ML18153A574

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Monthly Operating Repts for Dec 1995 for Surry Power Station Units 1 & 2.W/960111 Ltr
ML18153A574
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/31/1995
From: Bryant B, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-008, 96-8, NUDOCS 9601240076
Download: ML18153A574 (18)
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Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 e

January 11, 1996 U.S. Nuclear Regulatory Commission Serial No.96-008 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 December 1995.

Very truly yours, lfKA~

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 9601240076 951231 PDR ADOCK 05000280 R PDR 24oc, 19

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-12 Approved:.

i'\JJ~-$f-'}£,

Station Manager Date

e e Surry Monthly Operating Report No. 95-12 Page 2 of 17 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 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 ................................................................................................... 17

  • OPERATING DATA REPORT

-Surry Monthly Operating Report No. 95-12 Page 3 of 17 Docket No.: 50-280 Date: 01-02-96 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . December, 1995
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 8760.0 201840.0
12. Number of Hours Reactor Was Critical .......... 744.0 7581.0 138050.7
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 744.0 7506.0 135747.0
15. Unit Reserve Shutdown Hours ..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1856828.4 17944053.3 316397792.5
17. Gross Electrical Energy Generated (MWH) .... 620980.0 5963350.0 103577183.0
18. Net Electrical Energy Generated (MWH) ........ 601967.0 5746950.0 98455973.0
19. Unit Service Factor ................................... 100.0% 85.7% 67.3%
20. Unit Availability Factor ............................... 100.0% 85.7% 69.1%
21. Unit Capacity Factor (Using MDC Net) ........... 101.0% 83.6% 62.8%
22. Unit Capacity Factor (Using DER Net) ........... 102.7% 83.3% 61.9%
23. Unit Forced Outage Rate ............................ 0.0% 2.8% 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

  • OPERATING DATA REPORT e Surry Monthly Operating Report No. 95-12 Page 4 of 17 Docket No.: 50-281 Date: 01-03-96 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . December, 1995
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 8760.0 198720.0
12. Number of Hours Reactor Was Critical ......... . 744.0 7165.4 135502.9
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 328.1
14. Hours Generator On-Line .......................... . 744.0 7089.0 133556.1
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ..... . 1892329.8 17266589.7 312535054.0
17. Gross Electrical Energy Generated (MWH) ... . 629705.0 5713350.0 102155644.0
18. Net Electrical Energy Generated (MWH) ....... . 610244.0 5517379.0 97110415.0
19. Unit Service Factor .................................. . 100.0% 80.9% 67.2%
20. Unit Availability Factor.............................. . 100.0% 80.9% 67.2%
21. Unit Capacity Factor (Using MDC Net) .......... . 102.4% 80.1% 62.6%
22. Unit Capacity Factor (Using DER Net) .......... . 104.1% 79.9% 62.0%
23. Unit Forced Outage Rate ........................... . 0.0% 7.4% 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

  • UNIT SHUTDOWN AND POWER REDUCTION e Surry Monthly Operating Report No. 95-12 Page5 of 17 (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: December, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01-02-96 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 951207 F N/A F NIA N/A KD SG Power reduced to 30% due to an increase in the concentration *of sodium in the secondary system during the performance of Special Test 1-ST-314, Steam Generator Moisture Carryover Measure-ment.

(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)

e Surry Monthly Operating Report No. 95-12 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: December, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 L

Date: 01-02-96 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)

e Surry Monthly Operating Report No. 95-12 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01-04-96 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: December, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 825 17 826 2 826 18 827 3 826 19 828 4 826 20 827 5 825 21 827 6 825 22 827 7 375 23 827 8 732 24 826 9 826 25 827 10 827 26 828 11 828 27 826 12 827 28 826 13 827 29 827 14 827 30 828 15 827 31 829 16 827 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.

e Surry Monthly Operating Report No. 95-12 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 01-04-96 Completed by: Barry C. Bryant Telephone: {804) 365-2786 MONTH: December, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 822 17 821 2 822 18 822 3 822 19 822 4 793 20 822 5 818 21 820 6 821 22 810 7 821 23 822 8 822 24 823 9 821 25 823 10 822 26 822 11 821 27 822 12 821 28 822 13 821 29 822 14 821 30 822 15 821 31 823 16 821 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.

  • e Surry Monthly Operating Report No. 95-12 Page 9 of 17

SUMMARY

OF OPERATING EXPERIENCE MoNTHNEAR: December, 1995 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:

12/01/95 0000 The reporting period began with the unit operating at 100% power, 853 MWe.

12/07/95 0230 Started power reduction due to elevated sodium concentration levels in the secondary

- system during the performance of Special Test 1-ST-314, Steam Generator Moisture Carryover Measurement.

  • 1000 Stopped power reduction at 30%, 220 MWe.

12/08/95 0049 Started power increase following restoration of proper secondary system chemistry.

1017 Stopped power increase at 100%, 850 MWe.

12/31/95 2400 The reporting period ended with the unit operating at 100% power, 850 MWe.

UNIT Two:

12/01/95 0000 The reporting period began with the unit operating at 100% power, 850 MWe.

12/31/95 2400 The reporting period ended with the unit operating at 100% power, 850 MWe.

  • e Surry Monthly Operating Report No. 95-12 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December, 1995 DCP 89-004-1 Design Change Package 12-06-95 (Safety Evaluation No.90-164)

Design Change Package 89-004-1 replaced the high radiation doors in the Unit 1 containment with a new design that improves the safety of entry and exit to/from high __ _

radiation areas while maintaining the doors in a fully secured position.

The modification did not affect the operation or performance of any safety-related system or the margin of safety of the Technical Specifications. Therefore, an unreviewed safety question does not exist.

SE 95-179 Safety Evaluation 12-06-95 Safety Evaluation 95-179 was performed to evaluate the temporary installation and operation of a Lance Injection skid at the Surry Radwaste Facility (SRF). The equipment will be used to convert liquid ethylene diamine tetra-acetic acid (EDTA) to a solid form.

The EDTA is a component of the liquid waste resulting from the steam generator chemical cleaning process that was performed in 1994.

The Safety Evaluation also assessed the installation and operation of a temporary piping and hose system to transfer the subject liquid waste from temporary storage tanks at the SRF yard area to the Lance Injection skid.

The evaluation concluded that the temporary installation and operation of the Lance Injection skid and associated piping system is acceptable. Adequate spill control measures will be established and the integrity of the SRF systems will be maintained.

Therefore, an unreviewed safety question does not exist.

SE 95-180 Safety Evaluation 12-08-95 Safety Evaluation 95-180 was performed to evaluate the impact of starting the bearing lift pump (BLP) for the Unit 2 Reactor Coolant Pump (RCP), 2-RC-P-1C, while the RCP is running. The purpose for starting the BLP was to attempt to reverse an increasing trend in the 2-RC-P-1C upper thrust bearing temperature.

The evaluation concluded that the subject activity would not adversely affect the operation of the RCP nor the BLP. The RCPs and BLPs are nonsafety-related and are not required for safe shutdown. The activity does not reduce the margin of safety as defined by the Technical Specifications bases and does not pose an unreviewed safety question.

  • FACILITY CHANGES THAT DID NOT
  • Surry Monthly Operating Report No. 95-12 Page 11 of 17 REQUIRE NRC APPROVAL MONTHNEAR: December, 1995 DCP 93-034-3 Design Change Package 12-14-95 (Safety Evaluation No.94-194)

Design Change Package 94-034-3 replaced the check valves in the service water discharge path from the Unit 1 and Unit 2 charging pumps with a spool piece that includes a branch connection and a valve. The new spool piece was installed to provide an alternate flow path to the Unit 1 discharge tunnel for service water leaving the charging pump intermediate seal and lube oil coolers. The alternate flow path will be used in the event that the normal discharge flow path, which has become degraded, becomes unavailable.

The modification did not affect the performance of the charging pump service water sub-system or reduce the margin of safety of the Technical Specifications. Therefore, an unreviewed safety question does not exist.

JCO S1-95-004 Justification for Continued Operation 12-21-95 (Safety Evaluation 95-172, Revision 2)

A welded connection on the Unit 2 "A" steam generator (SG) channel head drain line nozzle recently failed. The cause of the failure was preliminarily identified as transgrannular stress corrosion cracking. Justification For Continued Operation S1 .004 assessed the acceptability of Unit 1 operation since the configuration of the Unit 1 SG

'channel head drain lines is similar to that of the Unit 2 "A" SG.

The subject JCO requires that the Unit 1 Reactor Coolant System (RCS) leakrate continue to be calculated as required by Technical Specifications. In addition, an RCS leakrate calculation is required in the event the containment gas and particulate radiation monitors alarm or fail. A leakrate calculation must also be performed once during each operating shift when the monitors are removed from service. Routine leakage monitoring in accordance with Operations Periodic Test procedure 1-0PT-RC-10.0, "Reactor Coolant Leakage," will continue along with use of Operations Check OC-52, "Identifying Increased RCS Leakage Unit 1," if increased leakage is noted.

Plant safety systems and the failure mechanism provide adequate assurance that the potential RCS leakage paths at the Unit 1 SG channel head drain lines will not pose an unreviewed safety question.

TM S2-95-18 Temporary Modification 12-26-95 (Safety Evaluation No.95-186)

Temporary Modification (TM) S2-95-18 installed an electrical jumper between relays RCP-G and E-D in the Unit 2 condensate polishing panel to maintain the continuity of other circuits during the replacement of relay E-G. Relay E-G provides annunciation in the condensate polishing control room when the effluent conductivity of the 2G polisher is in excess of 0.12 µmhos.

The subject relay was replaced while polisher 2G was out of service. Double verification of jumper installation/removal was performed. The activity did not affect condensate flow through the operating polishers and did not adversely affect steam generator chemistry.

The condensate polishing system is nonsafety-related and is not addressed by the Technical Specifications. Therefore, an unreviewed safety question does not exist.

  • FACILITY CHANGES THAT DID NOT
  • Surry Monthly Operating Report No. 95-12 Page 12 of 17 REQUIRE NRC APPROVAL MONTHNEAR: December, 1995 TM S2-95-19 Temporary Modification 12-26-95 (Safety Evaluation No.95-187)

Temporary Modification (TM) S2-95-19 installed electrical jumpers to maintain .the steam generator low-low level logic and the auxiliary feedwater pump start circuit logic during the replacement of relay LC-494A-XA.

The activity involved train "A" of the Reactor Protection System (RPS) and was implemented with the "A" by-pass breaker closed and the "A" main reactor trip breaker open. RPS train "B" was not affected by the TM. Double verification of jumper installation/removal and post-maintenance testing was performed. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 95-12 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1995 QA Topical Report Operational Quality Assurance Program Topical Report 12-14-95 (Safety Evaluation No.95-181)

The Operational Quality Assurance Program Topical Report, pages 17.2-2 and 17.2-34, were revised to clarify that the operational phase Quality Assurance Program assures that the technical requirements for maintenance and modification activities will be at least equivalent to the original technical requirements, so that structures, systems, and components will perform satisfactorily in service.

The change is consistent with the* Operational Quality Assurance Program, Virginia Power's commitment to ANSI N18.7-1976, "Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power* Plants," Sections 5.2.7 and 5.2.17, and continues to meet the requirements of 10 CFR 50, Appendix B. Therefore, no margin of safety is impacted by this change and an unreviewed safety question does not exist.

1-TOP-4070 Temporary Operating Procedure 12-19-95 (Safety Evaluation No.95-182)

Temporary Operating Procedure 1-TOP-4070, "Reactor Coolant Pump 1B Number 1 Seal Leakoff Bucket Check," was developed to provide instructions for verifying the accuracy of the seal leak-off flow instrumentation for the Unit 1 "B" Reactor Coolant Pump.

Implementation of the subject procedure, which involves the collection and measurement of RCP seal leak-off flow, will not affect the reactor coolant system pressure boundary and will not reduce the margin of safety as described by the Technical Specifications.

Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 95-12 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December, 1995 None During the Reporting Period

.. y

  • e Surry Monthly Operating Report No. 95-12 Page 15 of 17 CHEMISTRY REPORT MONTH/YEAR: December, 1995 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. AvQ. Max. Min. AVQ.

Gross Radioactivity, µCi/ml 1.02E+O 5.01E-1 7.64E-1 1.99E-1 1.01 E-1 1.52E-1 Suspended Solids, ppm  :=:;0.010  :=:;o.o10  :=:;0.010 :=:;O.Q10  :=:;o.o10  :=:;O.Q10 Gross Tritium, uCi/ml 4.85E-1 3.76E-1 4.20E-1 2.16E-1 1.14E-1 1.69E-1 1131, uCi/ml 2.07E-1 7.66E-3 5.06E-2 5.34E-4 1.04E-4 1.74E-4 113111133 1.00 0.31 0.66 0.13 0.06 0.08 Hvdroaen, cc/ka 44.7 36.3 41.6 44.1 31.6 37.9 Lithium, oom 2.32 2.08 2.19 2.33 2.06 2.19 Boron - 1O, oom* 239.3 209.3 215.6 127.8 111.5 119.2 Oxygen, (DO), ppm  :=:;0.005  :,;Q.005  :=:;0.005 :=:;0.005  :=:;0.005  :=:;0.005 Chloride, nnm 0.008 0.005 0.006 0.007 0.002 0.004 oH at 25 dearee Celsius 6.64 6.21 6.55 7.05 6.63 6.94

None

  • FUEL HANDLING e Surry Monthly Operating Report No. 95-12 Page 16 of 17 UNITS 1 & 2 MONTH/YEAR: December, 1995 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

. *

  • Surry Monthly Operating Report No. 95-12 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: December, 1995 None During the Reporting Period
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