ML18153D363

Monthly Operating Repts for May 1993 for Surry Power Station Units 1 & 2.W/930610 Ltr

ML18153D363
Person / Time
Site:	Surry
Issue date:	05/31/1993
From:	Bowling M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-365, NUDOCS 9306170374
Download: ML18153D363 (20)

Text

.' '

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 10, 1993 U. S. Nuclear Regulatory Commission Serial No.93-365 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 MONTHL V OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of May 1993.

Very truly yours, M. L. Bowling, Manager Nuclear Licensing & Programs 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 9306170374 930531

• PDR. ; ADOCK 05000280 R . PDR.

. IT~. i I

---

----- ---- ---- - - - - - - ~ - - - - _ __./

e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-05

~£a Station Manager r' G- i:- 5: ::::::.

Date

tlrry Monthly Operating Report No. 93-05 Page 2 of 19 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. .............................................................................. 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 14 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 16

. Chemistry Report ............................................................................................................................. 17 Fuel Handling - Unit No. 1 ................................................................................................................... 18 Fuel Handling - Unit No. 2 ................................................................................................................... 18 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 19

-rry Monthly Operating Report No. 93-05 Page 3of 19 OPERATING DATA REPORT Docket No.: 50-280 Date: 06-07-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . May, 1993

3. Licensed Thermal Power (MWt): ...................... . 2441

4. Nameplate Rating (Gross MWe): ...................... . 847.5

5. Design Electrical Rating (Net MWe): ................. . 788

6. Maximum Dependable Capacity (Gross MWe): .. .. 820

7. Maximum Dependable Capacity (Net MWe): ....... . 781

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

1O. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting Period ......................... . 744.0 3623.0 179183.0

12. Number of Hours Reactor Was Critical ......... . 744.0 3516.4 118891.4

13. Reactor Reserve Shutdown Hours ............. .. 0.0 0.0 3774.5

14. Hours Generator On-Line .......................... . 744.0 3498.0 116773.4

15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) ..... . 1811241.0 8295732.5 271915011.6

17. Gross Electrical Energy Generated (MWH) ... . 608020.0 2798010.0 88816263.0

18. Net Electrical Energy Generated (MWH) ....... . 582758.0 2666448.0 84264308.0

19. Unit Service Factor .................................. . 100.0% 96.5% 65.2%

20. Unit Availability Factor.............................. . 100.0% '96.5% 67.3%

21. Unit Capacity Factor (Using MDC Net).......... . 100.3% 94.2% 60.7%

22. Unit Capacity Factor (Using DER Net) .......... . 99.4% 93.4% 59.7%

23. Unit Forced Outage Rate ........................... . 0.0% 3.5% 18.0%

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

ery Monthly Operating Report No. 93-05 Page 4of 19 OPERATING DATA REPORT Docket No.: 50-281 Date: 06-07-93 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ..............*........................... May, 1993

3. Licensed Thermal Power (MWt): ...................... . 2441

4. Nameplate Rating (Gross MWe):...................... . 847.5

5. Design Electrical Rating (Net MWe): ................. . 788

6. Maximum Dependable Capacity (Gross MWe): ... . 820

7. Maximum Dependable Capacity (Net MWe): ....... . 781

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting Period ......................... . 744.0 3623.0 176063.0

12. Number of Hours Reactor Was Critical ......... . 651.4 2190.7 115877.6

13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 328.1

14. Hours Generator On-Line .......................... . 606.0 2145.0 114076.0

15. Unit Reserve Shutdown Hours.................... . 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) ..... . 1317613.0 4846947.5 266178021.3

17. Gross Electrical Energy Generated (MWH) ... . 435405.0 1618540.0 86814444.0

18. Net Electrical Energy Generated (MWH) ....... . 415224.0 1537952.0 82328365.0

19. Unit Service Factor .................................. . 81.5% 59.2% 64.8%

20. Unit Availability Factor .....*......................... 81.5% 59.2% 64.8%

21. Unit Capacity Factor (Using MDC Net) .......... . 71.5% 54.4% 60.0%

22. Unit Capacity Factor (Using DER Net) .......... . 70.8% 53.9% 59.3%

23. Unit Forced Outage Rate ........................... . 2.1% 0.6% 14.1%

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: June 3, 1993

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

tlrry Monthly Operating Report No. 93-05 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: May, 1993 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-07-93 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (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 930513 s 0 B 4 N/A TA V Unit power was reduced to 80%

in order to perform 1-0SP-TM-001, turbine valve freedom test.

(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)

. m y Monthly Operating Report No. 93-05 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: May, 1993 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-07-93 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (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 930531 F 12.9 B 4 NIA TA TRB Ramped the Unit off line to perform balance shot on main turbine to correct high vibration condition. The reactor remained critical.

(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. 93-05 Page 7of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-07-93 Completed by:

Telephone:

Month: May, 1993 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 782 17 782 2 793 18 783 3 790 19 782 4 789 20 789 5 789 21 787 6 786 22 785 7 788 23 787 8 790 24 784 9 790 25 782 10 788 26 787 11 785 27 782 12 779 28 781 13 743 29 779 14 782 30 779 15 781 31 782 16 779 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. 93-05 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-07-93 Completed by:

Telephone:

Month: May, 1993 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe - Net) 0 17 693 2 0 18 691 3 0 19 694 4 0 20 726 5 0 21 766 6 125 22 768 7 277 23 770 8 445 24 768 9 677 25 777 10 715 26 783 11 725 27 781 12 714 28 783 13 686 29 785 14 695 30 785 15 698 31 279 16 695 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.

eSurry Monthly Operating Report No. 93-05 Page 9 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: May, 1993 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE:

05/01/93 0000 The reporting period began with the Unit operating at 100% power, 825 MWe.

05/13/93 0502 Started ramp down to perform 1-0SP-TM-001, turbine valve freedom test; 100% power, 820MWe.

0745 Stopped ramp; 80% power, 660 MWe.

1253 Started ramp up; 80% power, 660 MWe.

1410 * *stopped ramp; 100% power, 820 MWe.

05/31/93 2400 The reporting period ended with the Unit operating at 100% power, 820 MWe.

UNIT TWO:

05/01/93 0000 The reporting period began with the Unit at hot shutdown (HSD) preparing to start up from a scheduled refueling outage.

05/04/93 2035 Reactor critical.

05/05/93 1946 Unit at 2% power and stabilized on the main steam dumps.

05/06/93 0510 Unit on line.

0545 Unit at 30% power on chemistry hold.

05/07/93 0820 Started ramp up from 30% power.

191 O Stopped ramp; 61 % power, 460 MWe.

05/08/93 1210 Started ramp up; 60% power, 465 MWe.

2213 Stopped ramp for calorimetric; 70% power, 560 MWe.

05/09/93 0055 Started ramp up; 70% power, 560 MWe.

0700 Stopped ramp; 90% power, 740 MWe.

05/10/93 0657 Started ramp up; 90% power, 740 MWe.

0727 Stopped ramp; 92% power; reactor coolant system loop "A" delta T indicated 100% power.

1202 Started ramp up; 92% power, 760 MWe.

1333 Stopped ramp due to "C" steam generator feedwater flow oscillations; 95.5% power.

1335 Reduced power to 93% power to stabilize feedwater flow on "C" steam generator.

e Surry Monthly Operating Report No. 93-05 Page 10 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: May, 1993 UNIT JWO {Continued):

05/11/93 1208 Started ramp down to test No. 4 turbine governor valve; 91 % power, 750 MWe.

1212 Stopped ramp; 89.7% power, 740 MWe.

1335 Started ramp up; 89.7% power, 740 MWe.

1540 Stopped ramp at 98.5% power.

1603 Started ramp down to stabilize Unit from 2% power swings resulting from feedwater flow oscillations on "C" steam generator.

1614 Stopped ramp; 95% power, 780 MWe.

1702 Started ramp down to place "C" feedwater regulating valve in automatic control mode; 92%

power, 760 MWe.

1841 Stopped ramp; 89.5% power, 740 MWe.

05/12/93 2107 Removed first point feedwater heaters from service for maintenance.

05/20/93 1438 Started ramp up; 91 % power, 730 MWe.

1919 Stopped ramp; 100% power, 825 MWe.

2050 Power reduced to 98% to stabilize unit from "C" steam generator feedwater flow oscillations.

05/25/93 0437 Started ramp up; 98% power, 800 MWe.

0511 Stopped ramp; 100% power, 820 MWe.

05/31/93 0552 Started ramp down due to turbine vibrations; 100% power, 820 MWe.

1109 Unit off line.

1115 Reactor power at 2%.

05/31/93 2400 The reporting period ended with the Unit off line and the reactor at 7% power.

e -rry Monthly Operating Report No. 93-05 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1993 TM S2-93-21 Temporary Modification 05-01-93 (Safety Evaluation No.93-105)

Temporary Modification S2-93-21 installed electrical jumpers to maintain power to certain Unit 2 reactor protection (RP) system train A circuit relays during the replacement of a RP system relay FC3-XA.

The activity was performed while Unit 2 was shutdown with the reactor trip breakers open. The operation of other systems was not affected. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

TM S2-93-22 Temporary Modification 05-01-93 (Safety Evaluation No.93-106)

Temporary Modification S2-93-22 installed electrical jumpers to maintain power to certain Unit 2 reactor protection (RP) system train B circuit relays during the replacement of a RP system relay FC3-XB.

The activity was performed while Unit 2 was shutdown with the reactor trip breakers open. The operation of other systems was not affected. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

TM S2-93-23 Temporary Modification 05-01-93 (Safety Evaluation No.93-107)

Temporary Modification S2-93-23 installed electrical jumpers to maintain power to certain Unit 2 reactor protection (RP) system train B circuit relays during the replacement of a RP system relay P10-XB.

The activity was performed while Unit 2 was shutdown with the reactor trip breakers open. The operation of other systems was not affected. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

FS 93-12 UFSAR Change 05-06-93 (Safety Evaluation 93-110)

Updated Final Safety Analysis Report Change 93-12 revised section 2.2.1, "Meteorological Program," to reflect previously approved changes to the meteorological monitoring system equipment and to include historical data.

This was an administrative change that did not affect the control functions, data collection, or reporting requirements of the system. Therefore, an unreviewed safety question does not exist.

9my Monthly Operating Report No. 93-05 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1993 TM S2-93-31 Temporary Modification 05-13-93 (Safety Evaluation No.93-113)

Temporary Modification S2-93-31 installed a temporary 120 volt AC power strip from the radiation monitor cabinet 2-1 power supply to radiation monitor cabinet 2-2.

This modification returned cabinet 2-2 to service following the failure of its Sola transformer. This alignment does not constitute any additional emergency bus loading since both cabinets are normally powered from the 2H1 -1 motor control center. Therefore, an unreviewed safety question does not exist.

TM S1-93-06 Temporary Modification 05-22-93 (Safety Evaluation No.93-115)

Temporary Modification S1-93-06 installed temporary blind flanges and pipe supports to facilitate the replacement of service water system strainer 1-VS-S-1A and valves 1-SW-301 and 1-SW-302.

The blind flanges met the criteria for the piping class for which they were used and an in-service leak test was performed to verify the adequacy of their installation. The applicable Technical Specification limiting conditions for operation were adhered to during this activity. Therefore, an unreviewed safety question does not exist.

TM S2-93-32 Temporary Modification 05-24-93 (Safety Evaluation No.93-117)

Temporary Modification S2-93-32 removed a control fuse to prevent a spurious Unit 2 Hi Hi Consequence Limiting Safeguards (CLS) train B signal while trouble shooting to identify a DC ground.

This modification affected only Hi Hi CLS train B. The Hi Hi CLS train A remained capable of performing its design function. Technical Specification action statements were adhered to during this activity. Therefore, an unreviewed safety question does not exist.

TM S2-93-33 Temporary Modification 05-24-93 (Safety Evaluation No.93-116)

Temporary Modification S2-93-32 de-terminated an electrical lead to prevent a spurious Unit 2 Hi Consequence Limiting Safeguards (CLS) train B safety injection (SI) actuation signal while trouble shooting to identify a DC ground.

This modification affected only the Hi CLS train B. The Hi CLS train A remained capable of performing its design function. Technical Specification action statements were adhered to during this activity. Therefore, an unreviewed safety question does not exist.

.urry Monthly Operating Report No. 93-05 Page 13 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1993 TM S1-93-07 Temporary Modification 05-25-93 (Safety Evaluation No.93-119)

Temporary Modification S1-93-07 installed a temporary ventilation duct and configured dampers to redirect cooling air from the Protective Clothing Issue and Dressing area to supply cooling air to the Health Physics Count Room. This modification will remain in place until repairs can be made to the air conditioner (1-VS-AC-3) that normally supplies the Health Physics Count Room.

This modification will improve the reliability of the radiation monitoring equipment used in post accident analysis (while 1-VS-AC-3 is out of service) and will not affect any safety-related systems or components. Therefore, an unreviewed safety question does not exist.

• EWR 90-275 "* Engineering Work Request 05-26-93 (Safety Evaluation No.90-242)

Engineering Work Request 90-275 installed a manually operate.d drain valve in Unit 1 waste gas system pipe spool 2"-GW-24-154.

This modification provides a means for draining accumulated condensate downstream of relief valve 01-RV-GW-103. This will improve the reliability of the relief valve since an accumulation of condensate could impair its operation (through corrosion) and increase the potential for water hammer upon valve actuation. This change does not affect the function or performance characteristics of the waste gas system. Therefore, an unreviewed safety question does not exist.

erry Monthly Operating Report No. 93-05 Page 14 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1993 SE 93-109 Safety Evaluation 05-04-93 Safety Evaluation 93-109 assessed continued operation of Units 1 and 2 with the containment sump sampling capability of the high radiation sampling sink (HRSS) out of service.

• The assessment concluded that the Emergency Response Procedures provide alternate methods for making core damage assessments. In addition, the HRSS containment sump sampling capability is not assumed in the basis for any Technical Specification. Therefore, an unreviewed safety question does not exist.

2-0P-5.1.5 Operating Procedure 05-05-93 (Safety Evaluation No.93-103)

Operating Procedure 2-0P-5.1.5, "Venting the PRT," was revised to provide direction for continuously venting the Unit 2 pressurizer relief tank (PRT) to the containment atmosphere via PRT pressure transmitter PT-2472. This change was made in order to maintain PRT pressure low and to allow stabilization of pressurizer safety and power operated relief valve tailpipe conditions.

The containment atmosphere will be monitored by the containment particulate and gaseous radiation monitors during the venting process. Activity samples will be obtained every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and weekly grab samples will be obtained on a weekly basis in the event these monitors become inoperable. The venting process will be performed at a slow rate and will be terminated if the containment radiation monitors alarm or if samples indicate adverse (explosive) gas concentrations. The release of the PRT contents to the containment atmosphere does not pose any design or operational concerns and has no impact on the UFSAR accident analyses. Therefore, an unreviewed safety question does not exist.

1-0P-5.1.5 Operating Procedure 05-11-93 (Safety Evaluation No.93-112)

Operating Procedure 1-0P-5.1.5, "Venting the PRT," was revised to provide direction for continuously venting the Unit 1 pressurizer relief tank (PRT) to the containment atmosphere via PRT pressure transmitter PT-1472. This change was made in order to maintain PRT pressure low and to allow stabilization of pressurizer safety and power operated relief valve tailpipe conditions.

The containment atmosphere will be monitored by the containment particulate and gaseous radiation monitors during the venting process. Activity samples will be obtained every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and weekly grab samples will be obtained on a weekly basis in the event these monitors become inoperable. The venting process will be performed at a slow rate and will be terminated if the containment radiation monitors alarm or if samples indicate adverse (explosive) gas concentrations. The release of the PRT contents to the containment atmosphere does not pose any design or operational concerns and has no impact on the UFSAR accident analyses. Therefore, an unreviewed safety question does not exist.

9my Monthly Operating Report No. 93-05 Page 15 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: May, 1993 1-PT-17.7 Periodic Test Procedure 05-14-93 (Safety Evaluation No.93-114)

Periodic Test Procedure 1-PT-17.7, "Recirculating Spray HX Service Water Radiation Monitor Pump Test," was temporarily changed to install electrical jumpers to allow the consequence limiting safeguards (CLS) automatic start features of Unit 1 recirculating spray heat exchanger service water radiation monitor sample pumps 1-SW-P-SA, 1-SW-P-58, 1-SW-P-SC, and 1-SW-P-5D to be tested.

Installation of the electrical jumpers will not affect other systems or components.

The applicable Emergency Operating Procedures (EOP) will be revised to require verification that the subject pumps have automatically started upon receipt of a Hi

.Hi CLS signal. The EOPs will also direct appropriate actions to minimize the potential for a radioactive release in the event the pumps do not start. Therefore, an unreviewed safety question does not exist.

O-ECM-1403-01 Electrical Corrective Maintenance Procedure 05-27-93 (Safety Evaluation No.93-121)

Electrical Corrective Maintenance Procedure O-ECM-1403-01, "RCP Motor Disconnect and Connect," was revised to provide instructions for implementing temporary modifications to defeat the Units 1 and 2 reactor coolant pump (RCP) breaker interlocks. These modifications are needed to facilitate the performance of an uncoupled RCP motor run without relying on bearing lift oil pressure switches and loop stop valve position.

The breaker interlocks that are defeated by this procedure are not needed during an uncoupled RCP motor run since there is no flow path requirements. The performance of this procedure will not affect the reactor coolant system and does not affect other accident mitigating equipment. Therefore, an unreviewed safety question does not exist.

e .urry Monthly Operating Report No. 93-05 Page 16 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1993 None During This Reporting Period

.urry Monthly Operating Report No. 93-05 Page 17of 19 CHEMISTRY REPORT MONTH/YEAR: May, 1993 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Ava. Max. Min. Ava.

Gross Radioact., µCi/ml 5.01 E-1 3.17E-1 3.79E-1 1.61E-1 7.43E-4 1.02E-1 Suspended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, uCi/ml 2.1 SE-1 1.99E-1 2.0SE-1 1.55E-1 2.0SE-2 9.37E-2 r131, uCi/ml 1.13E-3 5.99E-4 8.56E-4 5.05E-4 3.49E-5 1.07E-4 1131/1133 0.12 0.07 0.09 0.22 0.07 0.14 Hvdroaen, cc/ka 41.7 28.9 35.2 45.0 24.5 37.2 Lithium, oom 2.27 2.07 2.19 3.54 1.25 2.39 Boron - 10, oom* 102.3 84.7 93.3 469.4 257.0 325.2 Oxygen, (DO), ppm  :;;0.005  :;;0.005  :;;0.005 ,:;;.0.005  :;;0.005 ,:;;.0.005 Chloride, oom 0.006 0.001 0.002 0.025 0.003 0.013 pH at 25 degree Celsius 7.08 6.82 6.95 6.52 5.53 6.21

• Boron - 1O = Total Boron x 0.196 Comments:

Unit 2 On-line 5/6/93.

~- -

.urry Monthly Operating Report No. 93-05 Page 18 of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: May 1993 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 this Reporting Period.

.r

• tlturry Monthly Operating Report No. 93-05 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: May, 1993 None During This Reporting Period.