ML18153D385
| ML18153D385 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/30/1993 |
| From: | Mason D, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-421, NUDOCS 9307190117 | |
| Download: ML18153D385 (19) | |
Text
e e
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 12, 1993 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.93-421 50-280
. 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of June 1993.
Very truly yours,
~~
W. L. Stewart Senior Vice President - Nuclear Enclosure cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-06 Approved:
~ bQ c_ u--r7-- B-C,3 Station Manager Date
TABLE OF CONTENTS Section e
Surry Monthly Operating Report No. 93-06 Page 2 of 18 Page Operating Data Report - Unit No. 1......................................................................................................... 3 Operating Data Report - Unit No. 2......................................................................................................... 4 Unit Shutdowns and Power Reductions - Unit No. 1.................................................................................... 5 Unit Shutdowns and Power Reductions - Unit No. 2.................................................................................... 6 Average Daily Unit Power Level - Unit No. 1.............................................................................................. 7 Average Daily Unit Power Level - Unit No. 2.............................................................................................. 8 Summary of Operating Experience - Unit No. 1......................................................................................... 9 Summary of Operating Experience - Unit No. 2......................................................................................... 9 Facility Changes That Did Not Require NRG Approval............................................................................... 1 O Procedure or Method of Operation Changes That Did Not Require NRG Approval........................................... 12 Tests and Experiments That Did Not Require NRG Approval...................................................................... 15 Chemistry Report............................................................................................................................. 16 Fuel Handling - Unit No. 1................................................................................................................... 17 Fuel Handling - Unit No. 2................................................................................................................... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 18
e Surry Monthly Operating Report No. 93-06 Page3 of 18 OPERATING DATA REPORT Docket No.:
Date:
Completed By:
50-280 07-07-93 D. Mason Telephone:
(804) 365-2459 1. Unit Name:.......................*...........................
- 2. Reporting Period:..........................................
- 3. Licensed Thermal Power (MWt):.......................
- 4. Nameplate Rating (Gross MWe):.......................
- 5.
Design Electrical Rating (Net MWe):..................
- 6.
Maximum Dependable Capacity (Gross MWe):....
- 7.
Maximum Dependable Capacity (Net MWe):........
Surry Unit 1 June, 1993 2441 847.5 788 820 781
- 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. Reasons For Restrictions, If Any:
- 11. Hours In Reporting Period..........................
- 12. Number of Hours Reactor Was Critical..........
- 13. Reactor Reserve Shutdown Hours...............
- 14. Hours Generator On-Line...........................
- 15. Unit Reserve Shutdown Hours.....................
- 16. Gross Thermal Energy Generated (MWH)......
- 17. Gross Electrical Energy Generated (MWH)....
- 18. Net Electrical Energy Generated (MWH)........
- 19. Unit Service Factor...................................
- 20.
Unit Availability Factor...............................
- 21.
Unit Capacity Factor (Using MDC Net)...........
- 22.
Unit Capacity Factor (Using DER Net)...........
- 23.
Unit Forced Outage Rate............................
This Month 720.0 720.0 0.0 720.0 0.0 1751251.0 580910.0 556470.0 100.0%
100.0%
99.0%
98.1%
0.0%
YTD 4343.0 4236.4 0.0 4218.0 0.0 10046983.5 3378920.0 3222918.0 97.1%
97.1%
95.0%
94.2%
2.9%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Scheduled Outage - July 16, 1993, 11 days
- 25. If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
Cumulative 179903.0 119611.4 3774.5 117493.4 3736.2 273666262.6 89397173.0 84820778.0 65.3%
67.4%
60.8%
59.8%
18.0%
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
Surry Monthly Operatin~ Report No. 93-06 Page 4 of 18 OPERATING DATA REPORT Docket No.:
Date:
Completed By:
50-281 07-07-93 D. Mason Telephone:
(804) 365-2459
- 1. Unit Name:...................................................
- 2. Reporting Period:..........................................
- 3.
Licensed Thermal Power (MWt):.......................
- 4.
Nameplate Rating (Gross MWe):.......................
- 5. Design Electrical Rating (Net MWe):..................
- 6.
Maximum Dependable Capacity (Gross MWe):....
- 7. Maximum Dependable Capacity (Net MWe):........
Surry Unit 2 June, 1993 2441 847.5 788 820 781
- 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. Reasons For Restrictions, If Any:
- 11. Hours In Reporting Period..........................
- 12. Number of Hours Reactor Was Critical..........
- 13. Reactor Reserve Shutdown Hours...............
- 14. Hours Generator On-Line...........................
- 15. Unit Reserve Shutdown Hours.....................
- 16. Gross Thermal Energy Generated (MWH)......
- 17. Gross Electrical Energy Generated (MWH)....
- 18. Net Electrical Energy Generated (MWH)........
- 19. Unit Service Factor...................................
- 20. Unit Availability Factor...............................
- 21. Unit Capacity Factor (Using MDC Net)...........
- 22. Unit Capacity Factor (Using DER Net)...........
- 23. Unit Forced Outage Rat~............................
This Month 720.0 705.4 0.0 686.1 0.0 1455871.2 477515.0 455278.0 95.3%
95.3%
81.0%
80.2%
4.7%
YTD 4343.0 2896.1 0.0 2831.1 0.0 6302818.7 2096055.0 1993230.0 65.2%
65.2%
58.8%
58.2%
1.6%
Cumulative 176783.0 116583.0 328.1 114762.1 0.0 267633892.5 87291959.0 82783643.0 64.9%
64.9%
60.1%
59.4%
14.1%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED
(1)
Date Type 930611 s
(1)
F:
Forced S: Scheduled (4) e Surry Monthly Operating Report No. 93-06 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%}
REPORT MONTH: June, 1993 (2)
(3)
(4)
Method (5)
Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-07-93 Completed by: Anthony Xenakis Telephone: (804) 365-2145 Duration of LER System Component Cause & Corrective Action to Hours Reason Shutting No.
Code Code Down Rx 0
B 4
REASON:
A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Prevent Recurrence Started ramp down to permit containment entry for isolation of 1-RC-HCV-15568.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
- Exhibit 1 - Same Source.
(1) e Surry Monthly Operating Report No. 93-06 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: June, 1993 (2)
(3)
(4)
(5)
Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-0?:93 Completed by: Anthony Xenakis Telephone: (804) 365-2145 Duration Method of Reason Shutting Down Rx LER No.
System Component Cause & Corrective Action to Date Type Hours 930601 F
15.6 930620 F
18.3 (1)
F:
Forced S: Scheduled B
A (2)
REASON:
3 NIA S2 002-00 A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction Code Code Prevent Recurrence TA TRB SJ p
Unit maintained at 7% power for main turbine balance shot.
Automatic reactor trip occurred due to a steam flow/feed flow mismatch coincident with a low steam generator level on "A" steam generator. This condition was directly related to the overcurrent trip of 2-FW-P-1 A ("A"Main Feed Pump). The overcurrent trip was the result of a motor ground.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
E Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
(4)
. Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
(5)
Exhibit 1 - Same Source.
Month:
June, 1993 Day 1
2 3
4 5
6
- 7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 93-06 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-07-93 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level Average Daily Power Level (MWe-Net)
Day (MWe-Net) 787 17 771 779 18 771 785 19 772 784 20 766 786 21 771 787 22 761 787 23 774 785 24 770 782 25 772 780 26 774 767 27 771 689 28 770 778 29 769 782 30 763 781 771 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.
Month:
June, 1993 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 93-06 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-07-93 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level Average Daily Power Level (MWe-Net)
Day (MWe-Net) 126 17 777 763 18 775 764 19 780 769 20 143 770 21 399 784 22 510 782 23 481 779 24 472 776 25 482 777 26 478 776 27 482 776 28 484 778 29 477 781 30 475 777 777 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.
e Surry Monthly Operating Report No. 93-06 Page 9 of 18
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: June, 1993 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:
06/01/93 06/11/93 06/12/93 06/30/93 UNIT TWO:
06/01/93 0000 2213 0054 This reporting period began with the Unit operating at 100% power, 815 MW.
Started ramp down to permit containment entry for isolation of 1-RC-HCV-15568.
Stopped ramp; 60% power, 440 MW.
0315 Started ramp up; 60% power, 440 MW.
0758 Stopped ramp; 100% power, 81 O MW.
2400 0000 This reporting period ended with the Unit operating at 100% power, 810 MW.
This reporting period began with the Reactor critical at 7% power to permit performance of a balance shot on the Main Turbine-Generator.
1536 Unit on line.
06/02/93 0223 Unit at 100% power, 825 MW.
06/03/93 06/05/93 06/20/93 06/21/93 06/30/93 0327 Reduced Unit to 98% power due to the receipt of high loop Delta T. on "A" Loop.
0046 Started ramp down to perform 2-PT-6 (Control Rod Partial Movement Test); 97% power, 800MW.
0118 Stopped ramp; 95% power, 780 MW.
031 O Started ramp up; 95% power, 780 MW.
0345 Stopped ramp; 98% power, 805 MW.
1950 Started ramp up after "A" Loop Delta T. was calibrated; 98 % power, 800 MW.
2001 Stopped ramp; 100% power, 815 MW.
0413 2-FW-P-1A ("A" Main Feed Pump) tripped on overcurrent.
0414 Automatic Reactor trip occurred due to steam flow/feed flow mismatch in coincidence with low steam generator level on "A" steam generator.
1847 Reactor critical.
2233 Unit on line.
1420 2400 Unit power at 67% power, 540 MW; power being maintained at 67% until return of "A" Main Feed Pump to service.
This report period ended with the Unit operating at 67% power, 505 MW awaiting the return to service of "A" Main Feed Pump and a High Pressure Heater Drain Pump.
TM S2-93-34 TM S2-93-35 TM S2-93-36 e
Surry Monthly Operating Report No. 93-06 Page 10of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1993 Temporary Modification (Safety Evaluation No.93-122) 06-02-93 This Temporary Modification (TM) installed electrical jumpers to bypass test switch FC-494-TA on the Train "A" Safety Injection (SI) isolation circuitry to allow its replacement without rendering the circuits inoperable.
This TM continued to allow Train "A" SI isolation actuation on a valid signal and did not affect train "B," thus maintaining the design SI isolation functions. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.93-123) 02-93 This Temporary Modification (TM) installed electrical jumpers to bypass test switch FC-474-TA on the Train "A" Safety Injection (SI) isolation circuitry to allow its replacement without rendering the circuits inoperable.
This TM continued to allow Train "A" SI isolation actuation on a valid signal and did not affect train "B," thus maintaining the design SI isolation functions. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.93-124) 06-02-93 This Temporary Modification (TM) installed electrical jumpers to bypass test switch FC-484-TA on the Train "A" Safety Injection (SI) isolation circuitry to allow its replacement without rendering the circuits inoperable.
This TM continued to allow Train "A" SI isolation actuation on a valid signal and did not affect train "B," thus maintaining the design SI isolation functions. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.
TM S2-93-37 TM S2-93-38 TM S2-93-39 e
Surry Monthly Operating Report No. 93-06 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1993 Temporary Modification (Safety Evaluation No.93-126) 6-13-93 This Temporary Modification (TM) installed jumpers on Unit 2 Condensate Polishing Panel A to permit the use of 2-CP-AOV-217 A until out of stock replacement solenoids for 2-CP-OV-217 A and 2-CP-CV-217 A can be obtained.
Electrical and mechanical jumpers were used to place identical installed spares in panel 2-CP-PNL-A in service. Normal functions and controls of 2-CP-AOV-217 are available. Consequently, operation of the Condensate Polishing System is maintained as described in section 10.3.5.2 of the SPS UFSAR. Also, double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No. 91-145-R1) 6-17-93 This Temporary Modification (TM) was required to install a Temporary Vibration Monitoring System to the Unit 2 main turblne. New vibrational pickups were installed and are utilized for new monitors which are located locally on the turbine floor.
The turbine vibration monitors are not described in the UFSAR or a TS LCO and do not interface with.a safety system. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.93-138) 6-22-93 This Temporary Modification (TM) disconnected the defective bearing temperature detector on the 555 ton mechanical refrigeration unit (1-CD-REF-1 B) until repairs can be made. This TM was developed to allow continued operation of 1-CD-REF-1 B without falsely tripping *on high bearing oil temperature.
Bearing oil temperature is monitored as part of the normal turbine building operator rounds. If bearing oil temperature should increase, the operator would promptly notify maintenance to investigate.
The 555 ton mechanical chiller is not safety related and is not used to mitigate the consequences of a UFSAR Chapter 14 accident. The provisions outlined in TS 3.8 regarding containment temperature and pressure will be adhered to.
Therefore, an unreviewed safety question does not exist.
TSl-017 JCO C-93-003 AC S-93-0615 e
Surry Monthly Operating Report No. 93-06 Page 12 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1993 Technical Specification Interpretation (Safety Evaluation No.93-125) 06-11-93 Technical Specification Interpretation TSl-017 was developed to clarify the power supply requirements for an operable residual heat removal (RHR) loop with the Unit at cold or refueling shutdown. (Re: Technical Specifications 1.0.D, 3.0.2, 3.1.A.1.d, 3.1 O.A.6, 3.1 O.A.7, 3.16).
The TSI concludes that: 1) a reactor coolant loop or RHR loop is operable if it is capable of removing decay heat; 2) the power supply requirements of Technical Specification (TS) 3.16 do not apply and, therefore, the RHR pumps need to have only one of their power sources operable; and 3) at least one of the two decay heat removal loops must be operating. This interpretation was discussed with on-site and Region II NRC personnel. The NRC agreed that this TSI is consistent with the applicable TS. Therefore, an unreviewed safety question does not exist.
Justification For Continued Operation (Safety Evaluation No.93-127) 06-15-93 Justification For Continued Operation (JCO) C-93-003 assessed continued operation with a postulated single failure in the rod control system which results in the potential for inadvertent withdrawal of a single rod control cluster assembly.
The assessment concluded that adequate indications and alarms are available to alert the operator to a potential rod control system malfunction and adequate procedures exist to address such a condition.
Furthermore, Technical Specification operability requirements and limiting conditions for operation continue to be fully met. Therefore, an unreviewed safety question does not exist.
Administrative Control (Safety Evaluation No.93-128) 06-15-93 Administrative control of the main control room/emergency switchgear room boundary door was established to allow the door to be blocked open to permit temporary cables and ventilation ducts to be routed through the doorway.
A continuous fire watch was stationed at the door while it was open. The fire watch was responsible for disconnecting the temporary cables and ducts and closing the door in the event of a safety injection, fire, high energy line break, or turbine building flooding. This control action ensured the capability of rapidly restoring the main control room/emergency switchgear room pressure envelope to its required accident condition. Therefore, an unreviewed safety question does not exist.
2-PT-15.8 FS92-141 1-NSP-CC-001 1-NSP-CC-002
-Surry Monthly Operating Report No. 93-06 Page 13 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES.
THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1993 Periodic Test Procedure (Safety Evaluation No.93-129) 06-17-93 Periodic Test Procedure 2-PT-15.8, "Steam Generator Low-Low Level Test," was temporarily changed to provide instructions for verifying the operation of the Steam Generator "A" relays that are required to initiate an auxiliary feedwater pump start signal.
This change involves the lifting of electrical leads to actuation relays and cycling each one (one at a time) to verify contact continuity. This is a conservative action with regard to the logic for turbine driven auxiliary feedwater pump start and steam generator blowdown isolation. Only one motor driven auxiliary feedwater pump train will be in pull-to-lock at a time. The appropriate Technical Specification
, limiting conditions for operation will be entered, as required. Therefore, an unreviewed safety question does not exist.
UFSAR Change 06-21-93 (Safety Evaluation 93-137)
Updated Final Safety Analysis Report Change 93-141 revised section 9.1.2.6.7, "Resin Fill Tank," and Table 9.1-2, "Chemical and Volume Control System Principal Component Data Summary," to reflect the current method of adding resin to the chemical and volume control system (CVCS) demineralizers.
This change involves the use of a small funnel in lieu of the portable resin fill tank.
The funnel is connected to the eves only during the resin fill process when the demineralizer is tagged out of service. This is a routine evolution that is not discussed in the Technical Specifications and will not affect the operation of the eves system. Therefore, an unreviewed safety question does not exist.
Engineering Surveillance Procedures (Safety Evaluation No.93-140) 06-24-93 Engineering Surveillance Procedures 1-NSP-CC-001, "Performance Test of Component Cooling Heat Exchanger 1-CC-E-1 A," and 1-NSP-CC-002, "Performance Test of Component Cooling Heat Exchanger 1-CC-E-1 B," were revised to install a Rosemount pressure transmitter in parallel with the component cooling heat exchanger (CCHX) service water (SW) delta pressure indicator to provide performance data.
The temporary transmitters were installed using fittings and tubing rated for system design pressures. The reliability or integrity of the system was not impacted. Therefore, an unreviewed safety question does not exist.
QA Topical Report TSl-0148 e Surry Monthly Operating Report No. 93-06 Page 14of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1993 Quality Assurance Topical Report (Safety Evaluation No.93-141) 06-25-93 The QA Topical Report was revised to satisfy the requirement for an annual update.
The changes are primarily of an administrative or editorial nature and serve to enhance administrative controls and improve the effectiveness of the quality control program. The changes do not reflect or affect changes to the plant.
Therefore, an unreviewed safety question does not exist.
Technical Specification Interpretation (Safety Evaluation No.93-142) 06-25-93 Technical Specification Interpretation TSl-0148 was developed to describe the actions that need to be taken if a main feedwater regulating valve (MFRV) must be placed on its jack. (Re: Technical Specifications 3.7, Table 3.7-3).
The TSI directed controls permit no more than one MFRV on its jack at one time and for a period not to exceed eight hours. The TSI also requires that the motor operated valve (MOV) associated with the affected main Feedwater line be stroked partially closed to ensure it can be manually closed, if required. In addition, the controls require a dedicated control room operator to close the isolation MOV on a safety injection signal and a dedicated operator (located at the MFRV) to close the MFRV as required. These measures do not affect other accident mitigation systems and ensure that feedwater isolation is achieved within the main steam line break accident analysis assumptions. Accident probability and consequences are not increased. The proposed limited duration and controls to provide alternative isolation assure probability of equipment malfunction has not increased. The margin of safety is assured by diverse and redundant isolation control features. Therefore, an unreviewed safety question does not exist.
e Surry Monthly Operating Report No. 93-06 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1993 None During This Reporting Period
Primarv Coolant Analysis Gross Radioact., uCi/ml Suspended Solids, com Gross Tritium, uCi/ml 1131, uCi/ml 1131/1133 Hydrogen, cc/kg Lithium, oom Boron - 1 O oom*
Oxygen, (DO), ppm Chloride, ppm PH at 25 dearee Celsius Boron - 1 O = Total Boron x 0.196 Comments:
None.
CHEMISTRY REPORT MONTH/YEAR: June, 1993 Unit No.1 Max.
Min.
AvQ.
4.31 E-1 2.68E-1 3.73E-1
< 0.1
< 0.1
< 0.1 2.10E-1 1.77E-1 1.91 E-1 1.25E-3 7.29E-4 9.22E-4 0.13 0.07 0.09 40.5 20.6 31.8 2.32 1.95 2.18 86.4 67.8 76.5
- !'.0.005
- !'.0.005
- !'.0.005
<0.050
<0.001 0.004 7.11 7.00 7.06 e Surry Monthly Operating Report No. 93-06 Page 16 of 18 Unit No. 2 Max.
Min.
Avg.
1.74E-1 4.59E-2 1.32E-1
< 0.1
< 0.1
< 0.1 3.33E-1 2.41E-1 2.89E-1 2.31E-4 2.86E-5 7.89E-5 0.18 0.07 0.11 42.9 15.6 33.0 2.56 2.10 2.26 311.6 254.2 269.4 so.005
- !'.0.005 s0.005
<0.050 0.010 0.014 6.38 6.16 6.28
New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/VEAR: June, 1993 Number of Assemblies per Shipment Assembly Number ANSI Number e Surry Monthly Operating Report No. 93-06 Page 17of 18 Initial Enrichment New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During this Reporting Period.
e Surry Monthly Operating Report No. 93-06 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: June, 1993 None During This Reporting Period