ML18153C539

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Monthly Operating Repts for Jan 1991 for Surry Power Station Units 1 & 2
ML18153C539
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/31/1991
From: Negron M, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-068, 91-68, NUDOCS 9102200068
Download: ML18153C539 (16)
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Text

L VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 14, 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.91-068 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 January 1991.

Very truly yours, Rcf/!~1~

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. W. E. Holland NRC Senior Resident Inspector Surry Power Station

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 91-01 Approved:

2-5-9/

TABLE OF CONTENTS Section Surry Monthly Operating Report No.91-01 Page 2 of 15 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 NRC Approval........................................... 11 Tests and Experiments That Did Not Require NRC Approval...................................................................... 12 Chemistry Report............................................................................................................................. 13 Fuel Handling - Unit No. 1................................................................................................................... 14 Fuel Handling - Unit No. 2................................................................................................................... 14 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 15

Surry Monthly Operating Report No. 91-01 Page 3 of 15 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 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):

1 o. Reasons For Restrictions, If Any:

This Month

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

744.0

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

744.0

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

0.0

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

744.0

15.

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

0.0

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

1807474.0

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

612905.0

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

585097.0

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

100.0%

20.

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

100.0%

21.

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

101.0%

22.

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

99.8%

23.

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

0.0%

YTD Cumulative 744.0 158760.0 744.0 100218.2 0.0 3774.5 744.0 98224.2 0.0 3736.2 1807474.0 228027384.3 612905.0 74189728.0 585097.0 70368226.0 100.0%

61.9%

100.0%

64.2%

101.0%

57.2%

99.8%

56.2%

0.0%

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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

OPERATING DATA REPORT

  • Surry Monthly Operating Report No.91-01 Page 4 of 15 Docket No.:

50-281 02-01-91 M.A. Negron Date:

Completed By:

Telephone:

(804) 357 -3184 x452 1. Un~ 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 January 1991 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): _90_o/c_o~(7_4_0_M_W~e)~------------
10. Reasons For Restrictions, If Any:

_ln_o~pe_r_ab_l_e_c_on_t_ro_l_ro_d~(~M_-_12~)_. _____________ _

This Month YTD Cumulative

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

744.0 744.0 155640.0

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

744.0 744.0 99916.3

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

0.0 0.0 328.1

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

744.0 744.0 98314.6

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

0.0 0.0 0.0

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

1631563.9 1631563.9 229767032.2

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

547310.0 547310.0 74777424.0

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

520191.0 520191.0 70898916.0

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

100.0%

100.0%

63.2%

20.

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

100.0%

100.0%

63.2%

21.

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

89.5%

89.5%

58.4%

22.

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

88.7%

88.7%

57.8%

23.

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

0.0%

0.0%

15.2%

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

Refueling 5 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):

FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED

L Surry Monthly Operating Report No. 91-01 Page 5 of 15 UNIT SHUTDOWN AND POWER REDUCTION (ECUAL To OR GREATER THAN 20%)

REPORT MONTH: January 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 x452 Duration of LER No.

System Component Cause & Corrective Action to Date Type Hours Reason Shutting 01-11-91 s

0.0 (1)

F:

Forced S: Scheduled B

(2)

REASON:

Down Rx 4

NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code Prevent Recurrence TA NIA Ramped to 80% power for Performance of 1-PT-29.1, Turbine Gov. Valve Freedom Test (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.

(1)

.Surry Monthly Operating Report No. 91-01 Page 6 of 15 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MoNTH: January 1991 (2)

(3)

(4)

(5)

Docket No.: 50-281 Unit Name:

Surry Unit 2 Date:

02-01-91 Completed by:

M. A. Negron Telephone:

804-357-3184 x452 Duration Method of Reason Shutting Down Rx LER No.

System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1)

F:

Forced S:

Scheduled (4)

(2)

REASON:

None During This Reporting Period.

A Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

Month:

January 1991 Day 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUCTIONS Surry Monthly Operating Report No. 91-01 Page 7 of 15 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 x452 Average Daily Power Level Average Daily Power Level (MWe - Net)

Day (MWe - Net) 786 17 785 782 18 787 788 19 789 789 20 787 792 21 788 791 22 788 789 23 789 782 24 789 787 25 791 787 26 791 738 27 792 789 28 792 790 29 785 789 30 786 789 31 781 785 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:

January 1991 Day 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUCTIONS Surry Monthly Operating Report No.91-01 Page 8 of 15 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 x452 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 698 17 683 699 18 694 697 19 701 700 20 700 701 21 700 701 22 699 700 23 701 699 24 698 702 25 697 700 26 700 699 27 701 700 28 700 700 29 701 701 30 701 699 31 702 701 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.

Surry Monthly Operating Report No. 91-01 Page 9 of 15

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: January 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.

UNITONE 01-01-91 01-11-91 01-31-91 UNITTWO 01-01-91 01-31-91 0000 1025 This reporting period started with the Unit at 100% power and 825 MWe.

Started ramp down from 100% power and 825 MWe to perform 1-PT-29.1.

1225 Stopped ramp at 80% power and 665 MWe.

1807 Started ramp from 80% power to 100% power.

1905 Reactor at 100% power and 825 MWe.

2400 0000 2400 This report ends with the Unit operating at 100% power and 825 MWe.

This reporting period started with the Unit operating at 90% power and 740 MWe due to an inoperable control rod (M-12).

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

SE 91-001 TMS1-91-01 Surry Monthly Operating Report No. 91-01 Page 10 of 15 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January 1991 Safety Evaluation 01-08-91 A safety evaluation was performed to evaluate the consequences of station operation with the gas stripper removed from service due to extensive maintenance requirements.

Operation of the boron recovery system without the gas strippers does not create an unreviewed safety question. The activity of noble gases in the boron recovery tanks will not significantly increase because the gases that are not removed in the primary drain tank will vent out of the boron recovery tanks to the process vent. The process vent sub-system is a continuously monitored effluent pathway. The probability of occurrence or the consequences of accidents or malfunctions of equipment important to safety, previously evaluated in the safety analysis report has not increased. Normal radiological monitoring will ensure gaseous releases will be within Technical Specification limits.

Temporary Modification (Safety Evaluation No.91-002) 01-10-91 This temporary modification lifted a lead to de-energize relay 33XB-V595. The relay should normally be de-energized, but is energized due to a malfunctioning limit switch, 33BC-V1595 on Unit 1, Loop C Cold Leg Stop Valve, 1-RC-MOV-1595. The relay provides input to block header-to-line SI and lo-lo S/G level reactor trip. The relay also provides input to RCP 'C' trip due to both limit switches on MOV-1595 being closed.

The temporary modification will remove the input from the failed limit switch. Operator cog-nizance will be ensured by use of the Plant Status Log to note that this function will be removed. Current power operation and Technical Specification prohibitions against 2-loop operation makes this a minor concern. However, a malfunction of the other limit switch which provides this input on MOV-1595 could cause RCP 'C' to trip, and thereby a reactor trip. This change will eliminate the reactor trip concern. The temporary modification will be in effect until limit switch repair can be made.

An unreviewed safety question does not exist because UFSAR accident assumptions and analyses encompass any safety concerns raised by this change.

ENG-43 1-TPT-81 2-TPT-81 1 /2-EWR-88-385 Surry Monthly Operating Report No. 91-01 Page 11 of 15 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January 1991 Engineering Procedure (Safety Evaluation No.91-004) 01-14-91 The fouling rate of the Emergency Diesel Generators (EDGs) fuel filters has increased.

This safety analysis addresses the concern that the EDGs may not be able to satisfy the 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> run time specified in Technical Specification 3.16. In order to satisfy Technical Specifications and to maintain the operability of the EDGs, replacement of fuel filters will occur, as required, with the engine running during any event requiring the use of the EDGs.

The ability to change the fuel oil filters with the engine running is a design feature and will not affect the operation of the EDGs. Fuel oil filter changeout has been demonstrated at full load. Failure of an EDG is bounded by the availability of the redundant diesel and Station Procedures.

Because of the capability to change filters with the EDGs running (and loaded), an unreviewed safety question will not be created.

Periodic Test Procedures (Safety Evaluation No.91-013) 01-24-91 1-TPT-81 and 2-TPT-81 provided instructions for determining Excore Power Range detec-tor calibration constants with three flux maps. This procedure change reduces the number of flux maps required to calibrate Excore Power Range detectors to one.

A new methodology has been employed to determine constants for each of the Surry units based on the geometry of each unit's core and detectors.

Since the new methodology will result in calibrations equivalent to or better than multiple -

point calibrations the detectors will continue to function as designed. Therefore, no unreviewed safety question is created.

Engineering Work Request 06-23-89 This Engineering Work Request (EWR) was issued to install Westinghouse type NBFDG5NR relays as replacements for BFD relays. The BFD relays have a high failure rate due to insufficient heat dissipation. The new type utilizes a dual coil design that reduces heating under continuous operation and provides identical performance.

Since the design function is fulfilled with a relay of higher reliability, this change does not constitute an unreviewed safety question.

Surry Monthly Operating Report No. 91-01 Page 12of 15 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: January 1991 None During This Reporting Period.

CHEMISTRY REPORT MONTHNEAR: January 1991 Unit No. 1 Primary Coolant Analysis Max.

Min.

AvQ.

Gross Radioact., µCi/ml 5.73E-1 2.85E-1 4.33E-1 Suspended Solids, oom 0.0 0.0 0.0 Gross Tritium, µCi/ml 3.07E-1 4.86E-2 1.98E-1 1131, uCi/ml 3.08E-3 1.25E-3 1.80E-3 1131, 1133 0.12 0.06 0.09 Hydroaen, cc/kQ 47.2 27.5 39.5 Lithium, oom 2.34 2.06 2.16 Boron - 10, oom*

179.3 166.6 172.4 OxyQen, (DO), oom

<0.005

<0.005

<0.005 Chloride, oom 0.005

<0.001 0.003 pH at 25 demee Celsius 6.56 6.42 6.51 Boron - 1 O = Total Boron x 0.196 Remarks:

No Comments.

Surry Monthly Operating Report No. 91-01 Page 13 of 15 Unit No. 2 Max.

Min.

AvQ.

2.30E-1 1.00E-1 1.43E-1 0.0 0.0 0.0 1.14E-1 7.62E-2 9.21 E-2 7.55E-4 3.42E-4 5.12E-4 0.14 0.06 0.09 46.1 27.4 38.5 1.53 1.02 1.28 31.0 13.7 22.5

<0.005

<0.005

<0.005 0.004

<0.001 0.002 7.43 7.18 7.34

New or Spent Fuel Shipment Date Shipped Number or Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: January 1991 Number for Assemblies per Shipment Assembly Number ANSI Number None During this Reporting Period.

Surry Monthly Operating Report No. 91-01 Page 14 of 15 Initial Enrichment New or Spent Fuel Shipping Cask Activity

Surry Monthly Operating Report No. 91-01 Page 15 of 15 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: January 1991 None During This Reporting Period.

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