ML18153A593

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Jan 1996 for Surry Power Station.W/960212 Ltr
ML18153A593
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/31/1996
From: Bowling M, Olsen C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-075, 96-75, NUDOCS 9602220097
Download: ML18153A593 (16)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 12, 1996 U. S. Nuclear Regulatory Commission Serial No.96-075 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of January 1996.

  • Very truly yours,

!Pi. 8~

M. L. Bowling, Manager Nuclear Licensing & Operations Support 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 9602220097 960131 PDR ADOCK 05000280 JL _ __ _ __ ___ __ PDR-'- ___ _

220016

t /

, 4 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-01 Approved:

~~~JJ~cf1~=--=

Station Manager "1,...~11,..-<;o Date

  • ** Surry Monthly Operating Report No. 96-01 Pag~ 2 of 15 TABLE OF CONTENTS Section 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 R_equire NRC Appro".'al .................. :*********: .. :*********************************************** 10 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
  • OPERATING DATA REPORT
  • . Report Surry Monthly Operating No. 96-01 Page 3 of 15 Docket No.: 50-280 Date: 02-01-96 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . January, 1996
3. Licensed Thermal Power (MWt): ...................... . 2546
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 840
7. Maximum Dependable Capacity (Net MWe): ....... . 801
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 744.0 744.0 202584.0
12. Number of Hours Reactor Was Critical .......... 744.0 744.0 138794.7
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 744.0 744.0 136491 .0
15. Unit Reserve Shutdown Hours ..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1893918.5 1893918.5 318291711.0
17. Gross Electrical Energy Generated (MWH) .... 634205.0 634205.0 104211388.0
18. Net Electrical Energy Generated (MWH) ........ 614423.0 614423.0 99070396.0
19. Unit Service Factor ................................... 100.0% 100.0% 67.4%
20. Unit Availability Factor ............................... 100.0% 100.0% 69.2%
21. Unit Capacity Factor (Using MDC Net) ........... 103.1% 103.1% 63.0%
22. Unit Capacity Factor (Using DER Net) ........... 104.8% 104.8% 62.1%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 16.0%
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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

  • Surry Monthly Operating Report No. 96-01 Page 4 of 15 OPERATING DATA REPORT Docket No.: 50-281 Date: 02-01-96 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . January, 1996
3. Licensed Thermal Power (MWt): ...................... . 2546
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 840
7. Maximum Dependable Capacity (Net MWe): ....... . 801
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 744.0 744.0 199464.0
12. Number of Hours Reactor Was Critical .......... 744.0 744.0 136246.9
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 328.1
14. Hours Generator On-Line ........................... 744.0 744.0 134300.1
15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ...... 1887258.1 1887258.1 314422312.1
17. Gross Electrical Energy Generated (MWH) .... 629355.0 629355.0 102784999.0
18. Net Electrical Energy Generated (MWH) ........ 608707.0 608707.0 97719122.0
19. Unit Service Factor ................................... 100.0% 100.0% 67.3%
20. Unit Availability Factor ............................... 100.0% 100.0% 67.3%
21. Unit Capacity Factor (Using MDC Net) ........... 102.1% 102.1% 62.8%
22. Unit Capacity Factor (Using DER Net) ........... 103.8% 103.8% 62.2%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 13.0%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, May 2, 1996, 37 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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

  • Surry Monthly Operating Report No. 96-01 Page 5 of 15 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: January, 1996 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-02-96 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx None During the Reporting Period (1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

  • Surry Monthly Operating Report No. 96-01 Page 6 of 15 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: January, 1996 Docket No.-: 50-281 Unit Name: Surry Unit 2 Date: 02-02-96 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action to Date Type Hours Reason Shutting Code Code Prevent Recurrence Down Rx None During the Reporting Period (1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

~ .

  • AVERAGE DAILY UNIT POWER LEVEL
  • Surry Monthly Operating Report No. 96-01 Page 7 of 15 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-08-96 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: January, 1996 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day {MWe- Net) 828 17 824 2 829 18 820 3 829 19 817 4 824 20 817 5 828 21 824 6 828 22 827 7 829 23 826 8 828 24 827 9 828 25 826 10 828 26 826 11 828 27 827 12 828 28 826 13 828 29 825 14 828 30 822 15 828 31 824 16 825 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting mbnth. Compute to the nearest whole megawatt.
  • AVERAGE DAILY UNIT POWER LEVEL
  • Surry Monthly Operating Report No. 96-01 Page 8 of 15 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02-08-96 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: January, 1996 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 822 17 823 2 822 18 751 3 823 19 786 4 823 20 819 5 823 21 819 6 822 22 820 7 823 23 819 8 823 24 818 9 823 25 819 10 822 26 820 11 823 27 821 12 823 28 819 13 822 29 822 14 823 30 822 15 822 31 821 16 822 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.
  • Surry Monthly Operating Report No. 96-01 Page 9 of 15

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: January, 1996 The following 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:

01/01/96 0000 The reporting period began with the unit operating at 100% power, 850 MWe.

01/31/96 2400 The reporting period ended with the unit operating at 100% power, 855 MWe.

UNIT Two:

01 /01/96 0000 The reporting period began with the unit operating at 100% power, 850 MWe.

01/18/96 0920 Started power reduction to maintain condenser vacuum while "B" waterbox was removed from service.

1030 Stopped power reduction at 88%, 740 MWe.

01/19/96 0547 Started power increase.

1245 Stopped power increase at 100%, 840 MWe.

01/31/96 2400 The reporting period ended with the unit operating at 100% power, 845 MWe.

FACILITY CHANGES THAT DID NOT

  • Surry Monthly Operating Report No. 96-01 Page 10 of 15 REQUIRE NRC APPROVAL MONTHNEAR: January, 1996 DR S-95-2650 Deviation Report 1-02-96 (Safety Evaluation No.96-001)

Safety Evaluation 96-001 assessed Deviation Report S-95-2650 concerning the loss of capability to obtain a sample from the Unit 1 pressurizer vapor space. The sampling capability was lost as a result of inoperable sample system trip valves which must be maintained in a closed position to satisfy containment integrity requirements.

The evaluation concluded that this condition is acceptable since there are alternate means of sampling the Reactor Coolant System (RCS). Compliance with Technical Specification sampling surveillance requirements continues to be maintained using routine samples obtained from the RCS Letdown Subsystem. Therefore, an unreviewed safety question does not exist.

FS 95-41 Updated Final Safety Analysis Report Change 1/16/96 (Safety Evaluation No.96-003)

UFSAR Change 95-41 revised Section 14.2.6, "Startup of an Inactive Reactor Coolant Loop," to delete references to the loop stop valve interlocks and discussions regarding at-power Startup of an Inactive Loop (SUIL) accidents.

The requirements regarding loop stop valve interlocks were removed from the Technical Specifications by Amendment Nos. 177/176 since the interlocks are no longer credited in the SUIL accident analysis. The discussions of at-power SUIL accidents were removed from the UFSAR since the Technical Specifications preclude the occurrence of such accidents at conditions other than Refueling or Cold Shutdown. These changes are consistent with the current licensing basis. Therefore, an unreviewed safety question does not exist.

FS 96-03 Updated Final Safety Analysis Report Change 1/30/96 (Safety Evaluation No.96-006)

UFSAR Change 96-03 revised Section 11.2.3, "Liquid Waste Disposal System," to reflect the replacement of the radioactive liquid waste demineralization system with an ion exchange/demineralization system at the Surry Radwaste Facility.

The new system will ensure that the effluent release will not exceed 0.1 curies per year, as well as minimizing solid waste disposal. This change will not affect any safety-related systems and will not reduce the margin of safety as defined by the Technical Specifications. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES

  • Surry Monthly Operating Report No. 96-01 Page 11 of 15 THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: January, 1996 O-OPT-VS-002 Operations Periodic Test Procedure 1-20-96 (Safety Evaluation No.96-004)

Operations Periodic Test Procedure O-OPT-VS-002, "Auxiliary Ventilation Filter Train Test," was temporarily changed to provide instructions for administratively controlling the exhaust damper, 2-VS-MOD-201 B, for the Unit 2 "B" charging pump cubicle.

2-VS-MOD-201 B is designed to automatically close when the Unit 2 "B" charging pump is secured. This change allows the damper to be manually cycled to support maintenance activities while the charging pump is removed from service. Appropriate administrative controls are provided in the procedure to allow 2-VS-MOD-201 B to be manually closed (in lieu of the normal automatic closure function) within five minutes following the initiation of a safety injection on either unit. The procedure also prohibits refueling activities on either unit while the subject damper is under administrative control. These measures will ensure adequate charging pump cooling and proper operation of the Auxiliary Ventilation system.

Therefore, an unreviewed safety question does not exist.

1[2]-CSP-HRS-003 Chemistry Surveillance Procedures 1-23-96 (Safety Evaluation No.96-005)

Chemistry Surveillance Procedures 1[2]-CSP-HRS-003, "High Radiation Sampling System: Sampling Containment Air Chemistry Test and Operator Training," were revised to provide instructions for administratively controlling specific containment isolation valves while performing the subject procedure.

The specified containment isolation valves are required to be closed to maintain post accident containment integrity. The administrative controls provided by this change allow the valves to be opened during testing while ensuring compliance with the Technical Specifications. Therefore, an unreviewed safety question does not exist.

O-OPT-VS-002 Operations Periodic Test Procedure 1-30-96 (Safety Evaluation No.96-007)

Operations Periodic Test Procedure O-OPT-VS-002, "Auxiliary Ventilation Filter Train Test," was temporarily changed to provide instructions for administratively controlling exhaust damper, 2-VS-MOD-201 C, for the Unit 2 "C" charging pump cubicle.

2-VS-MOD-201 C is designed to automatically close when the Unit 2 "C" charging pump is secured. This change allows the damper to be manually cycled to support maintenance activities while the charging pump is removed from service. Appropriate administrative controls are provided in the procedure to allow 2-VS-MOD-201 C to be manually closed (in lieu of the normal automatic closure function) within five minutes following the initiation of a safety injection on either unit. The procedure also prohibits refueling activities on either unit while the subject damper is under administrative control. These measures will ensure adequate charging pump cooling and proper operation of the Auxiliary Ventilation system.

Therefore, an unreviewed safety question does not exist.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL

  • Surry Monthly Operating Report No. 96-01 Page 12 of 15 MONTHNEAR: January, 1996 1-ST-314 Special Test 1-12-96 (Safety Evaluation 95-077)

Special Test 1-ST-314, "Steam Generator Moisture Carryover Measurement," was conducted to determine the moisture carryover performance for the Unit 1 steam generators (SG) at the 98% and 100% power levels in order to predict the moisture carryover value at core uprated conditions (i.e., 2546 MWt).

The tests involved the injection of a radioactive tracer (Sodium-24) into each main feedwater (MFW) line downstream of the MFW regulating valves and sampling the main steam lines, SG blowdown, and the common feedwater pump discharge header.

The testing procedures employed controls to prevent any impact on feedwater system performance or the reactor protection function of the SG level circuitry. Therefore, an unreviewed safety question does not exist.

Surry Monthly Operating Report No. 96-01 Page 13 of 15 CHEMISTRY REPORT MONTH/YEAR: January, 1996 Unit No. 1 Unit No. 2 Primary Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioactivitv, uCi/ml 8.95E-1 6.65E-1 8.02E-1 2.11 E-1 1.20E-1 1.62E-1 Suspended Solids, ppm :o;0.01 :o;0.01 :o;0.01 :o;0.01  :,;0.01  :,;0.01 Gross Tritium, uCi/ml 6.55E-1 5.28E-1 5.91 E-1 3.20E-1 2.46E-1 2.86E-1 1131, µCi/ml 2.58E-2 1.17E-2 1.79E-2 2.36E-4 8.43E-5 1.31 E-4 113111133 1.23 0.81 0.95

  • 0.12 0.05 0.08 HydroQen, cc/kQ 40.6 34.8 36.7 41.4 32.8 35.9 Lithium, ppm 2.33 2.06 2.20 2.25 2.06 2.16 Boron - 10, oom* 210.3 198.2 204.3 112.3 95.6 103.9 Oxygen, (DO), ppm :o;0.005 :o;0.005 :o;0.005 :o;0.005 :o;0.005 :o;0.005 Chloride, ppm 0.009 0.004 0.006 0.005 :o;0.001 0.003 pH at 25 dearee Celsius 6.69 6.53 6.61 7.12 6.88 7.04 Boron - 10 = Total Boron x 0.196 Comments:

None

i 1

  • FUEL HANDLING i*

Surry Monthly Operating Report No. 96-01 Page 14 of 15 UNITS 1 & 2 MONTH/YEAR: January, 1996 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No Fuel Received or Stored During the Reporting Period

l.Surry Monthly Operating Report No. 96-01 Page 15 of 15 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: January, 1996 None During the Reporting Period

Retrieved from "https://kanterella.com/w/index.php?title=ML18153A593&oldid=2403116"