ML18153A574

Monthly Operating Repts for Dec 1995 for Surry Power Station Units 1 & 2

ML18153A574
Person / Time
Site:	Surry
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)

Text

..

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 11, 1996 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.96-008 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 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 TABLE OF CONTENTS Section e

Surry Monthly Operating Report No. 95-12 Page 2 of 17 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 01-02-96 D. Mason Date:

Completed By:

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 December, 1995 2546 847.5 788 840 801

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 INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

OPERATING DATA REPORT e

Surry Monthly Operating Report No. 95-12 Page 4 of 17 Docket No.:

50-281 01-03-96 D. Mason Date:

Completed By:

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 December, 1995 2546 847.5 788 840 801

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:

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 744.0 744.0 0.0 744.0 0.0 1892329.8 629705.0 610244.0 100.0%

100.0%

102.4%

104.1%

0.0%

YTD 8760.0 7165.4 0.0 7089.0 0.0 17266589.7 5713350.0 5517379.0 80.9%

80.9%

80.1%

79.9%

7.4%

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):

Cumulative 198720.0 135502.9 328.1 133556.1 0.0 312535054.0 102155644.0 97110415.0 67.2%

67.2%

62.6%

62.0%

13.0%

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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

REPORT MONTH: December, 1995 (1)

(2)

(3)

(4)

(5)

Method Docket No.: 50-280 Unit Name:

Surry Unit 1 Date: 01-02-96 Completed by:

Craig Olsen Telephone:

(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No.

Code Code Prevent Recurrence 951207 F

N/A (1)

F:

Forced S: Scheduled F

(2)

REASON:

Down Rx NIA N/A A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction KD 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)

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.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

(1)

Date Type (1)

F:

Forced S: Scheduled (4) 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 L

Docket No.:

50-281 Unit Name:

Surry Unit 2 Date:

01-02-96 Completed by: Craig Olsen Telephone:

(804) 365-2155 (2)

(3)

(4)

(5)

Duration Hours Method of LER No.

Reason Shutting Down Rx System Component Cause & Corrective Action to Code Code Prevent Recurrence None During the Reporting Period (2)

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)

(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.

e Surry Monthly Operating Report No. 95-12 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL MONTH:

December, 1995 Average Daily Power Level Day (MWe-Net) 1 825 2

826 3

826 4

826 5

825 6

825 7

375 8

732 9

826 10 827 11 828 12 827 13 827 14 827 15 827 16 827 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Docket No.: 50-280 Unit Name:

Surry Unit 1 Date: 01-04-96 Completed by:

Barry C. Bryant Telephone: (804) 365-2786 Average Daily Power Level (MWe-Net) 826 827 828 827 827 827 827 826 827 828 826 826 827 828 829 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 MONTH:

December, 1995 Average Daily Power Level Day (MWe-Net) 1 822 2

822 3

822 4

793 5

818 6

821 7

821 8

822 9

821 10 822 11 821 12 821 13 821 14 821 15 821 16 821 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Docket No.: 50-281 Unit Name:

Surry Unit 2 Date:

01-04-96 Completed by:

Barry C. Bryant Telephone:

{804) 365-2786 Average Daily Power Level (MWe-Net) 821 822 822 822 820 810 822 823 823 822 822 822 822 822 823 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

SUMMARY

OF OPERATING EXPERIENCE MoNTHNEAR: December, 1995 Surry Monthly Operating Report No. 95-12 Page 9 of 17 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 12/07/95 12/08/95 12/31/95 UNIT Two:

12/01/95 12/31/95 0000 0230 1000 0049 The reporting period began with the unit operating at 100% power, 853 MWe.

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.

Stopped power reduction at 30%, 220 MWe.

Started power increase following restoration of proper secondary system chemistry.

1017 Stopped power increase at 100%, 850 MWe.

2400 0000 2400 The reporting period ended with the unit operating at 100% power, 850 MWe.

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

The reporting period ended with the unit operating at 100% power, 850 MWe.

DCP 89-004-1 SE 95-179 SE 95-180 e

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December, 1995 Design Change Package (Safety Evaluation No.90-164)

Surry Monthly Operating Report No. 95-12 Page 10 of 17 12-06-95 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.

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 (EDT A) 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.

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.

DCP 93-034-3 JCO S1-95-004 TM S2-95-18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December, 1995 Design Change Package (Safety Evaluation No.94-194)

Surry Monthly Operating Report No. 95-12 Page 11 of 17 12-14-95 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.

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

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

TM S2-95-19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December, 1995 Temporary Modification (Safety Evaluation No.95-187)

Surry Monthly Operating Report No. 95-12 Page 12 of 17 12-26-95 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.

QA Topical Report 1-TOP-4070 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 Operational Quality Assurance Program Topical Report (Safety Evaluation No.95-181) 12-14-95 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.

Temporary Operating Procedure (Safety Evaluation No.95-182) 12-19-95 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 CHEMISTRY REPORT MONTH/YEAR: December, 1995 Unit No. 1 Primary Coolant Analysis Max.

Min.

AvQ.

Gross Radioactivity, µCi/ml 1.02E+O 5.01E-1 7.64E-1 Suspended Solids, ppm

=:;0.010

=:;o.o10

=:;0.010 Gross Tritium, uCi/ml 4.85E-1 3.76E-1 4.20E-1 1131, uCi/ml 2.07E-1 7.66E-3 5.06E-2 113111133 1.00 0.31 0.66 Hvdroaen, cc/ka 44.7 36.3 41.6 Lithium, oom 2.32 2.08 2.19 Boron - 1 O, oom*

239.3 209.3 215.6 Oxygen, (DO), ppm

=:;0.005

,;Q.005

=:;0.005 Chloride, nnm 0.008 0.005 0.006 oH at 25 dearee Celsius 6.64 6.21 6.55 Boron - 10 = Total Boron x 0.196 Comments:

None e

Surry Monthly Operating Report No. 95-12 Page 15 of 17 Unit No. 2 Max.

Min.

AVQ.

1.99E-1 1.01 E-1 1.52E-1

=:;O.Q10

=:;o.o10

=:;O.Q10 2.16E-1 1.14E-1 1.69E-1 5.34E-4 1.04E-4 1.74E-4 0.13 0.06 0.08 44.1 31.6 37.9 2.33 2.06 2.19 127.8 111.5 119.2

=:;0.005

=:;0.005

=:;0.005 0.007 0.002 0.004 7.05 6.63 6.94

FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December, 1995 New or Spent Fuel Shipment Date Stored or Number Received Number of Assemblies per Shipment Assembly Number ANSI Number e

Surry Monthly Operating Report No. 95-12 Page 16 of 17 Initial Enrichment New or Spent Fuel Shipping 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