ML18152B624

Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr

ML18152B624
Person / Time
Site:	Surry
Issue date:	10/31/1998
From:	Pincus J, Slade D, Steinert J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-680, NUDOCS 9811180008
Download: ML18152B624 (19)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICllMOND, VIRGINIA 23261 e

November 11, 1998 United States Nuclear Regulatory Commission Serial No.98-680 Attention: Document Control Desk SPS Lie/JCS RO 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 The Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of October 1998, is provided in the attachment.

If you have any questions or require additional information, please contact us.

Very truly yours, E. S. Grecheck, Site Vice President Surry Power Station Attachment Commitments made by this letter: None cc: U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

,,-* 9811180008 981031 :

PDR ADOCK 05000280 R . .PDR ,

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-10 Approved:

Date

e e Surry Monthly Operating Report No. 98-10 Page 2 of 18 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 Nos. 1 and 2 ............................................................................................. 9 Facility Changes That Did Not Require NRC Approval ............................................................................................ 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ................................................. 12 Tests and Experiments That Did Not Require NRC Approval .................................................................................. 15 Chemistry Report ..................................................................................................................................................... 16 Fuel Handling - Unit Nos. 1 and 2 ............................................................................................................................ 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 18

e Surry Monthly Operating Report No. 98-10 Page3of18 OPERATING DATA REPORT Docket No.: 50-280 Date: 11/03/98 Completed By: D. L. Slade Telephone: (757) 365-2246

1. Unit Name: ........................................................... . Surry Unit 1

2. Reporting Period: ................................................. . October, 1998

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 Year-To-Date Cumulative

11. Hours in Reporting Period 745.0 7296.0 226680.0

12. Hours Reactor Was Critical 434.0 6314.6 160340.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5

14. Hours Generator On-Line 433.9 6281.8 157881.3

15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) 992451.2 15813968.0 372058983.6

17. Gross Electrical Energy Generated (MWH) 327134.0 5248685.0 122064439.0

18. Net Electrical Energy Generated (MWH) 315118.0 5071615.0 116305836.0

19. Unit Service Factor 58.2% 86.1% 69.6%

20. Unit Availability Factor 58.2% 86.1% 71.3%

21. Unit Capacity Factor (Using MDC Net) 52.8% 86.8% 65.9%

22. Unit Capacity Factor (Using DER Net) 53.7% 88.2% 65.1%

23. Unit Forced Outage Rate 0.0% 6.6% 14.5%

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

Refueling, October 19, 1998, 32 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up: November 19, 1998

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 98-10 Page 4 of 18 OPERATING DATA REPORT Docket No.: 50-281 Date: 11/03/98 Completed By: D. L. Slade Telephone: (757) 365-2246

1. Unit Name: ............................................................ Surry Unit 2

2. Reporting Period: ................................................. . October, 1998

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 Year-To-Date Cumulative

11. Hours in Reporting Period 745.0 7296.0 223561.0

12. Hours Reactor Was Critical 745.0 7296.0 158446.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 328.1

14. Hours Generator On-Line 745.0 7296.0 156429.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1882532.8 18537181.8 3700707 49 .1

17. Gross Electrical Energy Generated (MWH) 628860.0 6172270.0 121297878.0

18. Net Electrical Energy Generated (MWH) 608583.0 5969264.0 115612415.0

19. Unit Service Factor 100.0% 100.0% 70.0%

20. Unit Availability Factor 100.0% 100.0% 70.0%

21. Unit Capacity Factor (Using MDC Net) 102.0% 102.1% 66.1%

22. Unit Capacity Factor (Using DER Net) 103.7% 103.8% 65.6%

23. Unit Forced Outage Rate 0.0% 0.0% 11.4%

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

Refueling, April 19, 1999, 35 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. 98-10 Page 5 of 18 (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October, 1998 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11103198 Completed by: J. R. Pincus Telephone: (757) 365-2863 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx 10119198 s 311H9M C 1 NIA NIA NIA Refueling Outage (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 (NU REG 0161)

• UNIT SHUTDOWN AND POWER REDUCTION e Surry Monthly Operating Report No. 98-10 Page6of18 (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October, 1998 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11 /03/98 Completed by: J. R. Pincus Telephone: (757) 365-2863 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx 10/01/98 s 21H35M B N/A N/A SI Cond Condenser Tube Scraping (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 (NU REG 0161)

• - Surry Monthly Operating Report No. 98-10 Page7of18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11/03/98 Completed by: J C. Steinert Telephone: (757) 365-2837 MONTH: October, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (Mwe - Net) 783 17 689 2 779 18 3 3 774 19 0 4 765 20 0 5 762 21 0 6 753 22 0 7 746 23 0 8 740 24 0 9 737 25 0 10 734 26 0 11 728 27 0 12 722 28 0 13 717 29 0 14 710 30 0 15 702 31 0 16 696 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.

• AVERAGE DAILY UNIT POWER LEVEL e Surry Monthly Operating Report No. 98-10 Page 8 of 18 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11/03/98 Completed by: J. C. Steinert Telephone: (757) 365-2837 MONTH: October, 1998 Average Daily Power Level Average Daily Power Level Day (Mwe - Net) Day (Mwe - Net) 642 17 826 2 759 18 826 3 813 19 825 4 816 20 826 5 819 21 820 6 822 22 823 7 824 23 830 8 824 24 829 9 824 25 866 10 824 26 830 11 825 27 829 12 824 28 828 13 824 29 829 14 824 30 830 15 824 31 830 16 826 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. 98-10 Page 9 of 18

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: October, 1998 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:

10/01/98 0000 Unit in cycle coast down at 97.2% power, 840 MWe.

10/18/98 1745 Commence ramp down, Unit at 84.6% / 710 Mwe.

10/19/98 0151 Unit off line.

10/19/98 0159 Reactor tripped.

10/31/98 2400 Unit 0% power, 0 MWe.

UNIT Two:

10/01/98 0000 Unit operating at 100% power, 842 MWe.

10/01/98 0530 Power reduction started 100%, 825 MWe, to maintain condenser vacuum during water box cleaning.

10/01/98 1600 Unit at 72.5% / 586 Mwe 10/02/98 0505 Commenced ramp up, Unit at 81.5% / 693 MWe 10/02/98 0740 Unit operating at 100% power, 845 MWe.

10/31/98 2400 Unit operating at 100% power, 855 MWe.

FACILITY CHANGES THAT DID NOT REQUIRE NRC e

APPROVAL Surry Monthly Operating Report No. 98-10 Page 10 of 18 MONTHNEAR: October, 1998 FS98-022 UFSAR Change Request 10/01/98 (Safety Evaluation 98-095)

UFSAR Change Request FS98-022 contains numerous editorial changes that correct inaccuracies and clarify or enhance sections of the UFSAR pertaining to the Emergency Diesel Generation and Electrical Power systems. These changes were needed as a result of the Integrated Configuration Management Project and consist of editorial and technical changes/corrections.

DCP 98-040 Design Change Package 10/01/98 (Safety Evaluation 98-096)

Design Change Package 98-040, "Recovery of RS System Spray Flows," changes the normal position, from normally open to normally closed, of various vent and drain valves associated with the Inside and Outside Recirculation Spray Heat Exchanger shell side level switches and shell side drains. The calculated flows lost through the valve created short falls in the delivered flows to the Recirculation Spray System spray rings. Although the short falls were evaluated and found acceptable, they do decrease the available flow margins for each of the Recirculation Spray System pump delivered flows. By closing the identified valves the short falls will be eliminated and the margins increased.

DCP 98-043 Design Change Package 10/01/98 (Safety Evaluation 98-097)

Design Change Package 98-043, "Auxiliary Feedwater Pumps Steam Supply PCVS,"

modifies the Turbine Driven Auxiliary Feedwater System (TDAFWP) circuit logic so that when the pump is started by an automatic signal and then the initiating signal is cleared, the steam flow can only be stopped after the circuit is manually reset. The modification consist of installing two new auxiliary relays for each TDAFWP solenoid operating valve circuit.

DCP 98-025 Design Change Package 10/08/98 (Safety Evaluation 98-100)

Design Change Package 98-025, "Fuel Assembly Repair," describes the reconstitution of fuel assemblies following Unit 1 Refueling Outage. The reconstitution will allow suspect fuel assemblies to be considered for subsequent core reload designs and potentially aid in the determination of the root cause failure mechanism of the assemblies.

SE 98-103 Safety Evaluation 10/14/98 Safety Evaluation 98-103 was performed to evaluate the Reload Safety Evaluation Technical Report and the Reload Safety Analysis Checklist for the refueling and operation of Surry Unit 1 Cycle 16. Cycle 16 will use higher enrichment (up to 4.3 w/o) reload fuel in accordance with Technical Specification Amendment Number 214.

FS98-040 UFSAR Change Request 10/16/98 (Safety Evaluation 98-104)

UFSAR Change Request FS98-040 modifies the refueling reassembly sequence as currently stated in the UFSAR to allow for easier deconning and ease of access of the reactor cavity when retensioning the reactor head studs. The new method of operation is to install the transfer tube blank flange, remove the cavity seal strong backs, and then retention the reactor vessel head studs. The UFSAR currently states that the head studs are retensioned, the cavity seal is removed, and the fuel transfer tube blank flange is then replaced.

FACILITY CHANGES THAT DID NOT REQUIRE e

NRC APPROVAL Surry Monthly Operating Report No. 98-10 Page 11 of 18 MONTHNEAR: October, 1998 SE 98-105 Safety Evaluation 10/16/98 Safety Evaluation 98-105 evaluates the 1998 Unit 1 Refueling Outage against current industry guidelines and Virginia power administrative requirements for shutdown risk management including NUMARC 91-06 and NE Technical Report 865, Rev.3. The schedule provides a plan for safely and efficiently accomplishing refueling, maintenance, modification, and testing activities.

TM S1-98-017 Temporary Modification 10/22/98 (Safety Evaluation 98-109)

Temporary Modification S1-98-017 will be used to install a temporary air supply. The air supply will be used to enable the replacement of an instrument air valve without causing a sample system valve to fail closed thus preventing the ability to pump the contents of the containment sump out of containment. The temporary air line will be installed from an instrument air valve to the inlet of a solenoid operated valve thereby enabling the valve to operate normally.

TM S1-98-018 Temporary Modification 10/26/98 (Safety Evaluation 98-110)

The purpose of Temporary Modification S1-98-018 is to facilitate the use of Valve Operator Testing and Evaluation System (VOTES) on a Condensate Polishing valve. The modification involves the installation of a jumper and lifting of an electrical lead. Without the modification the valve would remain open due to detection of low feedwater suction pressure. The valve needs to be cycled as part of the VOTES testing that will be performed at cold shutdown.

TM S1-98-016 Temporary Modification 10/29/98 (Safety Evaluation 98-111)

The purpose of Temporary Modification S1-98-016 is to install a temporary power supply to the level transmitter for the Component Cooling Surge Tank so that it will continue to provide Unit 1 and Unit 2 operators with level indication while work is being performed in the main board rack. The main board rack being worked provides level indication for both units.

TM S1-98-019 Temporary Modification 10/30/98 (Safety Evaluation 98-113)

The purpose of Temporary Modification S1-98-019 is to bypass the Robertshaw Fire Detection System alarm and the placement of a jumper in the affected CO2 hazard zone panels which will clear the signal from the Robertshaw Fire Detector System. This will clear the "locked in" trouble annunciator window. The modification will include the installation of jumpers. It will eliminate an operator work around to verify operability of the Robert Shaw Detection System on an hourly basis due to the "locked in" annunciator window caused by the tagout of the low pressure CO2 Fire Suppression System for the turbine and generator.

• PROCEDURE OR METHOD OF OPERATION CHANGES THAT Dip NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No. 98-11 Page 12 of 18 MONTHNEAR: October, 1998 01-NSP-CC-001 Engineering Surveillance Procedures 10/24/98 01-NSP-CC-002 (Safety Evaluation 93-140, Rev. 1)

Procedures 01-NSP-CC-001, "Performance Test of Component Cooling Heat Exchanger 1-CC-E-1 A," and 1-NSP-CC-002, "Performance Test of Component Cooling Heat Exchanger 1-CC-E-1 B," were modified to temporarily connect a Rosemount delta pressure transmitter in parallel with the existing pressure instrumentation to allow data collection on the component cooling heat exchangers. The revision to the safety evaluation was to make administrative changes to correctly reference the procedures and to include reference to the pressure rating of the tubing used in the installation.

1/2-MOP-EP-030&031 Maintenance Operating Procedures 10/01/98 1/2-MOP-EP-204,205, (Safety Evaluation 94-190, Rev. 2) 206,&207 Procedures, 1/2-MOP-EP-030&031"Removing From Service and Returning to Service of Station Batteries 1A, 18, 2A, & 28," and l/2-MOP-EP-204,205,206, & 207, for the removal from service and return to service of 4160V bus 1H & 1J, 480V buses 1H, 1H-1, 1J, & 1J-1, and 480V MCC 1H1-1, 1H1-2, 1J1-1, & 1J1-2 are being modified. The modification of the procedures is to describe the plant line-up that establishes the minimum equipment required for safe operation when the DC Buses are cross tied and one battery is disconnected from the DC Bus including the "H" and "J" Emergency Bus outages.

1/2-MOP-EP-030&031 Maintenance Operating Procedures 10/01/98 1/2-EPT-0106-01,02, Electrical Periodic Test Procedures 06,&07 O-ECM-0104-03 Electrical Corrective Maintenance Procedure (Safety Evaluation 96-047, Rev 3)

Procedures, 1/2-MOP-EP-030&031, "Removing From Service and Returning to Service of Station Batteries 1A, 18, 2A, & 28," and l/2-EPT-0106-01, 02, 06, & 07 "Main Station Battery (IA, lB, 2A, 2B) Refueling Service/Performance Test, and O-ECM-0104-03, "Main Station & EOG Battery Freshing Charge," are being modified. The modification of the procedures addresses the plant line-up during the interval that the Main Station Battery leads are disconnected and the DC cross tie is open. The modification also provides for the installation of the Main Station Battery test equipment and jumpering of weak cells, to ensure that the Main Station Batteries can be removed/returned to service within the design basis as stated in the UFSAR. The procedures provide for the installation of a jumper that removes a possible spark producing activity out of the vicinity of the Main Station Battery fill and sample ports.

01-TOP-BC-4087 Temporary Operating Procedure 10/01/98 (Safety Evaluation 98-094)

Procedure 1-TOP-BC-4087, "Bearing Cooling Water System Makeup," is being used to demonstrate that using condensate storage tank water as Bearing Cooling system make-up instead of gland steam will eliminate ammonia and high pH levels in the Bearing Cooling System. In the event that the alternate make-up is unable to be adequate, steps are included in the procedures to ensure proper make-up is obtained by returning to the original line-up. '

• PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID Nor REQUIRE NRC APPROVAL Surry Monthly Operating Report No. 98-11 Page 13 of 18 MONTHNEAR: October, 1998 1/2-PT-36 Periodic Test Procedure 10/06/98 (Safety Evaluation 98-098)

Periodic Test Procedures 1/2-PT-36, "Instrument Surveillance," are being revised to provide instructions that if the Recirculation Spray (RS) sump level is less that five inches, it should be filled to greater than six inches by placing both containment sump pumps in off and overflowing the containment sump into the RS sump. The evaluation was required because the UFSAR states that one containment sump pump is in automatic and the other is in standby.

O-OPT-VS-005 Operations Periodic Test Procedure 10/08/98 (Safety Evaluation 98-101)

Operations Periodic Test Procedure O-OPT-VS-005, "Control Room Leak Test," was revised to act as a procedurally controlled temporary modification to allow the attachment and removal of an orifice plate on the ventilation duct so that the Main Control Room pressure boundary test can be run using the fan.

1-0PT-ZZ-002 Operations Periodic Test Procedures 10/08/98 2-0PT-ZZ-002 (Safety Evaluation 98-102)

Operations Periodic Test Procedures 1/2-0PT-ZZ-002, "ESF Actuation With Undervoltage and Degraded Voltage 1J/2J Bus," were revised to allow functional testing of the auxiliary ventilation fan not connected to the shutdown unit by actually testing the fan controls originating in the shutdown unit. Previous testing of controls was done with the power supply swapped from the operating unit to "J" bus of the shutdown unit.

1-MOP-SW-002 Maintenance Operating Procedures 10/16/98 2-MOP-SW-002 (Safety Evaluation 98-106)

Maintenance Operating Procedures 1-MOP-SW-002 "Alignment of Alternate Discharge for Recirc Spray Service Water Rad Monitor Pumps," and 2-MOP-SW-002 "Alignment of Alternate Discharge for Recirc Spray Service Water Rad Monitor Pumps," were developed to include controlled temporary modifications to route the discharge of the Unit 1 or Unit 2 Recirculation Spray (RS) Heat Exchanger Service Water Radiation Monitor Pumps to a RS Service Water discharge pipe which will remain in service. This activity is necessary to support various outage activities/work involving the RS Service Water discharge pipe.

1-0P-RC-006 Operations Procedures 10/16/98 1-0P-RC-007 (Safety Evaluation 98-107)

Operations Procedures 1-0P-RC-006 "Isolation and Drain of One Reactor Coolant Loop,"

and 1-0P-RC-007 "Isolation and Drain of All Reactor Coolant Loops With RHR in Service,"

were revised to allow exercising the Reactor Coolant System (RCS) loop stop motor operated valves one time prior to isolating a RCS loop for outage maintenance. Exercising the valves once before closure has proven to reduce seat leakage. The cold leg isolation valve interlocks will be defeated, the valve electrically closed, then reopened. The same evolution will follow with the hot leg isolation valve.

e Surry Monthly Operating Report No. 98-11 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: October, 1998 1/2-0SP-TM-003 Operations Surveillance Procedures 10/22/98 (Safety Evaluation 98-108)

Operations Surveillance Procedures 1/2-0SP-TM-003 "Functional Check of Turbine Valves and Limit Switch Operation," are being used as a procedurally controlled temporary modification to test the turbine inlet valves during refueling. The electric overspeed will be de-energized to open the governor and intercept valves that could be energized due to conditions likely to be present during the period in which the test is performed. The fuses for this overspeed solenoid will be pulled to clear the condition to allow opening all required turbine valves.

1-0SP-Sl-002 Operations Surveillance Procedure 10/29/98 (Safety Evaluation 98-112)

Operations Surveillance Procedure 1-0SP-Sl-002 "Charging Pump Head Curve Verification," is being use to control the installation of a temporary flow meter on a Charging pump suction line. The temporary flow meter is needed to gather additional data on the "B" charging pump. The existing flow meter span is too low for the flow conditions required by procedure 1-0SP-Sl-002 which flows the pump on the high end of the pump curve.

1/2-0SP-ZZ-001 Operations Surveillance Procedures 10/30/98 1/2-PT-15.4 Periodic Tests 1/2-PT-15.8 1/2-0PT-ZZ-001 Operations Periodic Tests 1/2-0PT-ZZ-002 1/2-EPT-1801-01 Electrical Periodic Test 1/2-EPT-1801-02 (Safety Evaluation 93-029, Rev. 2)

The procedurally controlled Temporary Modification used various periodic tests and surveillance procedures to lift leads and install jumpers to allow placing charging pump and feedwater breakers in the test position f9r Engineered Safequards Function (ESF) and undervoltage testing including; the defeat of the transfer bus backup trip from emergency bus undervoltage; the defeat of "C" normal charging pump trip from "B" racked out condition; defeat of charging pump low header pressure and start; defeat of charging pump close circuit bypass from a racked out condition; defeat of feed water pump bearing oil and normal suction header pressure permissive; simulation of safety injection for an under voltage safety injection; and defeat of charging pump damper opening. The actions prevent an unwanted bus transfer .trip while testing unit response to an under voltage safety injection signal. Revision 2 was issued to clarify that fuel movement within the Fuel Building is not restricted.

\

e e Surry Monthly Operating Report No. 98-10 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1998 None During the Reporting Period

e Surry Monthly Operating Report No. 98-10 Page16of18 CHEMISTRY REPORT MONTHNEAR: October, 1998 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. AvQ. Max. Min. AvQ.

Gross Radioactivity, µCi/ml 4.88E-1 8.75E-4 1.55E-1 1.75E-1 1.26E-1 1.47E-1 Suspended Solids, ppm 0.150 s 0.010 0.036 - - -

Gross Tritium, µCi/ml 2.92E-2 2.09E-2 2.64E-2 5.68E-1 5.43E-1 5.56E-1 1131, µCi/ml 1.74E-1 1.23E-4 2.28E-3 4.09E-4 4.80E-5 1.14E-4 113111133 0.26 0.12 0.18 0.18 0.06 0.10 HvdroQen, cc/kQ 39.4 0.7 18.2 40.0 35.1 38.0 Lithium, oom 0.96 0.27 0.70 2.31 2.05 2.21 Boron - 10, ppm* 484.9 0.20 260.9 104.7 78.2 88.4 Oxygen, (DO), ppm 8.0 so.005 2.9 s0.005 so.005 so.005 Chloride, ppm 0.042 so.001 0.004 0.005 0.002 0.003 pH at 25 deQree Celsius 9.77 4.48 5.59 7.21 6.75 6.99 Boron - 10 = Total Boron x 0.196 Comments:

None

• *Surry Monthly Operating Report No. 98-10 Page17of18 FUEL HANDLING UNITS 1&2 MONTHNEAR: October, 1998 New Fuel Number of New or Spent Shipment or Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Cask No. Received per Shipment Number Number Enrichment Cask Activity None During the Reporting Period

Surry Monthly Operating Report No. 98-10 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: October, 1998 None During the Reporting Period