 58.8%

22. Unit Capacity Factor (Using DER 5et) 0 7. 9% 13.1%

l. 23. Ibit Forced Rate 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

i- .

25. If Shut Down At End Of Report Period Estimated Date of Startup:

26. Units In Test Status (Prior to Ccussercial Operation): Forecast Achieved i

INITIAL CRITICALITY INITIAL ELECTRICITY C019ERCIAL OPERATION (9/77)

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.,* PAGES AVERAM DAILY WII POWER LEVEL Docker no. 50-280 WIT burry Unit i DATgUecember 4,19db COMPLETED BY V. H. Jones ,

TELEPHONE R04-% 7 '41Rd MONTE November.1986 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 786 17 783-2 786 18 787 3 787 19 789 4 786 20 788 5 786 21 786 6 781 22 786

' 782 23 786 7

783 24 786 8

785 25 784 9

782 26 785 10 784 27 784 11 784 28 781 12 785 29 783 13 788 30 784 g4 l-788 15 16 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) i l

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,. PAGE 6 AVERAG DAILY IRIIT POWElt LIWL D0cxzr no. 50-281 gygg curry un1I 4 DATR7acomhar 4 14R6 C(3tPLETED BY V H.Tnnan 1ELEMIDItt 804-357-3184 nostru November,1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 0 17 0 1

0 18 0 2

0 19 0 3

4 0 20 0 0 21 0 5

i 0 22 0 6

0 23 0 7

0 24 0 8

0 25 0 9

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I 0 16 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 7

SUMMARY

OF OPERATING EXPERIENCE MONTH / YEAR November,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 11-01-86 0000 This reporting period begins with the unit at 100%

power, 820 MW's.

11-30-86 2400 This reporting period ends with the unit at 100 %

power, 820 MW's .

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SUMMARY

OF OPERATING EXPERIENCE MONTH / YEAR / NOVEMBER,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 11-01-86 0000. This reporting period begins with the unit at RSD, core on-load in progress.

Il-03-86 0530 Core on-load completed.

Il-07-86 0010 Rx head is set on Rx vessel.

Il-16-86 0538 Completed RCS fill and vent.

11-17-86 2335 Commenced Type 'A' test.

11-20-86 2144 Completed Type "A" test.

I1-27-86 1528 RCS > 200oF.

Il-28-86 0312 RCS > 350oF/450 psig.

Il-29-86 2002 Completed hot rod drops.

Il-30-86 0755 Rx critical, commenced physics testing.

Il-30-86 2400 This reporting period ends with physics testing in progress.

PAGE 9 FACILITY CHANGES REQUIRING NRC APPROVAL MONTH / YEAR NOVEMBER,1986

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DC 86-12 Large Bore Snubber Leak Before Break Modifications 2 This design change eliminates six large bore snubbers in each of the three reactor coolant loops, and two small bore snubbers on the diagonals of each RCP support.

Summary of Safety Analysis The deletion of the large bore snubbers eliminates a source of occupational exposure and facilitates maintenance and inservice inspections of piping and components by reducing plant congestion.

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I PAGE 10 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR NOVEMBER 1986 )

UNIT DC 80-49E Technical Support Center Electrical Installation 1&2 This design change installed the electrical power sources and system, including the uninterruptible power supply.

Summary of Safety Analysis The installation does not affect normal station operation or the operation of any safety related equipment.

DC 83-33 Excore Neutron Flux Monitoring System 1 Two redundant channels of monitors were installed, each powered by independent Class IE power sources to satisfy R.G.I.97 requirements. The system provides Source Range Indication over a range of 0.1 to 10 CPS 5 and Wide Range Indication over a range of 10-8 to 200% of full power. To satisfy appendix R requirements, channel I will have an additional power source for use in a fire.

Summary of Safety Analysis The system provides information to be used following a Design Basis Event or fires. Neutron flux is measured from wells in the Neutron Shield Tank. All operations take place outside the primary system. Safety related and non-safety related portions of the system are supplied by lE power sources.

Non-safety related portions are isolated from safety related portions by the Gamma-Metrics Signal Processors. Safety related portions are seismically qualified and supported.

DC 83-34 Excore Neutron Flux Monitoring System 2 l

l Two redundant channels of monitors were installed, each powered by independent Class IE power sources to satisfy R.G.I.97 requirements. The system provides Source Range Indication over a range of 0.1 to 100 CPS and Wide Range Indication over a range of 10-8 to 200% of full power. To satisfy appendix R requirements, channel I will have an additional power source for use in a fire.

Summary of Safety Analysis

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l The system provides information to be used following a Design l Basis Event or fires. Neutron flux is measured from wells in l the Neutron Shield Tank. All operations take place outside l the primary system. Safety related and non-safety related portions of the system are supplied by lE power sources.

Non-safety related portions are isolated from safety related portions by the Gamma-Metrics Signal Processors. Safety related portions are seismically qualified and suppcrted.

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. PAGE ll Corr 2cted Copy FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR NOVEMBER 1986 UNIT DC 83-39B Appendix 'R' Emergency Diesel Generator Mods 2 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.

DC 84-33 R.G.1.97 Containment Fan Heat Removal and Component 2 Cooling Instrumentation Modifications This modification replaces existing and adds new RTO's and flow transmitters.

Summary of Safety Analysis The new and replacement instrumentation satisfies R.G.I.97 requirements, is environmentally and seismically qualified, and thus provides a reliable means of monitoring station operation during and after a design basis event.

DC 84-35 Main Steam Safety Valve Position Indications 2 This design change installs flow sensors, with temperature flow probes, at each main steam safety valve. It also installs a new multiplexer and power supply local to the remote flow switch electronics.

Summary of Safety Analysis This modification adds flow switches for main steam safety valve position indication for assessment of safety systems operation and post-accident monitoring.

, '- . PAGE 12 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR NOVEMBER 1986 UNIT Pressurizer Instrumentation 2 DC 84-41 This design change replaces the existing temperature element with a dual element resistance temperature detector (RTD).

Summary of Safety Analysis The replacement of the single element RTD with an environmentally and seismically qualified dual element RTD provides the operator with redundant information to assess the operation of safety systems.

Snubber Replacement and Elimination 2 DC 84-55 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 no 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.

Containment Sump Trip Valves Replacement 2 DC 85-20 The containment sump trip valves have been a continual problem during Type A and Type C containment leak testing.

This design change replaces the existing globe valves with air operated ball valves.

Summary of Safety Analysis This design change is an enhancement over the existing equipment because it reduces the leakage rate of these valves to well within the established allowable range, thus improving the overall containment leakage rate.

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PAGE13 py FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR NOVEMBER 1986 UNIT DC 85-22 RCP Thermal Barrier CCW System Modification 2 This design change installs check valves, trip valves, and relief valves on the component cooling water (CCW) return header.

Installation of these valves prevents overpressurization and contamination of the CCW system.

Summary of Safety Analysis The installation of the valves and controlinstrumentation will provide Station Operations with automatic isolation of the leaking reactor coolant pump (RCP) and will not require unit shutdown. This modification will prevent overpressurization and contamination of the CCW system.

DC 85-23 Modifications for Fue1 Shipment 2 This design change modified the decontamination building to facilitate spent fuel handling. A 12 inch-thick masonry wall was installed for shielding of workers, a clean change room was provided, lighting fixtures, devices, conduit and associated wiring were relocated accordingly.

Summary of Safety Analysis The modifications covered by this design change are not safety related and will not affect the design basis, function, or operating conditions of any equipment important to safety.

DC 85-2E Feedwater Heater Replacement (Phase I- 5th and 6th Pt. Tube 2 Bundle Replacement)

This design change replacos the fifth and sixth point feedwater heater tube bundles and tubeside relief valves.

Summary of Safety Analysis This modification will improve system performance and increase heater life. The operation of safety-related equipment under normal or accident conditions is not affected by this design change.

'6 PAGE14 Corrected Copy FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR NOVEMBER 1986 UNIT DC 85-30 Safety Injection Leakage Monitoring 2 This design chang,e installed a leakage monitoring tubing between the two check valves in the safety injection piping which connects to each of the Reactor Coolant System cold legs.

Summary of Safety Analysis The tubing was designed and installed in accordance with the appropriate codes and standards, and is seismically supported.

The modification improves the reliability of leakage monitoring and failure of the 3/4" tubing would result in an insignificant amount of leakage and is within the previous analysis.

DC 86-06 PORV Modification 2 This design change removes solenoid valves, modifies tubing, and rewires the PORV control circuits at the main control boards.

Summary of Safety Analysis This modification will provide RCS overpressure mitigation through QA Category I, Class IE, seismically and environmentally qualified components.

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' PAGE 15 TESTS AND EXPERIENCES REQUIRING NRC APPROVAL MONTH / YEAR NOVEMBER,1986 NONE DURING THIS PERIOD

PAGE 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR NOVEMBER,1986 NONE DURING THIS PERIOD I

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-- - - - . _ . , . . . - . , . , , . - _ . _ , _ . _ _ y --_ _ _ ,_.- , _ _ , , , _ _ _ , _ , . - , . . _ _ , __ _ _ - .

PAGE 17 4

OTHER CHANGES, TEST AND EXPERIMENTS 1 MONTH / YEAR NOVEMBER,1986 i

NONE DURING THIS PERIOD i

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• - PAGE 18 VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT Novmber 19 L PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX. MIN. AVG. MAX. MIN. AVG.

Gross Radioact., uCi/ml 1.84 7.30E-1 1.08 1.54E-1 7.32E-4 2.21E-2 Suspended Solids, ppa 0.0 0.0 0.0 - --- ---

Gross Tritium, uCi/ml 3.25E-1 1.27E-1 2.49E-1 3.47E-2 3.47E-2 2.63E-1 131 , uCi/ml 6.40E-3 3.32E-3 4.31E-3 (A) (A) (A)

Iodine 0.19 0.09 0.12 (7) (A)

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/1 131 (A) 34.4 28.2 31.2 25.6 25.6 25.6 Hydrogen, cc/kg 1.65 1.42 1.52 3.59 1.06 2.26 Lithium, ppm 183 169 176 43P 314 416 Boron-10, ppm

• 0.005 0.0D5 0.005 4.0 0.005 2.18 0xygen, (DO), ppm 0.010 0.001 0.002 0.010 0.001 0.002 Chloride, ppm 6.55 5.53 6.44 6.38 4.68 5.39 pH @ 25 degree Celsius

• Boron-10 = Total Boron X 0.196 REMARKS: Unit One - A total of 326 crams of LiGI was added to Unit One.

The CAT Ded was not olaced in service durino t'ovmber.

f Unit Two - 6.5 gallons of Efydrazine was added on 11-24-E6 for oxycen rmoval orior to start-uo. A total of 6475 crarns LiOFI was added to Unit '1ko in preparation for start-un.

(A) The Iodine 131 and the Iodine ratio values are not annlic-able durina shutdown conditions.

• PAGE 19 UNIT I FUEL HANDLING DATE Nov.1986 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT f RECEIVED PER SHIPMENT f f ENRICHMENT CASK ACTIVITY LEVEL NONE DURING THIS PERIOE e

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. .i PAGE 20 UNIT 7 FUEL HANDLING DATE Nov.1986 DATE NUMBER OF NEW OR SPENT NEW OR SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING RECEIVED PER SHIPMENT f f ENRICHMENT CASK ACTIVITT SHIPMENT #

LEVEL NONE DURING THIS PERIOD e

.* PAGE 21 PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR MONTH / YEAR NOVEMBER,1986 NONE DURING THIS PERIOD

- , - - - - - . - - - . -. . . , _ , - - . , - - - - , - - - .._,_..c,, -. . ,.

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., d PAGE 22 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH / YEAR NOVEMBER,1986 NONE DURING THIS PERIOD i

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VINGINIA ELECTRIC AND POWEN COMPANY R icit w o x u , V x n o ix tA 2 0 2 6 1 December 15, 1986 W.L.STEWANT vice Passinant NUCLEAR opmEATBOwB Mr. Ronald M. Scroggins, Director Serial No.86-823 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 NOS. 1 AND 2 M')NTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos. I and 2 for the month of November 1986.

Very truly yours, 3 &%

k. L. Stewart nelosure (3 copies) l.

cc: Mr. James M. Taylor, Director (12 copies)

Office of Inspection and Enforcement i Dr. J. Nelson Grace (1 copy) l Regional Administrator Region 11 Mr. W. E. Holland l NRC Senior Resident Inspector Surry Power Station

.