ML18152A859
| ML18152A859 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/29/1988 |
| From: | Benson D, Stewart W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-132, NUDOCS 8803180050 | |
| Download: ML18152A859 (24) | |
Text
POW 34-04
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-02 APPROVED: Jrvvia. LJr/l14D11. .
0 MANAGER 8803180050 880229 PDR ADOCI< 05000280 R DCD
- ./
i SECTION PAGE '
- -*- t 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 Experience - Unit No. 1 7 Summary of Operating Experience - Unit No. 2 8 Facility Changes Requiring NRG Apprqval 9 Facility Changes That Did Not Require NRG Approval 10-12 Procedure or Method of Operation Changes that Did Not Require NRG Approval 13 Procedure or Method of Operation that Did Require NRG Approval 14 Tests and Experiments Requiring NRG Approval 15 Tests and Experiments That Did Not Require NRG Approval 16 Chemistry Report 17 Fuel Handling - Unit No. 1 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
PAGE 1 OF 21
- OPERAl'ING DAU REPOR%
DOClCE'r No.
DAD COHPLnED BY 3/3/88 L. A. Warren
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ttL!PHONE 804-357-3184
- 1. Unit Name: Surry Unit # 1 Notes
- 2. Reportin& Period: February 01-29, 1988
- 3. Licensed thermal Power CHWt): 2441 It. Nameplate Rating (Groaa MWe): 847,5
- 5. Design Eleei:i'ied bting (Nei: MWe) i --:.7..;:8:..:.:B;._..;,_.._ _
- 6. Maximum Dependable Capacity (Gro111 MWe): 820
- 7. Maximwa Dependable Capacity (Net MWe): 781
- 8. If Changes Occur in Capacity Ratings Cltema Humber 3 through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons lor Restrictions, If Any:
?his Month Yr. -to-Date Cumulative ll. Hours In Reporting Period 696.Q 1440 1 0 133152.0
- 12. Number of Bour* Reactor Vas Critical 679~5 1423~5 86146.9
- 13. Reactor Reserve Shutdown Roura o.o o.o 3774.5 1,.. Hours Generator On-Line 672.0 1416.0 . 84387. 2
- 15. Unit Reserve Shutdown Hours o.o 0. 0 . 3736.2
. 16. Gross thermal Energy Generated (MW) 1606034.0 3417744.2 196137965.6
- 17. Gross Electrical Energy Generated (HWH) 542760.0 1157695.0 63532868.0
- 18. Net Electrical Energy Generated (MW) 516-58ft~ Q: . 11Q2405 1 0 60257781.0
- 19. Unit Service Factor .95:~6% 98~3 *% 63.4%
- 20. Unit Available Factor 96.6% ;_98.3 % 66.2 %.
- 21. Unit Capacity Factor (Usina MDC Net) 95% 98% .26f~~ *
- 22. Unit Capacity Factor (Using DER Net) 94.2 97.2% 57*.4%
- 23. Unit Forced Rate 3.4% 1. 7% 17.4%
v.. Shutdowa Scheduled over llext 6 Months (type, Date, and Duration of !acbh Refuelin2 Outage, 4/2/88 - 62 days
- 2S. If Shut Down At !nd Of Report Period Estimated Date of Startups
- 26. Units_ In Teat Status (Prior to CC11111ercial Operationh Forecast Achiev,ed (9/77)
e .e PAGE 2 OF 21 OPERilING DAU REPORT OOClCE? NO. 50-281 DilE 3/3/88 COHPLErED BY L. A. Warren tELEPHONB 804-357-3184
- 1. Unit Name: Surry Unit # 2 Notes
- 2. Reportina Period: February 01-29. 1988
- 3. Licensed 'l'hermal Power CMWt):.
It. Nameplate Rating (Cross MWe):
- 5. Dedsn Electrical l~t!ng (Net !file):
- 6. Kaxillum Dependable Capacity (Groaa MWe):
2441 847.5 788 ____
820
- 7. Maximum Dependable Capacity (Net MWe): 781
- 8. If Changes Occur in Capacity Ratings (Items Humber 3 through 7) Since Last Report, Give Reasona:
- 9. Power Level 'to Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
Thia Month Yr.-to-Date Cumulative
- u. Hours In Reporting Period 696.0 1440.0 130032.0
- 12. Humber of Roura Reactor Was Critical 696.0 1440.0 86106.0
- u. Reactor Reserve Shutdown Bour* 0.0 0.0 328.1
- 14. Hours Generator On-Line 696.0 1440.0 -84738.3
- 15. Unit Reserve Shutdown Boun o.o o.o 0.0
. 16. Gross tberaal Energy Generated (MWB) 1673842.0 3484907.7 198655270.4
- 17. Gross !lectrical Energy Generated (MWB) 557300.0 1163840.0 64536664.0
- 18. Net Electrical Energy Generated (MWB) 530236 ,.o 1107816.0 61184293.0
- 19. Unit Service Factor 100% 100% 65.2%
- 20. Unit Available Pactor 100% 100% 65.2%
- 21. Unit Capacity Factor (Usin& MDC Net) ~z.sz 98.5 6Q. ft,% :-
- 22. Unit Capacity Factor (Using DER Net) 96. 7% 97.6 59:7%
- 23. Unit Forced Rate 0.0% 0.0% 14.2%
v.. Shutdown* Scheduled over lext 6 Hontha (type, Date, and Duration of !acb):
Refu~l1Dg Ql1tag1;: 2£2£66 - ~a da~s
- 25. If Shut Dow At !nd Of Report Period Estimated Date of Startup:
- 26. Units In 'teat Status (Prior to Commercial Operationh Forecast Acbie~ed (q/77\
PAGE 3 OF 21 UNIT SHUIDOWNS AND POWER REDUCTIONS DOCXET No. _ _ s_o-_2_0...,0_ _ _ _ __
UNIT NAME -~S!""u""'!'rry...;.~O-n_l_t_l____
DATE -~3... /3..../_88________
COMPLETED BY -~L.~A~ * ..,.W,,...arr~,..,en______
REPORI K:>NTH FEBRUARY 1988 TELEPHONE __ 8_04_-_35_7_-_3_18_4_ __
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0 88-02 02-06-88 s o.o B 1 Unit was reduced to 7 f'Plo power, 580 MW*s to allow monthly testing of turbine valves (PT-29.1 ).
88-03 02-16-88 F 24.0 G 3 LER-280/ During. performance of .PT-8.1, the Train 88-003 11 B11 P-10 button was pushed when T?'.ain 'A'.
was
- being .*tested causing a NIS Power Range I Lo SP Hi fl~x reactor trip. Corrective action is to ensure proper pre-job briefing and to change some wording in the procedure to give command type steps when referring to which Train to be in*or to go to.
e l 2 3 4
- F: Forced Reason: Method: Exhibit *c - Instructions S: Scheduled A - Equipment Failure (Explain) l - Manual for Preparation of Data B - Maintenance or Test 2
- Manual Sc.ram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) File D ~ Regulatory Restriction 4 - Other (Explain) (NUREG 0161)
E - Operator Training & License Examination 5
F - Administrative Exhibit 1 - Same Source G - Operational Error (Explain)
(9/77) H - Other (Explain)
PAGE 4 OF 21 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME ~~----------
50-281 Surry Unit 2 DATE 3/3/88 COHPLE'J:ED BY L. A. Warren REPORT MONTH FEBRUARY 1988 TELEPH0~:~8:o:4-:3~5~7-:3:1:s:4:::::::
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,Q 88-02 02-20-88 s o.o *B 1 Unit was reduced to 70% power, 580 MW to allow e
monthly testing of turbine valves (PT-29.1) e 1 2 3 4 F: Forced Reasons* Method: Exhibit G - InstTUCtion*
S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance OT Test 2 - Manual Scram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LEll) File D - Regulatory Restriction 4 - Other (Explain) (NUREG 0161)
E - Operator Training & License Examination F - Administrative s Exhibit 1 - Same Source G - Operational Error (Explain)
(9/77) H - Other (Explain)
PAGE 5 OF 21 e e
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- AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _s--'o__-__2__80""-----
UNIT Surrv Unit I DATE 3l3l88 COMPLE'IED BY L~ A~ Warren TELEPHONE 804-357-3184 MONTH F~bruarv f988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 789 17 16.7 2 788 18 561
'3 788 19 787 4 788 20 785 5 789 21 787 6 724 22 788 7 788 23 788 8 785 24 787 9 788 25 788 10 789 26 787 11 790 27 785 12 789 28 787 l'3 788 29 782 14 789 30 15 789 31 16 385 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 b Ut ZI e.
AVERAGE DAILY UNIT POWER LEVEL e
DOCKE'I NO. __5.,.0-......._28__1______
UNIT Surry Unit 2 DATE 3/3/88 COMPLETED BY L; A; warren
?ELEPHONE 804-357-3184 MON'IH Februazy 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 776 17 767 2 778 18 764
'3 777 19 774 4 777 20 606 5 776 21 712 6 775 22 775 7 776 23 776 8 777 24 775 9 777 25 774*
10 776 26 770 11 774 27 671 12 776 28 744 l'3 775 29 771 14 776 '30 15 776 31 16 773 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 OF 21
- e. e
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR FEBRUARY 1988 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 02-01-88 0000 This reporting period begins with the Unit at 100% power, 830 MW s.
02-06-88 1047 Commenced rampdown at 150 MW/hr. for performance of PT-29.1 (turbine valve stroking test).
1258 Holding power at 70%, 580 MW s.
1430 Commenced power increase at 40 MW s/hr.
2101 Unit at 100% power, 830 MW s. .
02-16-88 1143 Rx trip caused by NIS Power Range Lo SP Hi 0, while PT-8.1 was being performed.
- 02-17-88 0410 Rx critical.
1144 Generator on line.
1225 Holding power at 30%, 180 MW s.
1440 Commenced power increase at 150 MW /hr.
1616 Holding power at 57%, 403 Mw* s due to IJ. flux problems.
02-18-88 1113 Commenced slow power increase.
2100
- Unit at 100% power, 825 MW s.
02-29-88 2400 This reporting period ends with the Unit at 100% power, 825 MW s.
PAGE 8 OF 21
. e.
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR FEBRUARY 1988 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 02-01-88 0000 This reporting period begins with the Unit at 100% power; 815 MW s~
02-20-88 0455 Commenced slow power decrease due to losing condenser vacuum.
0515 Holding power at 99%, 800 MW*s~
0712 Commenced power decrease at 150 MW /hr for performance of PT-29.1 (turbine valve stroking test)~
0841 Holding power at 70%, 580 MW s~
02-21-88 0528 Commenced power increase at 150 MW /hr~
0730 Unit at 100% power, 810 MW s.
02-26-88 2230 Commenced power decrease at 15 0 MW /hr to allow removal of 11 1A 11 FW heater.
2315 Holding power at 89%, 720 MW s~
02-28-88 0604 Commenced power increase at 150 MW /hr~
0737 Unit at 100% power, 810 MW s~
02-29 2400 This reporting period ends with the Unit at 100% power; 810 MW s~
PAGE 9 OF 21 e.
F AGILITY CHANGES REQUIRING NRG APPROVAL MONTH/YEAR FEBRUARY 1988 NONE DURING THIS PERIOD
PAGE 10 OF 21 e.
.F ACIUTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR FEBRUARY 1988 T-MOP-2007 REPLACEMENT OF RV-BR-109 02-12-88 This temporary operating procedure involved the temporary hookup of fill and vent hoses from the gas stripper feed heat exchangers (HX) to the overhead gas compressors suction to evacuate the stripper feed HX while RV-BR-109 was replaced.
This change will not have an effect on the volume control tank (VCT) or waste gas decay tank (WGDT) rupture analyses as the gas concentration and release rates are unaffected and no condition exists wherein the relief capacities of the tanks relief devices are exceeded.
TM-Sl-88-3 TEMPORARY CCW MAKEUP SUPPLY FROM PG 02-01-88 A temporary modification connected a hose from a primary grade water service connection to a connection at the component cooling water (CCW) pump suction header in order to work l-CD-372.
Since a source of makeup is provided to CCW system and CCW remains operable and reliable, accidents are not affected or created.
TM-Sl-88-06 TRANSFER OF ION EXCHANGE RESIN 02-23-88 A temporary modification installed a fitting and flexible hose for transfer of ion exchange resin.
This modification does not constitute an unreviewed safety question because its probability of failure was not increased (due to appropriate pressure rating of components and pre-use testing of installation) and consequences of failure are previously evaluated.
TM-S2-88-8 ADMINISTRATIVE CONTROL OF TV-SS-202A & TV-SS-202B 02-02-88 11 This temporary modification failed closed (by lifting solenoid valve leads and isolating instrument air) and placed under administrative control the sample trip valves TV-SS-202 A/B.
No unreviewed safety question exists due to this modification because alternate PASS flowpaths via RHR sample lines, RCS - Loop Hot Leg Sample lines and eves demineralized sample lines will remain available.
PAGE 11 OF 21 e.
FACILJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR FEBRUARY 1988 TM-S .2-88-10
- CORROSION PRODUCT STUDY 02-25-88 A temporary modification installed sampling lines for the following Unit 2 components/systems: A and C blowdown, feedwater, and 2A feedwater heater.
No
- unreviewed safety question exists due to this modification since additional sampling lines do not increase probability of tube rupture and consequences of main steam line rupture are previously analyzed*
. SP-88-08 PLANT COASTDOWN 02-25-88 Setpoints of various plant instruments* were changed to allow an end of cycle plant coastdown.
Accidents and equipment were reviewed for the proposed average temperature. Proposed reduction was within previously reviewed range resulting
- in no unreviewed safety question.
SCAFFOLD REQUEST 02-10-88 A temporary scaffold platform was constructed in the Unit 2 Main Stearn valve house at 27 1 elevation to work on 2-MS-176 (steam supply check valve to 2-FW-P-2).
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
I I
ADMINISTRATIVE CONTROL OF CH HEAT TRACING 02-22-88 !
Heat tracing circuit 2Al-25 (CH) was placed under administrative control to provide increased surveillance of the heat tracing circuit and, if required, manual operation of the circuit to maintain temperature within the required band.
Manual control of CH heat tracing does not constitute an unreviewed safety question because it will be under administrative control ensuring that fluid temperatures are maintained between l 20°F and l B0°F.
PAGE 12 OF 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL e .
MONTH/YEAR FEBRUARY 1988
. SCAFFOLD REQUEST 02-23-88 A temporary scaffold. platform was constructed in the Auxiliary Building at ten feet elevation to work a vertical ladder.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST 02-23-88 A temporary scaffold platform was constructed in the Auxiliary Building at five feet elevation to work on a vertical ladder.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
- SCAFFOLD REQUEST 02-26-88 A temporary scaffold platform was constructed in the Turbine Building Basement .at nine feet elevation to work on 1-CW-MOV-lOOA.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
- e. PAGE 13 OF 21 PROCEDUREORMETHOI> OF-QPERATION-GHANGES THAT-DID NOT-REQUIRE NRG APPROVAL MONTH/YEAR FEBRUARY 1988 EMP-P-RT-13 PROTECTIVE RELAY MAINTENANCE FOR CB I5Hl 02-25-88 A procedure deviation was approved to place the H and J bus cross connect breaker in test to perform the preventive maintenance procedure while at power; Placing the H and J cross_ connect breaker in test while at power will have no effect on the H & -J buses because the breaker will not be placed in the connect position; IMP-C-RPI-32 ROD POSITION INDICATION SYSTEM MAINTENANCE UNIT 2 02-10-88 Procedure deviation to allow use of the Prodac 250 computer to monitor control bank 'B' rod positions during repair of benchboard !RPI.
- Control rod position indication from the P-250 computer is an acceptable substitute for benchboard !RPI provided that T.S. 3~12.E is complied with and duration of substitute is minimized.
MOP-12.4 RETURN OF RM-SS-113 TO SERVICE UNIT-I 02-16-88 Procedure deviation to align blowdown of two steam generators (B & C) through RM-SS-113 which contradicted UFSAR 11;3;3~8; UFSAR 11~3;3~8 states that all three steam generator blowdown flows are through one radiation monitor~
Changing the UFSAR assumed alignment of steam generator blowdown flow through the radiation monitors enhances the ability to detect primary-to-secondary leakage. Therefore; SGTR accident analyses and consequences are not adversely affected;
r--
, PAGE 14 OF 21 I.
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- NONE-(
~
PAGE I 5 OF 21 e.
TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR FEBRUARY 1988 NONE DURING TIITS PERIOD
PAGE 16 OF 21 e.
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR ---=-===:.:.:.=:......;a..;:a...:;..::e---
FEBRUARY 1988 NONE DURING TlllS PERIOD
e PAGE 17 OF 21 VIRGINIA .POWER SURRY POWER STATION CHEMISTRY REPORT February 19 88 PRIMARY COOLANT ANALYSIS UNIT NO. 1 UNIT NO. 2 MAX. MIN. AVG. MAX. MIN. AVG.
Gross Radioact., µCi/ml 1.63 E+( 4. 60 E-1 1.16 E+O 2.43 :8:- 1 1.54 E-1 1.83 E-1 Suspended Solids, DDm o.o o.o o.o o.o p.o o.o Gross Tritium, µCi/ml 6.90 E-2 3.40 E-2 4.60 E-2 1.59 E-1 1.20 E-1 1.40 E-1 131 Iodine , lJCi/ml 9.30 E-l 5.53 E-3 7.08 E-2 f!i..13 E-~ 12.91 E-5 1. 50 E-4 11'31 / 11'31 0.24 0.12 0.18 0.23 k).06 0.10 Hydrogen, cc/kfl. 33.9 25.6 28.3 33.6 ~6.2 29.8 Lithium, ppm 0.63 0.26 0.40 0.90 P.63 0.79 Boron-10, ppm* 43.9 1.18 10.3 69.0 ~2.9 61.5 Oxygen, (DO), ppm 0.005 o.oos 0.005 0.005 p.005 0.005 Chloride, ppm o. 010 0.001 0.006 0.010 0.001 0.007 pH@ 25 de2ree Celsius 7.98 6.65 7.31 6.81 p.56 6.70
- Boron-10
2-18@ 0905 380 g, and 2-19@ 0555 400g for a total LiOH addition of 1360g.
Unit One A Deborating Bed was in service on 2-24 at 2040 until 2-25 0327 for Boron removal; Operations also put A DEB in service as needed for Boron control.
Unit Two: No Lithium additions; Cation Bed in service for Lithium removal on 2-3 from 0600 to 0838 and 2-16 from 2000 - 2237.
PAGE 18 OF 21 e.
DATE FEB 1988 UNIT
--I FUEL HANDLING NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT# RECEIVED PER SHIPMENT (I (I ENRICHMENT CASK ACTIVITI LEVEL NONE DUF ~G TIIlS Pl RIOD
PAGE 19 OF 21 e
UNIT 2* FUEL HANDLING DATE FEB 1988 NEW OR
. ASSEMBLIES PER SHIPMENT ASSEMBLY I ,
ANSI INITIAL ENRICHMENT FUEL SHIPPING CASK ACTIVITI LEVEL NONE DUF ING THIS Pl RIOD
PAGE 20 OF 21 e
PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR MONTH/YEAR FEBRUARY 1988 NONE DURING THIS PERIOD
e
. DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS
- PAGE 21 OF 21 MONTH/YEAR
- -FEBRUARY - - - -1988 ----
NONE DURING TlllS PERIOD
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L.
VICE PRESIDENT STEWART March 15, 1988 NUCLEAR OPERATIONS U. S. Nuclear Regulatory Commission Serial No.88-132 Attention: Document Control Desk NO/DAS: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 1 and 2 for the month of February 1988.
Very truly yours, lJL~W. L. Stewart Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station