ML18153C574

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Monthly Operating Repts for Feb 1991 for Surry Power Station Units 1 & 2
ML18153C574
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/28/1991
From: Negron M, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-137, NUDOCS 9103250383
Download: ML18153C574 (23)
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Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 15, 1991 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.91-137 50-280 50-281 DPR-32 DPR-37 Enclosed in Attachment 1 is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of February 1991. Attachment 2 includes one corrected page from the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of January 1991 submitted to you in a letter (Serial No.91-068) dated February 14, 1991.

Very truly yours, i?J/)~

I rw. L. Stewart 0

Senior Vice President - Nuclear Attachments

1. February 1991 Monthly Operating Report
2. Corrected Page - January 1991 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 9103250383 910228 PDR ADOCK 0500CFJi!O.. I R.

',J.. {

e ATTACHMENT 1

[

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 91-02 Approved:

/..t ~ /1:11

~

TABLE OF CONTENTS Section e Surry Monthly Operating Report No. 91-02 Page 2 of 19 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 NRC Approval............................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval........................................... 13 Tests and Experiments That Did Not Require NRC Approval...................................................................... 14 Chemistry Report............................................................................................................................. 15 Fuel Handling - Unit No. 1................................................................................................................... 16 Fuel Handling - Unit No. 2................................................................................................................... 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 19

.rry Monthly Operating Report No. 91-02 Page 3 of 19 OPERATING DATA REPORT

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 February 1991 2441 847.5 788 820 781 Docket No.:

Date:

Completed By:

Telephone:

50-280 03-05-91 M.A. Negron (804) 357-3184 X 452

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):

1 0. Reasons For Restrictions, If Any:

This Month

11. Hours In Reporting....................................
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............................

672.0 672.0 0.0 672.0 0.0 1629335.0 552475.0 526326.0 100.0%

100.0%

100.3%

99.4%

0.0%

YID 1416.0 1416.0 0.0 1416.0 0.0 3440809.0 1165380.0 1111423.0 100.0%

100.0%

100.5%

99.6%

0.0%

Cumulative 159432.0 100890.2 3774.5 98896.2 3736.2 229660719.3 74742203.0 70894552.0 62.0%

64.4%

57.4%

56.4%

20.4%

24. Shutdowns Schedule 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

e Surry Monthly Operating Report No. 91-02 Page 4 of 19 OPERATING DATA REPORT

1.

Unit Name:...................................................

2.

Reporting Period:..........................................

3.

Licensed Thermal Power (MW!):.......................

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 February 1991 2441 847.5 788 820 781 Docket No.:

Date:

Completed By:

Telephone:

50-281 03-05-91 M.A. Negron (804) 357-3184 X 452

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): _9_0_

0i<_o~(7_4_0_M_W_e)~------------

10. Reasons For Restrictions, If Any:

_l_n~op~e_r_ab_l_e_c_on_t_ro_l _ro_d~(_M_-_12~)_. _____________ _

This Month YTD Cumulative

11. Hours In Reporting....................................

672.0 1416.0 156310.0

12. Number of Hours Reactor Was Critical..........

672.0 1416.0 100588.3

13. Reactor Reserve Shutdown Hours...............

0.0 0.0 328.1

14.

Hours Generator On-Line...........................

672.0 1416.0 98986.6

15. Unit Reserve Shutdown Hours.....................

0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH)......

1474676.3 3106240.2 231241708.5

17. Gross Electrical Energy Generated (MWH)....

495535.0 1042845.0 75272959.0

18.

Net Electrical Energy Generated (MWH)........

470662.0 990853.0 71369578.0

19.

Unit Service Factor...................................

100.0%

100.0%

63.3%

20.

Unit Availability Factor...............................

100.0%

100.0%

63.3%

21.

Unit Capacity Factor (Using MDC Net)...........

89.7%

89.6%

58.6%

22.

Unit Capacity Factor (Using DER Net)...........

88.9%

88.8%

57.9%

23.

Unit Forced Outage Rate............................

0.0%

0.0%

15.1%

24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):

Refueling 29 67 days

25.

If Shut Down at End of Report Period Estimated Date of Start-up:

26. Unit In Test Status (Prior to Commercial Operation):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

e Surry Monthly Operating Report No. 91-02 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February 1991 (1)

(2)

(3)

(4)

(5)

Method Docket No.:

50-280 Unit Name:

Surry Unit 1 Date:

02-01-91 Completed by:

M. A. Negron Telephone:

804-357-3184 x 452 Duration of LER No.

System Component Cause & Corrective Action to Date Type Hours Reason Shutting 02-07-91 s

0 (1)

F:

Forced S:

Scheduled 8

(2)

REASON:

Down Rx 4

NIA A

Equipment Failure (Explain) 8 Maintenance or Test C

Refueling D

Regulatory Restriction Code Code Prevent Recurrence TA V

Ramped unit from 100% power to 75% power to perform turbine valve freedom test (1-PT-29.1 ).

(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.

erry Monthly Operating Report No. 91-02 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February 1991 (1)

(2)

(3)

(4)

(5)

Method Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02-01-91 Completed by:

M. A. Negron Telephone: 804-357-3184 x 452 Duration of LER System Component Cause & Corrective Action to Date Type Hours 02-14-91 s

0 (1)

F:

Forced S: Scheduled Reason B

(2)

REASON:

Shutting No.

Down Rx 4

NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code TA V

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 (NU REG 0161)

Prevent Recurrence Ramped unit from 90% power to 75% power to perform turbine valve freedom test (2-PT-29.1 ).

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

Month:

February 1991 Day 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 91-02 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.:

50-280 Unit Name: Surry Unit 1 Date:

02-01-91 Completed by:

M.A. Negron Telephone:

804-357-3184 X 452 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 787 17 783 788 18 783 789 19 779 789 20 783 788 21 786 788 22 782 722 23 781 788 24 782 791 25 781 790 26 779 789 27 779 790 28 781 790 29 789 30 790 31 786 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:

February 1991 Day 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 91-02 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name:

Surry Unit 2 Date:

02-01-91 Completed by:

M.A. Negron Telephone:

804-357-3184 X 452 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 702 17 699 702 18 700 703 19 700 702 20 703 702 21 701 702 22 702 701 23 703 700 24 703 700 25 702 700 26 702 698 27 702 699 28 703 700 29 683 30 699 31 699 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.

tlrry Monthly Operating Report No. 91-02 Page 9 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: February 1991 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 02-01-91 02-07-91 02-28-91 UNIT TWO 02-01-91 02-14-91 02-28-91 0000 0821 1045 1630 1821 2400 0000 0903 This reporting period started with the Unit operating at 100% power and 825 MWe.

Started ramp down to perform 1-PT-29.1; 100% power, 825 MWe.

Stopped ramp; 75% power, 625 MWe.

Started ramp up after completion of 1-PT-29.1; 75% power, 625 MWe.

Stopped ramp; 100% power, 825 MWe.

This reporting period ended with the Unit operating at 100% power and 825 MWe.

This reporting period started with the Unit operating at 90% power and 735 MWe due to inoperable control rod M-12.

Started ramp down to perform 2-PT-29.1; 90% power, 735 MWe.

1007 Stopped ramp; 75.6% power, 630 MWe.

1155 Started ramp up after completing 2-PT-29.1; 75% power, 630 MWe.

1405 Stopped ramp; 90% power, 740 MWe.

2400 This reporting period ended with the Unit operating at 90% power and 740 MWe due to inoperable control rod M-12.

TM S1-91-03 TM S2-91-01 EWR 90-161

  • rry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1991 Temporary Modification (Safety Evaluation No.91-018)

No. 91-02 Page 10 of 19 02-01-91 This temporary modification (TM) installs a jumper on RIS panel 1D-19 from wire 1A255P to wire 1A255 to disable annunciator 1 D-C3, Boric Acid Tank HI-LO temperature Channel 1.

  • The TM will reduce the number of nuisance alarms associated with Channel 1 being out of service and will be removed upon completion of Channel 1 repairs. The provisions of Technical Specifications 3.2.C.3 will be complied with for the duration of this TM.

Therefore, an unreviewed safety question is not created.

Temporary Modification (Safety Evaluation No.91-019) 02-01-91 This temporary modification (TM) installs a jumper on RIS panel 2D-19 from wire 2A255P to wire 2A255 to disable annunciator 2D-C3, Boric Acid Tank HI-LO temperature Channel 1.

The TM will reduce the number of nuisance alarms associated with Channel 1 being out of service and will be removed upon completion of Channel 1 repairs. The provisions of Technical Specifications 3.2.C.3 will be complied with for the duration of this TM.

Therefore, an unreviewed safety question is not created.

Engineering Work Request (Safety Evaluation No.90-139) 02-06-91 This Engineering Work Request (EWR) installed new seismically designed storage supports for fuel handling tools in the spent fuel pool area. The new supports replace existing temporary supports.

This EWR does not affect the operation or performance of safety related systems or components and does not constitute a change to the UFSAR or Technical Specifications.

Therefore, an unreviewed safety question is not created.

TM S1-91-04 TM S2-91-02 EWR89-708

-rry Monthly Operating Report No. 91-02 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1991

[continued]

Temporary Modification (Safety Evaluation No.91-026) 02-13-91 This temporary modification (TM) installs an alternate Diesel Generator in place of the permanent ISFSI Diesel Generator until maintenance activities are complete.

The ISFSI is a passive installation, with no operations to control, no motorized fans, dampers, louvers, or valves, and no electrically operated cranes or lifts. Electricity is required only for monitoring equipment and convenience lighting. A power loss will result in a temporary loss in data which is not considered of major significance because there are no conditions under which the monitored parameters will change abruptly. A loss of power will not affect the integrity of the casks, jeopardize the safe storage of the fuel, or result in radiological releases. In addition, the normal power feed to the facility will not be intentionally interrupted before, during, or after installation of the temporary diesel generator.

Therefore, this TM does not constitute an unreviewed safety question.

Temporary Modification (Safety Evaluation No.91-027) 02-13-91 This temporary modification (TM) connects a 200# hose to discharge drain valve, 2-WT-2026, on pump 2-WT-P-1068, to provide demineralized water for tank flushing at the new Radwaste Facility. The TM will be installed on a non-radioactive, non-safety related system. The connection will be a quick disconnect type and not in the vicinity of any safety related equipment. The pump will be operated within procedural guidelines, minimizing the potential for pump damage. Therefore, an unreviewed safety question does not exist.

Engineering Work Request (Safety Evaluation No.90-200) 02-21-91 This Engineering Work Request (EWR) added vent valves on Service Water supply lines to the Recirculation Spray Heat Exchangers. The modification was made to increase venting capacity and eliminate vacuum conditions in the lines, while draining.

This EWR does not affect the design requirements or the operation or function of the system. Therefore, an unreviewed safety question does not exist.

JCO 89-100 9rry Monthly Operating Report No. 91-02 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1991

[continued]

Justification for Continued Operation (Safety Evaluation No.91-036) 02-26-91 This Justification for Continued Operation provides for the operation of Unit 1 with the back-up air system for the pressurizer power operated relief valve (PORV), 01-RC-PCV-1456, at a pressure less than the required air pressure in UFSAR Section 4.3.4.2 until repairs can be made.

The impact of this condition on continued power operation and on Overpressure Mitigation System (OPMS) operation was reviewed. Technical Specifications 3.1.G states that OPMS is required below 350°F/450 psig. For the UFSAR Section 14 accident analyses, PORV operation is not assumed to mitigate any accidents. However, JCO 89-100 requires that one pressurizer PORV remain operable until the pressurizer safety valve setpoint issue is resolved. Thus, as long as one pressurizer PORV is operable (the unit has two), this activity does not create an unreviewed S?lfety question for continued power operation.

1-NSP-CC-001 1-NSP-CC-002 1-NSP-CC-004 1-PT-8.3A 4lrry Monthly Operating Report No. 91-02 Page 13 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1991 Performance Test Procedure (Safety Evaluation No.91-023) 02-11-91 Performance test procedures, 1-NSP-CC-001, 1-NSP-CC-002, and 1-NSP-CC-004, for Component Cooling Heat Exchangers 1-CC-E-1 A, 1-CC-E-18, and 1-CC-E-10, respectively, are being changed to remove local thermometers from thermowells and install pressure transducers to flow elements.

This change does not constitute an unreviewed safety question since the system pressure boundary and system performance are not affected.

Periodic Test Procedure (Safety Evaluation No.91-029) 02-14-91 A one-time change to performance test, 1-PT-8.3A, is being made to delay logic testing for the Steam Generator (SG) 2 "A" train high-level until test switch LC-484-TA can be replaced. This change is desired due to the spurious alarms that are generated in non-related protective circuits as a result of the malfunctioning test switch.

Delaying SG 2 "A" train high-level testing will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety, and the margin of safety as the basis for any technical specification will not be reduced. The SG high level logic is not addressed by the Technical Specifications and there are no logic surveillance requirements for these logic circuits. The OBA analyses do not take credit for the turbine trip or feedwater isolation functions provided by the steam generator high level logic circuits. Therefore, an unreviewed safety does not exist.

e 4lrry Monthly Operating Report No. 91-02 Page 14 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL 1-ST-290 MONTH/YEAR: February 1991 Special Test Procedure (Safety Evaluation No.90-240) 02-07-91 This test allows for the collection of flow data while flowing service water through the Recirculation Spray Heat Exchangers, 1-RS-E-18 and 1-RS-E-1 C. The data will be used to verify that the Design Basis flow and long term cooling are adequate to reject Design Basis Heat Loads from containment.

The test was performed with the unit in a refueling shutdown mode. Temporary flow instrumentation was installed in the service water piping to and from the B and C Recirculation Spray Heat Exchangers. The personnel involved with the test were briefed prior to initiating flow through the system.

The test did not constitute an unreviewed safety question since the RCS was less than 350°F and 450 psig and the system is not required to be operable at these conditions. In addition, the test used the same flow path described in the UFSAR and Technical Specifications. Plant operators maintained control of the test via MOV's to start or stop the service water flow. Temporary test equipment installation and removal was performed using approved station procedures.

e CHEMISTRY REPORT MONTH/YEAR: February 1991 Unit No. 1 Primary Coolant Analysis Max.

Min.

Avg.

Gross Radioact., u.Ci/ml 6.05E-1 3.00E-1 4.61 E-1 Susoended Solids, oom 0.0 0.0 0.0 Gross Tritium, µCi/ml 3.73E-1 2.94E-1 3.43E-1 r131, u.Citml 2.18E-3 1.24E-3 1.74E-3 1131, 1133 0.12 0.08 0.09 Hvdroqen, cc/kq 43.1 30.1 37.8 Lithium, oom 2.34 2.05 2.20 Boron - 10, oom*

169.3 156.2 162.5 Oxygen, (DO), ppm

~0.005

~0.005

~0.005 Chloride, oom 0.007 0.004 0.005 pH at 25 degree Celsius 6.64 6.50 6.56 Boron - 1 O = Total Boron x 0.196 Remarks:

No Comments.

e Surry Monthly Operating Report No. 91-02 Page 15 of 19 Unit No. 2 Max.

Min.

Avg.

1.78E-1 1.01 E-1 1.41E-1 0.0 0.0 0.0 1.10E-1 8.83E-2 1.03E-1 7.80E-4 3.50E-4 5.51 E-4 0.12 0.06 0.09 44.1 31.3 38.1 1.16 0.76 0.95 14.5 0.7 7.7

~0.005

~0.005

~0.005 0.006 0.002 0.004 8.14 7.29 7.68

FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: February 1991 Unit One None for this reporting period.

Unit Two New or Spent Fuel Shipment Number 2

Date Received 02-12-91 02-14-91 Number for Assemblies per Shipment 4

12 Assembly Number 1V7 OV1 OV2 OV5 OV6 OV8 1V2 OV9 4V6 OV3 OV4 2V6 2V1 3V2 2V2 1V8

[continued]

ANSI Number LMO m

LMO TSR LMO TSS LMO TSV LMO TSW LMO TSY LMO TI2 LMO TSZ LMO lU2 LMO TST LMO TSU LMO TIG LMO TIB LMO TIN LMO TIC LMO TIS 4lrry Monthly Operating Report No. 91-02 Page 16 of 19 Nominal New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.8%

N/A 3.8%

N/A 3.8%

NIA 3.8%

NIA 3.8%

N/A 3.8%

NIA 3.8%

NIA 3.8%

NIA 4.0%

NIA 3.8%

NIA 3.8%

NIA 3.8%

NIA 3.8%

NIA 3.8%

NIA 3.8%

NIA 3.8%

NIA

---~-

e

.rry Monthly Operating Report No. 91-02 Page 17 of 19 FUEL HANDLING MONTH/YEAR: February 1991 Unit Two [continued]

New or Spent Number for Nominal New or Spent Fuel Shipment Date Assemblies Assembly ANSI Initial Fuel Shipping Number Received Qer ShiQment Number Number Enrichment Cask Activity LMO 3

02-19-91 12 4V2 TTY 4.0%

NIA LMO 4VO nw 4.0%

NIA LMO 2V4 TIE 3.8%

NIA LMO 2V5 TTF 3.8%

NIA LMO OV7 TSX 3.8%

NIA LMO 1V3 TT3 3.8%

NIA LMO 1V4 TI4 3.8%

NIA LMO 2V7 TTH 3.8%

NIA LMO 4V7 TU3 4.0%

NIA LMO 1V6 TIS 3.8%

NIA LMO 3V6 TIS 4.0%

NIA LMO 4V5 TU1 4.0%

NIA LMO 4

02-21-91 12 2V9 TIK 3.8%

NIA LMO 1VO no 3.8%

NIA LMO 2V3 no 3.8%

NIA LMO 2V8 TIJ 3.8%

NIA LMO 2VO TIA 3.8%

NIA LMO 4V4 TUO 4.0%

NIA LMO 3VO m

3.8%

NIA LMO 1V9 TI9 3.8%

NIA LMO 1V1 TI1 3.8%

NIA LMO 1V5 TIS 3.8%

NIA LMO 3V4 na 4.0%

NIA LMO 3V9 nv 4.0%

NIA

[continued]

.rry Monthly Operating Report No. 91-02 Page 18 of 19 FUEL HANDLING MONTH/YEAR: February 1991 Unit Two [continued]

New or Spent Number for Nominal New or Spent Fuel Shipment Date Assemblies Assembly ANSI Initial Fuel Shipping Number Received Qer ShiQment Number Number Enrichment Cask Activit~

LMO 5

02-26-91 12 3V8 nu 4.0%

NIA LMO 3V1 TIM 3.8%

NIA LMO 4V1 TIX 4.0%

NIA LMO 3V3 TIP 4.0%

NIA LMO 5V8 lUE 4.0%

NIA LMO 5V4 lUA 4.0%

NIA LMO 3V7 ITT 4.0%

NIA LMO 4V8 lU4 4.0%

NIA LMO 4V3 nz 4.0%

NIA LMO 3V5 TIR 4.0%

NIA LMO 5V1 lU7 4.0%

NIA LMO 6V4 lUL 4.0%

NIA LMO 6

02-28-91 12 6V1 lUH 4.0%

NIA LMO 5V5 lUB 4.0%

NIA LMO 6V2 TUJ 4.0%

NIA LMO 5V9 lUF 4.0%

NIA LMO 6V3 lUK 4.0%

NIA LMO 4V9 lU5 4.0%

NIA LMO 5V6 lUC 4.0%

NIA LMO 5V7 lUD 4.0%

NIA LMO 5V2 lU8 4.0%

NIA LMO 6VO lUG 4.0%

NIA LMO 5VO lU6 4.0%

NIA LMO 5V3 lU9 4.0%

NIA

e Surry Monthly Operating Report No. 91-02 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: February 1991 None During This Reporting Period.

)

ATTACHMENT 2 CORRECTED PAGE e

.my Monthly Operating Report No.91-01 Page 3 of 15 OPERATING DATA REPORT

1.

Untt 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 January 1991 2441 847.5 788 820 781 Docket No.:

Date:

Completed By:

Telephone:

50-280 02-01-91 M.A. Negron (804) 357-3184 x452

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....................................
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 744.0 744.0 0.0 744.0 0.0 1811474.0 612905.0 585097.0 100.0%

100.0%

101.0%

99.8%

0.0%

YTD 744.0 744.0 0.0 744.0 0.0 1811474.0 612905.0 585097.0 100.0%

100.0%

101.0%

99.8%

0.0%

Cumulative 158760.0 100218.2 3774.5 98224.2 3736.2 228031384.3 74189728.0 70368226.0 61.9%

64.2%

57.2%

56.2%

20.5%

24. Shutdowns Schedule 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

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