ML18153C365
| ML18153C365 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/31/1990 |
| From: | Stewart W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-559, NUDOCS 9009250296 | |
| Download: ML18153C365 (23) | |
Text
"*. '.
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 17, 1990 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.
NO/RPC:vlh Docket Nos.
License Nos.90-559 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of August 1990.
W. L. Ste art Senior Vice President - Nuclear 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
(
-POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT#
90-08 APPROVED:
TABLE OF CONTENTS SECTION Operating Data Report - Unit No. 1 Operating Data Report - Unit No. 2 Unit Shutdowns and Power Reductions - Unit No. 1 Unit Shutdowns and Power Reductions - Unit No. 2 Average Daily Unit Power Level
- Unit No. 1 Average Daily Unit Power Level
- Unit No. 2 Summary of Operating Experience - Unit No. 1 Summary of Operating Experience - Unit No. 2 Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval Tests and Experiments That Did Not Require NRC Approval Chemistry Report Fuel Handling - Unit No. 1 Fuel Handling - Unit No. 2 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1
2 3
4 6
7 8
9 13 15 16 17 18 18 20
/
OPERATING DATA REPORT DOCKET NO.:
50-280 DATE: -0;....;9,....,/~05;....:/,..,,.9-=-o -----
COMPLETED BY:
L.A. Warren TELEPHONE: ~(8=0..;,..4).....,,3=5=-7_-=3:":'"18.,....4:--x3=5=5~
OPERATING STATUS NOTES
- 1. Unit Name:
Surry Unit 1
- 2. Reporting Period: AUG. 01-31, 1990
- 3. Licensed Thermal Power (MWt):2441
- 4. Nameplate Rating (Gross MWe):847.5
- 5. 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 Through 7) Since Last Report, Give Reasons: -----------------------
- 9. Power Level To Which Restricted, If Any (Net MWe): -----------
- 10. Reason For Restrictions, If Any: -------------------
THIS MONTH YTD CUMULATIVE
- 11. Hours In Reporting Period 744.0 5831.0 155087.0
- 12. Number of Hours Reactor Was Critical 744.0 5540.7 98291.5
- 13. Reactor Reserve Shutdown Hours O
O 3774.5
- 14. Hours Generator On-Line 744.0 5527.0 96350.2
- 15. Unit Reserve Shutdown Hours O
O 3736.2
- 16. Gross Thermal Energy Generated (MWH) 1614105.0 13126098.5 224242901.5
- 17. Gross Electrical Energy Generated (MWH) 519855.0 4385225.0 72930628.0
- 18. Net Electrical Energy Generated (MWH) 490754.0 4168041.0 69178971.0
- 19. Unit Service Factor 100%
94.8%
62.1%
- 20. Unit Availability Factor 100%
94.8%
64.5%
- 21. Unit Capacity Factor (Using MDC Net) 84.5%
91.5%
57.6%
- 22. Unit Capacity Factor (Using DER Net) 83.7%
90.7%
56.6%
- 23. Unit Forced Outage Rate O
5.2%
20.8%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling/Snubber Outage scheduled to begin 10/05/90, 62 days
- 25. If Shut Down at End of Report Period Estimated Date of Startup:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAsT*-----=-A-=-cH,..,..,I=-=E=v=ED=--
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1
OPERATING DATA REPORT DOCKET NO.:
50-281 DATE: -0=9.-.,;=05..-;=9=0-----
COMPLETED BY:
L.A. Warren TELEPHONE:.....:;.;(8,..;.,,;0..;..4.....;,)3;..;,,5-=-7---=3,.,,:.1_84-x3_5_5~
OPERATING STATUS NOTES
- 1. Unit Name:
Surry Unit 2
- 2. Reporting Period: AUG. 01-31, 1990
- 3. Licensed Thermal Power (MWt):2441
- 4. Nameplate Rating (Gross MWe):847.5
- 5. 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 Through 7) Since Last Report, Give Reasons: -----------------------
- 9. Power Level To Which Restricted, If Any (Net MWe): -----------
- 10. Reason For Restrictions, If Any: -------------------
THIS MONTH YTD CUMULATIVE
- 11. Hours In Reporting Period 744.0 5831.0 151967.0
- 12. Number of Hours Reactor Was Critical 714.2 5655.2 96853.8
- 13. Reactor Reserve Shutdown Hours 0
0 328.1
- 14. Hours Generator On-Line 707.4 5637.7 95286.6
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1632315.0 13429538.3 223039873.1
- 17. Gross Electrical Energy Generated (MWH) 526780.0 4460065.0 72540664.0
- 18. Net Electrical Energy Generated (MWH) 498085.0 4237471. 0 68778430. 0
- 19. Unit Service Factor 95.1%
96.7%
62.7%
- 20. Unit Availability Factor 95.1%
96.7%
62.7%
- 21. Unit Capacity Factor (Using MDC Net) 85.7%
93%
58.1%
- 22. Unit Capacity Factor (Using DER Net) 85.0%
92.2%
57.4%
- 23. Unit Forced Outage Rate 4.9%
3.3%
15.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Dura ti on of Each):
- 25. If Shut Down at End of Report Period Estimated Date of Startup:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST'-----..-A=cR..... I.... E...,.V"'"'ED,.---
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2
DATE (1)
F:
Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTION (Equal To or Greater Than 20%)
REPORT MONTH:
AUGUST 1990 METHOD OF LICENSEE DURATION SHUTTING EVENT SYSTEM COMPONENT TYPE(l)
(HOURS)
REASON(2) DOWN REACTOR(3) REPORT# C0DE(4)
CODE(5)
NONE DURING THIS REPORTING PERIOD (2)
REASON:
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain) 3 (3)
METHOD:
1 - Manual 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain)
DOCKET NO.:
50-280
--=----,.,,-.,,..,,.-..----'---
UN IT NAME:
Surry Unit 1 DATE:
09/05/90 COMPLETED BY:
L.A. Warren TELEPHONE:
804-357-3184 x355 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE (4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)
File (NUREG 0161)
(5)
Exhibit 1 - Same Source
DATE 08/05/90 08/06/90 08/08/90 08/11/90 08/17/90 (I}
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTION (Equal To or Greater Than 20%)
REPORT MONTH:
AUGUST 1990 METHOD OF LICENSEE DURATION SHUTTING EVENT SYSTEM COMPONENT TYPE(!)
(HOURS)
REAS0N(2) DOWN REACTOR(3) REPORT#
CODE(4)
C0DE(5) s s
s s
s 0
0 0
0 0
(2)
REASON:
B 4
B 4
B 4
B 4
B 4
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction N/A N/A N/A N/A N/A E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain)
METHOD:
1 - Manual HX HX HX HX HX 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain) 4 DOCKET NO.:
50-281 UNIT NAME:
Surry Unit 2 DATE:
09/05/90 COMPLETED BY:
L.A. Warren TELEPHONE:
804-357-3184 x355 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE Ramped the Unit to 75% powe~
maintain condenser vacuum wh e
cleaning the waterboxes.
Ramped the Unit to 55% power to maintain condenser vacuum while cleaning the waterboxes.
Ramped the Unit to 80% power to maintain condenser vacuum while cleaning the waterboxes Ramped the Unit 63% power to maintain condenser vacuum while cleaning the waterboxes.
Ramped the Unit to 67.7% po~
to maintain condenser vac while cleaning the waterboxes.
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)
File (NUREG 0161)
(5)
Exhibit 1 - Same Source
DATE 08/27/90 08/29/90 (1)
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTION (Equal To or Greater Than 20%)
REPORT MONTH:
AUGUST 1990 METHOD OF LICENSEE DURATION SHUTTING EVENT SYSTEM COMPONENT TYPE{l)
(HOURS)
REASON{2) DOWN REACTOR(3) REPORT#
CODE{4)
CODE{5)
F F
36.6 A
I 2-90-04 SJ FCV 0
(2)
REASON:
A 4
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction N/A E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other {Explain) 5 SN (3)
METHOD:
1 - Manual HX 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain)
DOCKET NO.:
50-281
-=---....~--=---
UNIT NAME:
Surry Unit 2 DATE:
09/05/90 COMPLETED BY:
L.A. Warren TELEPHONE:
804-357-3184 x355 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE Manually tripped the reactor due to failure of 1A 1
main f~
regulator valve (1-FW-FCV-254-,,,,:
Failure of the valve was due to insertion of test board into MUX unit which caused a short in the valve control circuit.
Ramped the Unit from 86% to 60%
power to reseat lifting first point feedwater heater relief valve.
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)
File (NUREG 0161)
(5)
Exhibit 1 - Same Source
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:
50-280 UNIT NAME:
Surry Unit 1 DATE:
09/05/90 COMPLETED BY:
L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH:
AUGUST 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 735 17 656 2
736 18 645 3
733 19 636 4
743 20 640 5
746 21 636 6
731 22 631 7
726 23 622 8
719 24 618 9
715 25 609 10 702 26 612 11 679 27 603 12 675 28 594 13 666 29 587 14 656 30 582 15 649 31 585 16 581 INSTRUCTIONS Listed above for each day in the reporting month is the average daily unit power level in MWe-Net computed to the nearest whole megawatt.
6
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:
50-281 UNIT NAME:
Surry Unit 2 DATE:
09/05/90 COMPLETED BY:
L.A. Warren TELEPHONE:(804J357-3184 x355 MONTH:
AUGUST 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 741 17 693 2
715 18 678 3
746 19 710 4
742 20 754 5
690 21 741 6
746 22 762 7
683 23 742 8
723 24 764 9
741 25 756 10 709 26 757 11 667 27 298 12 690 28 14 13 648 29 452 14 626 30 699 15 675 31 652 16 744 INSTRUCTIONS Listed above for each day in the reporting month is the average daily unit power level in MWe-Net computed to the nearest whole megawatt.
7
I __ _
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
AUGUST 1990 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 08/01/90 0000 This reporting period started with the Unit operating at 94%
power, 740 MW.
0015 Started slow ramp up; 94% power, 740 MW.
0405 Stopped ramp; 99.1% power, 770 MW.
08/05/90 1805 08/15/90 2328 08/16/90 0158 Primary coolant boron concentration is 'O' ppm; commence Unit coastdown; 99% power, 770 MW.
Started ramp down to clean waterboxes; 89% power, 680 MW.
Stopped ramp; 73.5% power, 520 MW.
0545 Started slow ramp up; 72% power, 525 MW.
2111 Stopped ramp and resumed Unit coastdown, 96% power, 750 MW.
08/31/90 2400 This reporting period ended with the Unit coasting down; 77.8% power, 620 MW.
8
SUMMARY
OF OPERATING EXPERIENCE MONlll/YEAR:
AUGUST 1990 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 08/01/90 0000 This reporting period started with the Unit operating at 100% power, 785 MW.
2324 Started ramp down to clean waterboxes; 100% power, 775 MW.
08/02/90 0517 Stopped ramp; 90% power, 705 MW.
0611 Started ramp up; 90%, 705 MW.
0749 Stopped ramp; 100% power, 800 MW.
08/05/90 1113 Started ramp down to clean waterboxes; 100% power, 780 MW.
1400 Stopped ramp; 76% power, 580 MW.
1736 Started ramp up; 75% power, 575 MW.
2015 Stopped ramp; 100% power, 795 MW.
08/06/90 2233 08/07/90 0301 Started ramp down to clean waterboxes; 100% power, 780 MW.
Stopped ramp; 55.5% power, 395 MW.
0340 Started ramp up; 55.5% power, 395 MW.
0715 Stopped ramp; 100% power, 800 MW.
08/08/90 0018 Started ramp down to clean waterboxes; 100% power, 775 MW.
0208 Stopped ramp; 81% power, 630 MW.
0420 Started ramp up; 81% power, 630 MW.
0620 Stopped ramp; 100% power; 800 MW.
08/09/90 2213 Started ramp down to clean waterboxes; 100% power, 775 MW.
2350 Stopped ramp; 80% power, 630 MW.
9
e
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
AUGUST 1990 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 08/10/90 0353 Started ramp up; 80% power, 630 MW.
0640 Stopped ramp; 100% power, 800 MW.
2230 Started ramp down to clean waterboxes; 100% power, 790 MW.
08/11/90 0145 Stopped ramp; 63% power, 480 MW.
0400 Started ramp up; 63% power, 480 MW.
0635 Stopped ramp; 100% power, 780 MW.
08/12/90 1156 Started ramp down to maintain condenser vacuum; 100% power, 775 MW.
1521 Stopped ramp; 88.5% power, 680 MW.
08/13/90 0305 Started ramp up; 89.5% power, 695 MW.
0330 Stopped ramp; 93% power, 720 MW.
1138 Started ramp down to maintain condenser vacuum; 93%
- power, 720 MW.
1530 Stopped ramp; 86% power, 670 MW.
08/14/90 0351 Started ramp up; 87% power, 680 MW.
0420 Stopped ramp; 92% power, 705 MW.
1215 Started ramp down to maintain condenser vacuum; 91% power, 705 MW.
1550 Stopped ramp; 82% power, 640 MW.
08/15/90 0435 Ramped up from 84% power, 655 MW to 87% power, 670 MW.
1259 Started ramp up; 86% power, 660 MW.
1357 Stopped ramp; 100% power, 795 MW.
10
e
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
AUGUST 1990 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 08/17/90 1200 Started ramp down to clean waterboxes; 100% power, 775 MW.
2340 Stopped ramp; 67.7% power, 500 MW.
08/18/90 0418 Started ramp up; 67.5% power, 520 MW.
0746 Stopped ramp; 100% power, 800 MW.
2346 Started ramp down to clean waterboxes; 99.5% power, 775 MW.
08/19/90 0131 Stopped ramp; 84% power, 650 MW.
0719 Started ramp up; 84% power, 650 MW.
0828 Stopped ramp; 100% power, 800 MW.
08/20/90 2342 Started ramp down to clean waterboxes; 100% power, 795 MW.
08/21/90 0033 Stopped ramp; 89% power, 710 MW.
0445 Started ramp up; 89% power, 700 MW.
0520 Stopped ramped; 100% power, 800 MW.
08/22/90 0025 Started ramp down to clean waterboxes; 100% power, 800 MW.
0113 Stopped ramp; 88% power, 670 MW.
0434 Started ramp up; 88% power, 685 MW.
0602 Stopped ramp; 100% power, 805 MW.
08/27/90 0925 Reactor tripped manually due to failure of 02-FW-FCV-254A,
(
1A 1 main feed regulator valve); 100% power, 805 MW.
08/28/90 1511 Reactor critical.
2200 Unit on line and ramping up.
11
- ((...
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: ~-A_UG_U_S_T_l_99_0~~~
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 08/29/90 0504 0508 0520 0900 1058 1115 1342 Stopped ramp due to lifting of 1st point feedwater heater relief valve; 77% power, 630 MW.
Started ramping down to reseat relief valve; 77% power, 630 MW.
Stopped ramp, relief valve reseated; 74% power, 610 MW.
Started ramp up; 74% power, 605 MW.
Stopped ramp up and started ramp down due to 1st point feedwater heater lifting; 86% power, 680 MW.
Stopped ramp; 60% power, 490 MW.
Experienced perturbations in turbine performance, i.e.
governor valve swings of 10%; swapped turbine control from "operator auto" and "imp in" to "turbine manual" and "imp out"; unit went to 55% power, 440 MW.
2223 Started ramp up; 55% power, 440 MW.
08/30/90 0435 Stopped ramp; 100% power, 785 MW.
2308 Started ramp down to clean waterboxes; 100% power, 785 MW.
2343 Stopped ramp; 90% power, 710 MW.
08/31/90 1608 Started ramp down to maintain condenser vacuum; 87%
- power, 680 MW.
1645 Stopped ramp; 81.5% power, 630 MW.
1800 Started ramp up after finding and repairing tube leak in 1A 1
waterbox. 81.5% power, 630 MW.
2315 Stopped ramp; 96.5% power, 775 MW.
2400 This reporting period ended with the Unit operating at 96.1%
power, 775 MW.
12
11(**.
DC 89-06-03 TM-Sl-90-018 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
AUGUST 1990 RADIOLOGICAL/METEOROLOGICAL COMPUTER REPLACEMENT DESIGN CHANGE STATUS FOR NRC REPORT As a result of recent studies conducted by Virginia Electric and Power Company and NRC inspections, several deficiencies were identified with the current Class 1A1 Radiological/Meteorological Dose Assessment Model (RAD/MET) computer code and Emergency Plan Implementing Procedures developed by the Company.
To rectify the problems, a new computer system (hardware and software) for dose assessment was installed.
The new dose assessment program has been executed on a dedicated RAD/MET computer system installed in the Technical Support Center computer room which is linked to workstations and/or peripheral equipment located in the TSC Dose Assessment office and programming room, the Health Physics Shift Supervisors*
office, the Local Emergency Operating Facility and the Corporate Emergency Operating Facility.
This design change installed a state of the art computer system and software dedicated to dose assessment modelling, and which will execute the new Dose Assessment Class 1A 1
Model.
This system enhances the current dose assessment modelling capability. The design change does not affect the operation of a safety-related system or components or the availability of any safety-related power source.
TEMPORARY MODIFICATION (Safety Evaluation #90-0194) 08/02/90 The disk of valve 1-CS-51 became separated from the stem; the disk was removed to allow recirculation of l-CS-TK-2.
Valve 1-CS-51 serves a safety related function since its body forms part of the piping system for the containment spray system and a non-safety related function as isolation for the caustic addition tank recirculation pump.
Since removal of the disc only eliminates the non-safety related function, this temporary modification does not create an unreviewed safety question.
13
AC-S2-90-0818 AC-Sl-90-0821 SPS 1 CYCLE lOA FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
AUGUST 1990 ADMINISTRATIVE CONTROL (Safety Evaluation #90-0201) 08/18/90 Administrative Control to ensure that containment integrity can be maintained in accordance with the T.S. 1.0 definition with the outside Instrument Air supply manual isolation valves open.
Administrative Control over valves 2-SA-81 and 2-SA-82 in accordance with SUADM-0-26 ensures the ability to maintain containment integrity as defined in Technical Specifications. The administrative control requires that the valves be closed upon notification by the main control room.
In addition, control over the valves will ensure the ability to maintain the containment partial pressure within the limits established T.S. 3.8.
Therefore, an unreviewed safety question is not created.
ADMINISTRATIVE CONTROL (Safety Evaluation #90-0212) 08/21/90 Administrative Control to ensure that the main control room (MCR) pressure envelope can be maintained.
The SA supply valve to the #2 emergency switchgear room (l-SA-226), must be maintained under administrative control when the valve is open.
Administrative control over l-SA-226 in accordance with SUADM-0-26 ensures the ability to maintain the MCR/ESGR pressure boundary in the event of a radioactivity release.
The valve will be closed upon notification by the MCR.
In addition, control over the valve will ensure the ability to maintain the pressure boundary thus maintaining operability of the MCR air bottle dump system. Therefore, an unreviewed safety question is not created.
RELOAD SAFETY EVALUATION (PATTERN ML) LICENSE BURNUP.
LIMIT EXTENSION 08/23/90 (Safety Evaluation #90-0217)
This change is to permit operation beyond the current cycle burnup limit of 15,000 MWD/MTU; the new cycle burnup limit is 16,900 MWD/MTU.
The impact of extended operation of the Surry 1 Cycle lOA reload core has been evaluated. Details of this evaluation are provided in the Nuclear Analysis and Fuel Technical Report NE-793.
14
PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
AUGUST 1990 NONE DURING THIS REPORTING PERIOD 15
{.. ;.
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
AUGUST 1990 NONE DURING THIS REPORTING PERIOD 16
{
~*.-.*
e VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR:
AUGUST 1990 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX.
MIN.
AVG.
MAX.
MIN.
AVG.
Gross Radioact., µCi/ml 1.06EO 7.78E-1 8.98E-1 2.90E-1
- 2. llE-2 2.15E-1 Suspended Solids, ppm 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, µCi/ml 8.93E-2 8.18E-2 8.64E-2 2.59E-1 1.69E-1
- 1. 86E-l Iodine-131, µCi/ml
- 1. 05E-2 5.52E-3 7.74E-3 6.34E-3 3.73E-4 9.42E-4 Iodine-131/Iodine-133 0.18 0.14 0.16 0.14 0.07 0.10 Hydrogen, cc/kg 33.6 25.5 30.4 32.7 25.6 30.6 Lithium, ppm 0.88 0.70 0.77 2.35 2.05 2.22 Boron - 10, ppm*
4.70 0.20 0.42 129.8 72.1 86.1
~0.005
~0.005
~0.005
~0.005
~a. 005
-ifQ.005 Oxygen, (DO), ppm 0.008
~0.001 0.003 0.006 0.003 0.005 Chloride, ppm pH@ 25 degree Celsius 9.55 7.80 9.07 7.13 6.70 7.00
- Boron - 10 = Total Boron x 0.196 REMARKS:
17
UNIT 1&2 SPENT FUEL CASK II Castor V/21 500-11-011 Castor V/21 500-11-010 DATE STORED 08/07/90 08/08/90 FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER NUMBER N/A J48 LM034R J50 LM034Z G05
.LMOlQK G06 LMOlQM G07 LMOlQN G13 LM01Q3 J06 LM034P G03 LMOlQQ J29 LM0355 GlO LMOlQB G15 LMOlQA J44 LM035N J35 LM035D J24 LM0350 Gll LM01Q9 J04 LM034E J47 LM034Q J52 LM0362 J27 LM034N J31 LM035B J32 LM035C N/A J02 LM034C Jll LM034H P39 N/A J30 LM034S H24 LMOlQU P25 N/A J43 LM035M J36 LM035K P26 N/A J28 LM034V H17 LMOlQX Jl2 LM034J J14 LM0358 J26 LM034U J25 LM034W JIB LM0352 J21 LM0351 J22 LM0356 P20 N/A P16 N/A H21 LM01R5 18 DATE:
AUGUST 1990 NEW OR SPENT INITIAL FUEL SHIPPING ENRICHMENT CASK ACTIVITY LEVEL 2.9 N/A 2.9 2.1 2.1 2.1 2.1 2.9 2.1 2.9 2.1 2.1 2.9 2.9 2.9 2.1 2.9 2.9 2.9 2.9 2.9 2.9 2.9 N/A 2.9 3.1 2.9 2.6 3.1 2.9 2.9 3.1 2.9 2.6 2.9 2.9 2.9 2.9 2.9 2.9 2.9 3.1 3.1 2.6
UNIT 1&2 SPENT FUEL CASK I Castor V/21 500-11-012 DATE STORED 08/29/90 e
FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER NUMBER N/A K07 LM035X K06 LM035W K05 LM035Y K08 LM0360 3N9 LM06EP 4N3 LM06F2 4N5 LM06GA K04 LM035V 3N8 LM06F4 4Nl LM06EZ EID LM007K 4N8 LM06FD K03 LM035U 3N4 LM06ER 4N2 LM06F6 4N4 LM06F5 4N6 LM06FU K02 LM035T 3N5 LM06G9 3N6 LM06EX KOl LM035Z 19 DATE:
AUGUST 1990 NEW OR SPENT INITIAL FUEL SHIPPING ENRICHMENT CASK ACTIVITY LEVEL 2.6 N/A 2.6 2.6 2.6 3.4 3.4 3.4 2.6 3.4 3.4 2.6 3.4 2.6 3.4 3.4 3.4 3.4 2.6 3.4 3.4 2.6
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DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:
AUGUST 1990 NONE DURING THIS REPORTING PERIOD 20