ML18152A997
| ML18152A997 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/31/1988 |
| From: | Benson D, Cruden D, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-368, NUDOCS 8806220154 | |
| Download: ML18152A997 (23) | |
Text
POW 34-04
, e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-05 APPROVED: _)t:lAALL, t_ ~~
STA TIONANAGER
e 1 e
SECTION PAGE Operating Data Report - Unit No. l l Operating Data Report - Unit No. 2 2 Unit Shutdowns and Power Reductions - Unit No. l 3 Unit Shutdowns and Power Reductions - Unit No. 2 4 Average Daily Unit Power Level - Unit No. l 5 Average Daily Unit Power Level - Unit No. 2 6 Summary of Operating Experience - Unit No. l 7 Summary of Operating Experience - Unit No. 2 8 Facility Changes Requiring NRC Approval 9 Facility Changes That Did Not Require NRC Approval 10 Procedure or Method of Operation Changes that Did Not 13 Require NRC Approval Procedure or Method of Operation that Did Require NRC Approval 14 Tests and Experiments Requiring NRC Approval 15 Tests and Experiments That Did Not Require NRC Approval 16 Chemistry Report 17 Fuel Handling - Unit No. l 18 Fuel Handling - Unit No. 2 19 Description of Periodic Test Which Were Not Completed Within 20 the Time Limits Specified in Technical Specifications
PAGE 1 e
OPERATING DATA REPORT DOCKET NO. 50-280 DATE 06-07-88 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 OPERATING STATUS
- 1. Unit Name: Surry Unit # 1 Notes
- 2. Reporting Period: May 01-31, 1988 3.
4.
Licensed Thermal Power (MWt):
Nameplate Rating (Gross MWe}:
2441
--'=-=-=-=-------
847.S S. Design Electrical Rating (Net MWe): 788 6.
7.
Maximum Dependable Capacity (Gross MWe):
......;.~---
820 Maximum Dependable Capacity (Net MWe}: _...:.7....;:8;..:l~--
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give 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 3647.0 135359.0
- 12. Number of Hours Reactor Was Critical 0 2312.6 87036.0
- 13. Reactor Reserve Shutdown Hours 0 0 3774.5
- 14. Hours Generator On-Line 0 2297.6 85268.8
- 15. Unit Reserve Shutdown Hours 0 0 3736.2
- 16. Gross Thermal Energy Generated (MWH} 0 5322810.2 198043031.6
- 17. Gross Electrical Energy Generated (MWH} 0 1794685.0 64169858.0
- 18. Net Electrical Energy Generated (IMO 0 1705504.0 60860880.0 19, Unit Service Factor 0 63.7% 63%
- 20. Cnit Available Factor 0 63% 65.8%
- 21. Unit Capacity Factor (Using MDC Net} 0 59.9% ss*.1%
- 22. Unit Capacity Factor (Using DER Net} 0 59.4% 57.1%
- 23.
24.
Unit Forced Rate 0 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each}:
3.3% 17.3%
Refueling: Outa2e 04-08-88 thru 06-24-88
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to COl!BDercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
PAGE 2 e
OPERATING DAIA REPORT DOCKET lfO. 50-281 DAl'E 06/07 /88 COMPLETED BY L. A. Warren TELEPHONE 804-357-3184 OPERAIING SLU'US
- 1. Unit Name: Surry Unit # 2 Notes
- 2. Reporting Period: MayOl-31, 1988 3.
1+.
Licensed Thermal Power (MWt):
---~~------
2441 Nameplate Rating (Gross MWe): -~8.:.4.:..7;:..;.5,.__=-~--
S. Design Electrical Rating (Net MWe): 788
- 6. Maximum Dependable Capacity (Gross MWe): 820
- 7. Maximum Dependable Capacity (Net MWe): 781
- 8. If Changes Occur in Capacity Ratings (Items Number 3 lbrough 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
Ihis Month Yr.-to*Date Cumulative
- 11. Hours In Reporting Period 744.0 3647.0 132239.0
- 12. ~umber of Hours Reactor Was Critical 363.4 3048.2 87714.2
- 13. Reactor Reserve Shutdown Hours 0 0 328. 1 lit. Bours Generator On-Line 363.4 3020.3 86318.6 15, Unit Reserve Shutdown Hours 0 0 0 16, Gross thermal Energy Generated (MWH) 872882. 0 7301877.2 202472239.9
- 17. Gross Electrical Energy Generated (MWH) 290075 2433760.0 65806584.0
- 18. Set Electrical Energy Generated (MWH) 276123 2316598.0 62393075.0
- 19. Unit Service Factor 48.8% 82.8% 65.3%
- 20. ~nit Available Factor 48.8% 82.8% 65.3%
- 21. Unit Capacity Factor (Using MDC Net) 47.5% 81.3% 60.6%
- 22. Unit Capacity Factor (Using DER-Net) 47 .1% 80.6% 59. 9%
- 23. Unit Forced Rate 51.2% 17 .2% 14.5%*
21t. Shutdowns Scheduled Over Next 6 Months (l'ype, Date, and Duration of Each) :
Refueling Outage - 09/02/88, 62 days
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INIIIAL CRinCALI'IY INI'IIAL !LEC'l'RICIIY COHH!RCIAL OP!RAl'ION (9/77)
1-'AGt j 50-280 UNIT S\llTJ'DOWNS AND POWER REDUCTIONS DOCKET NO.
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0 88-05 04-09-88 s 744.0 C 1 Unit shutdown for refueling outage 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data B - Maintenance or Iest 2 - Manual Scram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) File D - Regulatory Reetricti.on 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 UNIT SlllITDOWNS AND POWER REDUCTIONS DOCKET NO. __5_0_-2_8_1_ _ _ _ _ __
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88-07 05-16-88 F 380.6 A 3 Reactor trip by S/G Lo-Lo level signal. e Investigation being performed to determine the reason the turbine governor valves closed causing S/G Lo-Lo level.
1 F: Forced 2
Reason:
3 Method:
4 Exhibit G - Instructions 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- Regulotory Reotriction 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 5 II AVERAGE DAILY UNIT POWER LEVEL DOCICEt NO. 50-280 UNIT
--::=---~----
Surry Unit I I DATE 06/09/88 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 MONTH MA"£ 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0
'3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 2 '3 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 l'3 0 29 0 14 0 '30 0 15 0 '31 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 l e
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-281 UNIT Surry Unit # 2 DAIE 06-09-88 COHPI.El'ED BY L. A. Warren TELEPHONE 804-357-3184 MON'IH MAY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 712 17 0 2 765 18 0 1 776 19 0 4 776 20 0 5 760 21 0 6 761 22 0 7 746 23 0 8 736 24 0 9 758 25 0 10 773 26 0 11 771 27 0 12 768 28 0 13 757 29 0 14 770 30 0 15 768 31 0 16 766 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 e
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR May 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 05-01-88 0000 This reporting period begins with the RCS level at 17 1 standpipe, preparing to start refueling activities.
05-09-88 1410 Reactor head removed from vessel.
05-10-88 1741 Commenced core off-load.
05-12-88 0739 Core is defueled.
05-21-88 2040 Commenced core on-load.
05-23-88 1649 Core on-load completed.
05-29-88 1448 Reactor head set on vessel.
05-31-88 2400 This reporting period ends with the reactor head tensioning in progress.
PAGE 8 e
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR MAY 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 05-01-88 0000 This reporting period begins with the unit at 66% power, 545 MWs while repairing 'A' isolated phase bus duct fan.
0250 Commenced power increase at 150 :MW /hr.
0550 Unit at 100% power, 820 MWs.
05-16-88 0324 Reactor trip caused by S/G Lo-Lo level and turbine trip by Rx trip.
0325 Manually initiated SI due to decreasing pressurizer level.
0333 Declared NOUE due to SI actuation.
0340 Terminated NOUE.
05-17-88 0440 Commenced RCS cooldown to repair blockage in AFW line to 'A' SIG.
0611 Declared NOUE due to mode reduction required by Technical Specification.
1255 RCS at 350°F / 450 psig.
05-18-88 0519 RCS< 200°F.
05-24-88 1523 Declared N OUE due to fire in Unit 2 containment.
1530 Fire extinguished in Unit 2 containr.1.ent.
1643 Terminated NOUE.
05-31-88 2400 This reporting period ends with the unit at CSD on RHR.
PAGE 9 e
F AGILITY CHANGES REQUIRING NRG APPROVAL MONTH/YEAR May 1988
=------
NONE DURING THIS PERIOD
PAGE 10 FACILlTY clNGES THAT DID NOT REQUIRE. APPROVAL MONTH/YEAR MAY 1988 SNSOC MEETING MINUTES 05-03-88 The safety valves for the pressurizer were removed and two pieces of gasket material were placed over the three flanges with four out of eight bolts holding the gasket material in place. The gasket material had a 1/ 4 11 hole in the center. The gasket material would not hold pressure, but would keep dirt out of the safety valve lines.
With the pressurizer safety valves removed at cold shutdown, a pressure relief path is assured. The material placed over the valve flange will not interfere with the relief flow at the safety design pressures.
TM SI-88-46 TEMPORARY MODIFICATION 05-03-88 Temporary modification to wire open damper to 1-VS-F-lA and wire shut dampers to 1-VS-F-lB and lC.
This change does not constitute an unreviewed safety question because the containment air recirculation system is not required to function during design basis accident.
TM Sl-88-48 TEMPORARY MODIFICATION 05-04-88 Temporary modification required to provide a primary grade water supply to Unit 1 Containment with VB 1-ill de-energized, thus causing TV-1519A to fail closed.
The requirements for containment integrity will be met as the jumper will be removed prior to exceeding 200°F. Also refueling conditions integrity required by T.S 3.1 O.A are met as this flowpath does not provide a direct release path from containment atmosphere.
SCAFFOLD REQUEST 05-05-88 Erection of temporary platform scaffold located in Unit 2 safeguards elevation 27' to work 2-MS-176, 178, and 182.
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.
TM Sl-88-54 TEMPORARY MODIFICATION 05-09-88
- Temporary modification wired open the exhaust dampers for 1-VS-F-lA, lB, and lC.
This change does not constitute an unreviewed safety question because the containment air recirculation system is not required to function during design basis events.
e -
FACIIJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR MAY 1988 PAGE 11 SCAFFOLD REQUEST 05-10-88 Erection of temporary scaffold platform located in Containment 27' level to work MOV-RH-l 720A/B.
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 05-10-88 Erection of temporary scaffold platform located in auxiliary building basement to work l-CC-220 (replacement).
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.
TM Sl-88-57 TEMPORARY MODIFICATION 05-12-88 Install jumper hose and teel pump from l-RH-34 to l-DG-60.
Since draining the RHR system to the PDTT is within design specifications of the systems involved and there is no impact on the accident analysis, an unreviewed safety question is not created.
l-OP-63.8 PROCEDURE DEVIATION 05-13-88 This temporary modification removed check valve internals from 1-BD-558 and installed a bonnet adapter and jumper hose to condensate polishing waste neutralization or low conductivity sumps.
The steam generators were at atmospheric pressure during installation of this temporary modification. Therefore, probability of a steam generator tube rupture is not credible. If leakage on the jumper should occur, the release can be terminated immediately by securing the recirculation and transfer pump. Therefore, no unreviewed safety question exists.
RELOAD SAFETY EVALUATION - SURRY 1 CYCLE 10 05-18-88 This report presents an evaluation which demonstrates that the redesigned Cycle 10 core and the use of the Surry improved fuel product in a core design will not adversely ~If ect the safety of the plant during refueling and cold shutdown.
The report concluded that no changes to the Technical Specifications are required and none of the Chapter 14 UFSAR accidents require reanalysis. Further, no unreviewed safety questions exist as a result of operation at Refueling or Cold Shutdown conditions.
PAGE 12 FACILITY C.NGES THAT DID NOT REQUIRE. APPROVAL MONTH/YEAR MAY 1988 TM S2-88-38 TEMPORARY MODIFICATION 05-20-88 This temporary modification removed check valve internals from 2-BD-558 and installed a bonnet adapter and jumper hose to condensate polishing waste neutralization or low conductivity sumps.
The steam generators were at atmospheric pressure during implementation of this jumper. Therefore, the probability of a steam generator tube rupture is not credible. If leakage on the jumper should occur, the release can be terminated immediately by securing the recirculation and transfer pump. Therefore, no unreviewed safety question exists.
TM Sl-88-59 TEMPORARY MODIFICATION 05-26-88 This temporary modification removed check valve internals from 1-BD-558 and installed a bonnet adapter and jumper hose to condensate polishing waste neutralization or low conductivity sumps.
The steam generators were at atmospheric pressure during implementation of this temporary modification. Therefore, the probability of a steam generator tube rupture is not credible. If leakage on the jumper should occur, the release can be terminated immediately by securing the recirculation and transfer pump. Therefore, no unreviewed safety question exists.
TEMPORARY OPERATING PROCEDURE 05-05-88 The change involved the installation of Jumper # 1 (from l-IA-6_90 to 1-SA-18 to supply air to LT-CW-101) and Jumper #2 (from 2-IA-930 to 1-IA-467 to supply air to Unit 1 auxiliary building).
TV-CC-109B, component cooling to residual heat removal heat exchanger will be placed on Appendix 'R' blocking device to assure cooling for RHR. If air is lost to the bubbler (LT-CW-101), the Unit l signal of the two out of two Lo Canal Level turbine trip matrix will be made up, thus failure is in the safe direction. Therefore, an unreviewed safety question is not created.
PAGE 13 e
PROCEDURE OR METHOD OF OPERATION CHANGES e
THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR MAY 1988 UFSAR UPDATE - CHAPTER 8, SECTION 4.1 05-3-88 Update UFSAR, section 8.4.1 to reflect that the H & J bus x-tie breakers (1 SH 1, 25H 1) are installed in their respective cubicles but will be racked out and tagged.
An unreviewed safety question is not involved because the change in breaker location retains the breaker in the open position, racked out and tagged. Valve closure will be under* strict administrative and procedural control.
r:~ 31-45
PAGE 14 EDURE OR METHOD OF OPERA.N AT DID REQUIRE NRG APPROV MONTH/YEAR MAY 1988 NONE DURING THIS PERIOD
PAGE 15 e
TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH/YEAR MAY 1988 NONE DURING THIS PERIOD
PAGE 16 e e TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR MAY 1988 l-ST-213 SPECIAL TEST 05-ll-88 Test to verify operability of the nitrogen back up system to perform its intended function to operate the turbine driven auxiliary feedwater pump air operated valve (S0V-MS-l02A/B) when required.
No concern on 10CFRS0.59/10CFR72.35 review since this test is performed with Unit 1 at cold shutdown when auxiliary feedwater is not required.
2-ST-212 SPECIAL TEST 05-26-88 Test to functionally check relays SZX 1-1 C and SZX 1-12 contacts nine and ten as part of root cause analysis of Unit 2 trip on O5-16-8 8.
No unreviewed safety question exists since there were no plant or electrical modifications made.
2-ST-220 SPECIAL TEST 05-30-88 Test to check speed sensors and power supply to relays 20-0PC-l and 20-0PC-2 while turbine is rolling in speed control (off-line).
No unreviewed safety question exists since no safety related equipment was modified or affected, nor was the plant being operated outside normal constraints.
PAGE 17 e
VIRGINIA .POWER SURRY POWER STATION CHEMISTRY REPORT MAY 19 88 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX. MIN. AVG. MAX. MIN. AVG.
Gross Radioact. 1 ~Ci/ml 5.54E-2 4.14E-3 2.04E-2 2.61E-l 5.99E-l l.88E-2 Suspended Solids, ppm o.o o.o o.o o.o o.o o.o Gross Tritium, ~Ci/ml * *
- 5.66E-2 5.28E-2 5.47E-2 Iodine 131 , ~Ci/ml * *
- 1. 73E-3 2.68E-4 l.32E-3 11 '31 / 11'31 * *
- 0.14 0.05 0.10 Bydroaen, cc/ksz. * *
- 31.2 3.7 14.1 Lithium, ppm * *
- 1.13 0.45 0.60 Boron-IO, ppm* 418.1 391.6 408.1 263.62 16.07 119.78 Oxygen, (DO)
- ppm 5.5 3.0 4.2 0.005 0.005 0.005 Chloride, oom 0.035 0.008 0.016 0.010 0.001 0.004 pH@ 25 degree Celsius 5.40 4.61 4.97 7.02 5. 77 6.47
- Boron-10
- Total Boron X 0.196 REMARKS: *Unit one shutdown for refueling 1 analysis not required. Unit one reactor liquid purification out of service on 5-3 and restarted 5-10 at 1215. 'A' mixed bed taken out of service on 5-17 at 1445 due to color change and high activity. '3B' deborator with a mixed bed charge put in service on 5-21 at 1234.
Reactor liquid purification out of service on 5-27 at 1817 due to low cavity ievel.
Reactor head inplace on 5-30 at 2200. Unit two: started month at 66% and ramped to 100% on 5-1 at 0550. Reactor trip on 5-16 at 0324 and borated to cold shutdown.
Unit on RHR on 5-18 at 0353. LiOH addition on 5-2 at 0605, 150gm; 5-4 at 1230, 160gm; 5-29 at 1510, 1278gm. Monthly total of 1588gm LiOH
- PAGE 18 e e UNIT _.._I_ FUEL HANDLING DATE May 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT # RECEIVED PER SHIPMENT n n ENRICHMENT CASK ACTIVITI LEVEL NONE DUR ING TIITS PE lUOD
- - PAGE 19 UNIT
-- 2 FUEL HANDLING DATE May 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT# PER SHIPMENT I RECEIVED
' ENRICHMENT CASK ACTIVITY LEVEL NONE DUR ING TIIlS Pl RIOD
PAGE 20 e e DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR MAY 1988 NONE DURING THIS PERIOD
,..a y
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 15, 1988 D.S.CRUDEN VICE PRESIDENT-NUCLEAR U. S. Nuclear Regulatory Commission Serial No.88-368 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 I AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of May 1988.
~:.----------------
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